american nuclear society eastern regional …

TRANSACTIONS

AMERICAN NUCLEAR SOCIETY

EASTERN REGIONAL

STUDENT CONFERENCE

APRIL 5 - 7 . 1984

OtSTRIBUnONOFIHISDOCUBOITISUNDHnn)

NOTICE

PORTIONS OF THIS REPORT « : -: -LEGIBLE. Ithas been reproduced from tha"best availablecopy to permit the broadest possible avail-ability.

COI;F-G4G417 8—Absts.

DEB4 01511G

W E L C O M E

On behalf of the students, facul ty, and administration of the Universityof Lowell, I would l i ke to welcome you to the 1984 American Nuclear SocietyEastern Regional Student Conference. I t i s our intention to promote ameaningful exchange of ideas in both an informative and interesting manner.

We thank you for coming, and sincerely hope that your attendance proves tobe an enjoyable and worthwhile experience.

Anne Marie LacerteConference Chairman

DISCLAIMER

This report was prepared as an account of work sponsored by an agency of the United StatesGovernment. Neither the United States Government nor any agency thereof, nor any of theiremployees, makes any warranty, express or implied, or assumes any legal liability or responsi-bility for the accuracy, completeness, or usefulness of any information, apparatus, product, orprocess disclosed, or represents that its use would not infringe privately owned rights. Refer-ence herein to any specific commercial product, process, or service by trade name, tradfinark,manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom-mendation, or favoring by the United States Government or any agency thereof. The viewsand opinions of authors expressed herein do not necessarily state or reflect those of theUnited States Government or any agency thereof.

Mm H v IiVlrX j II" If * *•*

DISTRIBUTION OF THIS DOCUMENT IS UNLIMITED

ABOUT THE UNIVERSITY OF LOWELL

The University of Lowell was created i n 1975 by the Commonwealthof Massachusetts, through a merger of the Lowell TechnologicalIns t i tu te and the Lowell State College. F i rs t established as atex t i l e school, the Lowell Text i le Ins t i tu te became the LowellTechnological Ins t i tu te in 1950. The University now consists ofseven colleges: Engineering, Education, Health Professions, LiberalArts, Management Science, Music, and Pure and Applied Sciences.

The Nuclear Engineering curriculum at the University of Lowellwas the f i r s t of i t s kind to be established a t any publ ica l lysupported i ns t i t u t i on i n New England. I t nas been f u l l y accreditedby ABET. The f a c i l i t i e s fo r nuclear research and education at theUniversity are among the most modern at any educational i ns t i t u t i onin the United States. These f a c i l i t i e s include a 1 MW nuclearreactor and a 5.5 MeV Van de Graff accelerator, both located in thePinanski Nuclear Center. Extensive computer f a c i l i t i e s ex is t oncampus, including a CDC Cyber, a Digi ta l VAX system, and a ComputerAided Design system.

The American Nuclear Society student chapter at the Universityof Lowell is a very active Branch. Act iv i t ies in the past few yearshave included: several t r i p s to reactor s i tes , tours of BrookhavenNations1 Laboratory, numerous speakers and f i lms , student-facutlymixers, active par t ic ipat ion in past ANS student conferences, act ivepart ic ipat ion in the meetings of the Northeast Section of the ANS,sponsorship of the 1978 ANS student confernece, and now thesponsorship of the 1984 ANS Eastern Regional Student Conference.

TABLE OF CONTENTS

Agenda 1Description of Events 3List of Participants hJudges Critique 6Catagories and Schedule 7Acknowledgments 8Conference Organization 9

Computer Applications Abstracts ' ASafety and Economics Abstracts : BFusion Abstracts ': CThermal Hydraulics Abstracts 5 DRadiation Studies Abstracts i EEnvironmental Analysis Abstracts 2 FReactor Design and Applications Abstracts $ G

AGENDA

THURSDAY

6:00

FRIDAY

7:45

8:00

8:30

9:00

9:30

PM

AM

AM

AM

AM

AM

12:00 noon

1:30 PM

4:00

5:30

7:30

10:00

SATURDAY

PM

PM

PM

PM

8:30 AM

11:30 AM

Registration/Reception at the Tewksbury Holiday Inn.

Buses leave Holiday Inn for Cumnock Hall

Morning Registration; coffee and donuts in Cumnock Hall

Conference Opening; Address by Dr. Mary McGauvran, VicePresident for Student Affairs.

Briefing of Judges by Dr. James PhelpsBriefing of Authors by Mark Durrenberger

Technical Sessions:A. Computer Applications I EB 311E. Radiation Studies I OS 503C. Fusion OH 428

Buffet Lunch, Cumnock Hall

Technical Sessions:A. Computer Applications I I EB 311E. Radiation Studies I I EB 311B. Safety and Economics OH 428

F. Environmental Analysis OS 503

Buses from Cumnock Hall to Holiday Inn

Buses to downtown Lowell for dinner at the Market Mi l ls

Buses from downtown to Skate-3 (free rol lerskating)

Buses from Skate-3 to Holiday Inn.

Technical Sessions:G. Reactor Design and Applications Holiday InnD. Thermal Hydraulics Holiday Inn

Lunch Break

SATURDAY

1 2 : 0 0 NOON

4:30

6:00

6:30

7:30

PM

PM

PM

PM

AGENDA (continued)

Buses to Seabrook Station

Buses leave Seabrook Station

Buses from Holiday Inn to South Campus.

Wine and Cheese Cocktail Hour

Awards Banquet. Remarks by Dr. Aldo Crugnola, Dean ofthe College of Engineering. Quest speaker, WilliamDemckson, Senior Vice-President of Nuclear Energy,from Public Service of Mew Hampshire.

DESCRIPTION OF EVENTS

Conference opening and brief ing sessions: The formal opening of the conferencew i l l be at 8:30 am, April 6, in Cumnock Kail at the University of Lowell. Anopening address w i l l be given by the Vice President for Student Af fa i rs , Dr.Mary McGauvran. There w i l l be a short br ief ing of the judges by Dr. JamesPhelps, and of the authors by Mark Durrenberger.

Bus Service: Bus service w i l l be provided to and from Cumnock Hall and thehotel on Friday; for the dinner and entertainment on Friday evening; for theSeabrook t r i p Saturday afternoon; and for the awards banquet Saturday night.

Technical Sessions: The technical sessions w i l l be held on the North Campusof the University of Lowell on Friday. A map of the campus w i l l be given andample directions w i l l be posted. The Saturday morning sessions w i l l be heldat the Holiday Inn. Student presentations are to be 15 minites long. Therew i l l be 5 minutes allowed for questions and discussion. Papers w i l l be judgedaccording to the c r i te r ia set forth in the Judge's Critique Form. An awardw i l l be given for the most outstanding paper in each category and w i l l bepresented at the banquet Saturday evening.

Meals: Coffee and donuts w i l l be provided Friday morning and a lunch"sponsored by the University of Lowell w i l l be offered in Cumnock Hall onFriday. Dinner Friday can be purchased at the histor ic Market Mi l ls indowntown Lowell. Saturday's dinner w i l l be provided at the awards banquet.

Entertainment: A fun evening of ro l l e r skating has been planned for Fridaynight. After dinner at the histor ic Market Mi l ls in downtown Lowell busesw i l l bring everyone to the Skate-3 rink for 2 hours of free skating.

University Tours: During the luncheon break on Friday, tours of theUniversity of Lowell Research Reactor, Van de Graaff Accelerator, and relatedf a c i l i t i e s w i l l be conducted. Also tours of the Computer Aided Design andEngineering Center w i l l be offered.

Off-Campus Tours: On Saturday, April 7, a detailed tour of the Seabrook PowerStation, Seabrook, New Hampshire w i l l be conducted. Buses w i l l leave theHoliday Inn at 12:00 noon, and w i l l leave the s i te at 4:30 pm. FLATCLOSED-TOE SHOES MUST BE WORN. Sneakers are not allowed on s i te .

Information about informal sight-seeing tours w i l l be made available atregistrat ion. Participants who wish to v i s i t any of the numerous histor icallandmarks in Massachusetts and New Hampshire may contact any ConferenceCommittee member for further information.

Awards Banquet: The conference w i l l conclude with the awards banquet Saturdayevening at the South Campus banquet ha l l . The social hour begins at 6:30 pmand is followed by dinner at 7:30 pm. After dinner opening remarks w i l l begiven by Dr. Aldo Crugnola, Dean of the College of Engineering, followed by anaddress by guest speaker, William B. Derrickson from Public Service of NewHampshire. After Mr. Derrickson has addressed the conclave, the awards foroutstanding papers w i l l be presented.

LIST OF PARTICIPANTS

(* Author; * * Faculty)

HOWARD UNIVERSITY

Araya AsfawFemi AwolusiMajid Motlagh

MASSACHUSETTS INSTITUTEof TECHNOLOGY

Oluwole A. AdekugbeIonel V. BursucRaymond L. Coxe, J r .Michael H. FellowsVictor IannelloHan~Sem JooKosuke KatoRene J . Led a i r , Jr .V i t t o r i o ParetoDavid Pett iSusan M. Rei l lyRobert J. Wit tShih-Ping Kao

RENSSELAER POLYTECHNIC INSTITUTE

***

**

NORTH CAROLINA STATEUNIVERSITY

Abdel BarakatRoy HarperPeter HastingsCharles S. llenkelDanny MorinMatt RichardsEric SniderChuck StoneDr. Michael Doster * *

NEW JERSEY INSTITUTEof TECHNOLOGY

Wil l iam BraceyGregory E. DzulaDana Y. Fil ipowczRobert HegartyMichael J . KoomanDavid KropaczekJohn V. NikasSal i f Thiam

Wil l iam P. DugganThomas C. HaleySeok H. KimDavid Laf leurRoma MohantiRtndall J . PfluegerGeorgios VarsamisDr. Mark J . EmbrechtsDr. Rusi Taleyarkhan

**

* *

UNITED STATES NAVAL ACADEMY

Hidn. Steve Berninger *Midn. Heide Merk *Midn. Dean M i l l e r *Dr. Martin E. Nelson * *

UNIVERSITY OF FLORIDA

Michael C. CarstensenMichael HoutsHiy LyRuy Montealegre C.Jeffery Samuel sJuan V i t a l iMadeline G. WoodruffCynthia Woody

***

CLEMSON UNIVERSITY

Les RiggsSteve DavenportKaren JonesMikel l MurrayDavid WalkerEdward Vickers

UNIVERSITY OF VIRGINIA

Melvin J . FeatherBouvard HostickaMathew J . SchorKeith SymmersLatresia A. Wilson

****

LIST OF PARTICIPANTS (continued)

UNIVERSITY OF LOWELL

Jama! Abdelghany *Eric AbslquistMi l t iadis Arvanitel l isMichael Barry *Robert Bettinson *Edward BrennanElizabeth BurkeMark CaronFred Carpenito *Tim CaseyDave Chapman *Johnny Chen *Stephen ClaffeySteven CoakleyJoseph CondonMark Durrenberger *Eric EdmundsJames FomenkoByron Frank *William FrenchJohn Gale *James GoudourosRichard GuilianoJoanna HanzMichael Helfn'chMichael HicksTim HolmesInsoo JunSteven LabrecqueAnne Marie LacerteMichael LaghettoLisa Langlois *Ernest LeeRichard LeonardOebbie LepageCindy Lock!in *Mark LukitschJames Ma reel loAnthony MartuscelloCaroline McAndrewsHugh McKenneyDavid McLaughlin *Fred McWiliams *Juan MotaFlorin Muradian *Mark NadeauAndrew NicholsonPedro Perez *David RawsonDavid ReeseJames Robichaud *Raymond RoyMichael Rubin *Allen ScheierShirin Shirazi

Peter Spacher *John StoddardCasper SunWindi SunMichael Tremblay *Lionel WertzDouglas YatesJames YoungDr. Gilbert J. Brown **Dr. John Duffy **Dr. Arthur Mittler **Dr. James Phelps **Dr. Paul RingDr. James SheffProf. John White **Dr. Moses Yeung **

****

UNIVERSITY OF MARYLAND

James M. BarloweRobert Broughman *David R. BrownGeorge Budock *Linda L. BurleyRuth Chiang Carter *Mike CaselliRavi E. ChedalavadaCynthia Clark *Marie DannerDick DuffeyMircea Gavrilas *Bambang HerwantoroScott M. Hi l lSun Lee *Christos M. MakrisJohn Me CordRichard Lee Moore *Angela Munno *David W. MurphyMichelle S. Neuder *Joseph PestanerLaura A. Rossell *Mohsen Sharirli *Frank TalbotWilliam W. Thomas, IIIGinny TilghmanHuong Van NguyenHirad YazdankhahDr. Maria Gavrilas **Dr. M. Modarres **Dr. Frank J. Munno **Dr. Gary A. Pertner **Dr. Marvin L. Roush **

JUDGE'S CRITIQUE FORK

Session Number i Paper Nuraber_

Author's Name_

Judge's Mane

Student's Academic Level: B.S. M.S. Ph.D.

Paper Related to: Undergraduate Work M.S. Thesis _________

Ph.D. Dissertation Other

I. Technical Content; Consider the following factors

Relevance/Significance of Topic* . . . A A- B+ B B- C+ C

Logical Approach and Organization. . . A A- B+ B B- Of C

Interpretation of Results A A- B+ B B- Of C

Completeness A A- B+ B B- Of C

IX. Presentation; Consider the following factors

Abstract A A- B+ B B- Of C

Delivery and Poise A A- B+ B B- Of C

Response to Questions . . . . . . . . A A- B-f B B- Of C

Suggested overall grade • ____________

(Note that the judges will together determine the best papers for the technicalsessions they evaluate)

Remarks (Use back If necessary) .

(Signature of Judge)

CATAGORIES AND SCHEDULE

Cstagories: (A) Computer Appl icat ions(B) Safety and Economics(C) Fusion(D) Thermal-Hydraulics(E) Radiat ion Studies(F) Environmental Analys is(G) Reactor Research and Design

Schedule

FRIDAY:

9:30 am9:50 am10:10 am10:30 am10:50 am11:10 am11:30 am

1:20 pm1:40 pm2:00 pm2:20 pm2:40 pm3:00 pm3:20 pm3:40 pm

SATURDAY:

8:30 am8:50 am9:10 am9:30 am9:50 am10:10 am10:30 am10:50 am

of Presentat ions:

EB 311

A - l (Tremblay)A-2 (Lee)A-3 (Rubin/Tremblay)A-4 (Richards)A-5' (Bet t inson)A-6 (Joo)A-7 (Samuels)

***** i_

A-8 (Frank)A-9 (Muradian/Locklin)A-10 (Feather)A- l l (Robichaud)E-8 (Hegarty e t a l )E-9 (McLaughlin)E-10 (Symmers)E- l l (Spacher)

(rooms t o be announced a t

D-l (Adekugbe)D-2 (Iannello)D-3 (Chen)D-4 (Kim)D-5 (Witt)D-6 (Kao)D-7 (Abdelphany)D-8 (Boehl ing)

OS

E-lE-2E-3E-4E-5E-6E-7

U N

F-lF-2F-3F-4F-5F-6F-7F-8

Holi

G-lG-2G-3G-4G-5G-6G-7G-8

503

(Barry)(Pfleuger)(Mil ler)(Scannell)(Merk)(Reilly)(McWilliams)

C H * * * * *

(Budeck)(Gavrilas)(Carter)(Neuder)(Munno)(Reilly)(Clark)(Schor)

day Inn)

(Berninger)(Vitale)(Pareto)(Carpenito)(Broughman)(Hosticka)(Chapman)(Perez)

OH 428

C-l(LaFleur et al)C-2 (Bursus)C-3 (Haley)C-4 (LeClaire)C-5 (Varsamis)C-6 (Kato)C-7 (Wilson)

B-l (Petti)B-2 (Rossell)B-3 (Sharirl i)B-4 (Gale)B-5 (Coxe)

ACKNOWLEDGEMENTS

The following organizations are grateful ly acknowledged forthe i r financial contributions:

American Nuclear Society - Headquarters

American Nuclear Society - Reactor Physics Division

Anerican Nuclear Society - Mathematics and Computation Division

American Nuclear Society - Material Science and Technology Division

Anerican Nuclear Society - Nuclear Reactor Safety Division

American Nuclear Society - Northeast Section

Public Service Company of New Hampshire

Westinghouse - Hittman

Westinghouse - Water Reactor Division

Pickard, Lowe and Garrick

University of Lowell

Yankee Atomic Electric Company

Also, special thanks must be given to : Fran Broderick, Dr.Suresh Mathur, Mark Caron, Lewis Chesno, Dean Aldo Crugnola,Byron Frank, Joanna Hanz, President William T. Hogan, Dean Leo F.King, Paul Lacerte, Caroline McAndrews, Nancy Moller, Juan Mota,Pat Ouellette, Dr. James Sheff, John Stoddard, Dr. John White,and many others who donated both time and energy.

CONFERENCE ORGANIZATION

Although many people have given o f t h e i r t ime and e f f o r t towards makingth is conference a success, the following individuals are ident i f ied for thei rmany hours of hard work.

Co-Chairmen

Technical Sessions

Publicity

Housing

Transportation

Communications

Social Programs

Entertainment Guide

Transcript Book

Faculty Advisor

Nuclear Engineering Program Director

Anne Marie Lacerte, General ChairmanMark Durrenberger, Finance Chairman

Michael TremblayAnne Marie Lacerte

Raymond Roy

Mark Durrenberger

Michael Tremblay

Anne Marie LacerteMark DurrenbergerCindy Locklin

Debbie LaPageMichael Hicks

Hugh McKenney

Anne Marie Lacerte

Dr. Gilbert J . Brown

Dr. James P. Pholps

C O M P U T E R

A P P L I C A T I O N S

A-lUNIVERSITY OF IDVELL

PAPER ABSTRACT

AUTHMt: Michael Tremblay.

ADVISOR: Dr. John R. White

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: University of Lowell

CANDIDATE FOR: B.S.

PAPER RELATED TO: Other

TITLE: DSNP : A Dynamic Language for the Simulation of Nuclear Power Plants

This paper introduces DSNP, a nuclear power plant simulator. DSNP isa dynamic digital language with Fortran as a subset. It allows the modellingof the many various components of a nuclear reactor into a computer program.DSNP developes the power plant simulation from a flow chart model of theplant. An overview of the use of the DSNP language will be given, as well asa discussion of its advantages and disadvantages.

A-2UNIVERSITY OF IOWELL

PAPER ABSTRACT

AUTH3R: Sun G. lee

ADVISOR: Dr. Maria Gavrilas

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: University of Maryland

CANDIDATE FOR: B.S.


TITLE: Comparative Study of Parameter Changes in the PWR-GALE Code

The PWR-GALE code is a computerized mathematical model whichcalculates the radioactive releases of Gaseous And Liquid Effluents frompressurized water reactors (PWRs). The calculations are based on datagenerated from operating reactors, field and laboratory tests, andplant-specific design characteristics.

The PWR-GALE code claculates the releases for a reactor operatingunder 'Vionnal" conditions. By changing the initial data, a comparison is madebetween the calculated releases under normal" operations versus the newconditions. In addition, an estimate of the internal dose to aquatic biotafrom radioactive liquid effluents is performed.

A-3UNIVERSITY OF IDWELL

PAPER ABSTRACT

AUTHOR: Michael Rubin & Michael Tremblay

ADVISOR: Dr. James Sheff


CANDIDATE FCR: B.S.


TITLE: The Modeling of the Core of the University of Lowell 's Research ReactorUsing Computer Aided Design

Along with a short paper, w i l l be included a few hard copies of d i f f e r -ent views of the reac tor core . The paper w i l l be composed of a short presen-t a t i o n of the school 's CAD system and an overview of the s teps taken t o designthe core . A simplified ( i . e . summarized) descr ip t ion of the c o r e ' s dimensionsand s t ruc tu re w i l l a l so be included.

Hardcopies:1) Detailed drawing of the core arrangement

Isometric view of the coreTop and s ide views of the core

A-4UNIVERSITY OF IOVELL

PAPER ABSTRACT

AUTHOR: Matt Richards

ADVISOR: Dr. J. M. Doster

MAJOR FIELD: Cfomputer Cbdes & ApplicationsUNIVERSITY: North Carolina State

CANDIDATE FOR: M.S.


TITLE: Parallel Algorithms for the Finite DifferenceSolution to the IS&vier-Stokes Equations

The equations governing one dimensional homogeneous equilibrium flowof a steam water mixture in a clesed loop geometry are solved using a finitedifference technique. A semi-implicit time advancement is used such that alinear equation set is solved for each time step. The linear system is sovedusing both sequential and parallel algorithms. The studies indicate that theparallel algorithms can signicantly reduce computer time.

A-5UNIVERSITY OF LOWELL

PAPER ABSTRACT

AUTH3R: Robert Bettinson

ATV3SCR: Dr. James Sheff


CANDIDATE FOR: B.S.


TITLE: Computer Aided Design of the University of Lowell's Concrete Pool

This presentation will cover all aspects of designing the reactor pool atthe University of Lowell. I will cover the basic CAD system (its problems andgood points) and the process of plotting the design into the machine includingthe major problems.


PAPER ABSTRACT

AUTHOR: Han-Sem Jbo

ADVISOR: Professor Allan F. Henry

MAJOR FIELD: Reactor PhysicsUNIVERSITY: Massachusetts I n s t i t u t e of TechnologyCANDIDATE FOR: Fh.D.

PAPER RELATED TO: Ph.D. dissertation X

TITLE: Resolution of the control Bod Cusping Problem for Nodal Methods

The objective of this research is to develop an accurate systematicinexpensive and reliable procedure for resolving die control rod cuspingproblem for nodal methods in light water reactor calculations. This cuspingproblem arises if the prsence of a control rod partially inserted in laigespatial mesh node is represented by homogeneous cross sections of magnitudeproportional to the volume of control rod material present. A plot ofreactivity vs. control rod position then exhibits unphysical cusps as the rodis withdrawn form node to node.

It is first shown that the presence of control rods partiallyinserted in a node accounted for by homogenized cross sections found byconventional procedures leads to incorrect nodal power distribution andreactor eigenvalue. Several new solution methods are then developed fordetermining accurate homqgenization pararaenters for a partially rodded node:a tabulation-interpolation scheme, a volume-weighted cross section method, andthe Collector-Predictor Method.

Trie Collector-Predictor Method is shown to be more accurate andsystematic than the other schemes. It is incorporated into the QJANDRY nodalcode, and tested for several benchmark problems. Results obtained are forcompared with those of conventional solution methods: for static problems,error in eigenvalue and nodal power are reduced by a factor of 5 - 10, and fortransient problems, theny are reduced by a factor of 10, the maximum error inpower density being less than 2 % in most cases. This method is found to besystematic, problem independent, consistent, and inexpensive for providing asatisfactory resolution of the control rod cusping problem.


PAPER ABSTRACT

AUTHDR: Jeffery W. Samuels

ADVISOR: Edward T. Dugan

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: University o£ Florida

CANDIDATE FOR: M.S.

PAPER RELATD TO: M.S. thesis X

TITLE: The Application of DSNP as a Teaching Aid

This presentation describes the Dynamic Simulator for Nuclear Bawer Plants(DSNP) programming language, a simulation programming language developed attiie Argonne National Laboratory. Plans for the application of DSNP as ateaching aid in Nuclear Reactor Power Plant Systems Dynamics and Control andwith possible applications in Principles of Nuclear Reactor Operations andFundamentals of Reactor Safety courses at the University of Florida areoutlined.

Key features of DSNP modeling along with the advantages of using DSNPare listed. Methods for using the DSNP language to illustrate the dynamics ofnuclear power systems and the interrelations between the various systemcomponents are discussed. * Typical in-class demonstrations and out-of-classassignments using the DSNP language are outlined. These include the modelingand simulation of nuclear power plants or their subsystems with applicationsto specific operating units.


PAPER ABSTRACT

AUTH3R: Byron Prank

ADVISOR: Dr. John R. White


CANDIDATE FOR: B.S..


TITLE: Analytic Solution of the 1-D Diffusion Equation for the Fundamentaland Higher Harmonics - Forward and Adjoint Forms

An exact solut ion technique for the multi-group mult i-regiondiffusion equation i s presented with p a r t i c u l a r emphasis on the ease ofcalcula t ing the higher hannonics as well as the fundamental mode eigenvalues.A se r i e s expansion of the multi-group flux allows at. exact so lu t ion for theexpansion coef f ic ien ts . The solut ion technique for the forward and adjointforms of the flux-eigenvalue probleam have been implemented i n the newlydeveloped HAREM code (HARraonic Expansion Method). Results from sampleproblems u t i l i z i n g a 1-D representat ion of the 2-group IAEA PWR benchmarkproblem w i l l be presented, along with r e s u l t s from VENTURE for comparison.

A-9UNIVERSITY OF IDWELL

PAPER ABSTRACT

AUTHOR: Florin Muradian 8c GLndy Campbell



CANDIDATE FOR: B.S.


TITLE: Designing the Thermal Column on the Computer Aided Design System (CAD)

There are three basic procedures we used in designing the Thermal Columnon the CAD system.

The first procedure was for us to obtain the blue prints of the ThermalColumn from the reactor

Following the obtaining of the blue prints we then gathered the commandsthe computer. Using the commands we started to design the Thermal Column.

A-10UNIVERSITY OF LOWELL

PAPER ABSTRACT

AUTHOR: Meivin J . FeatherADVISOR: Prof. Roger Rydin

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: Univers i ty o f V i rg in ia

CANDIDATE FOR: B.S.

PAPER RELATED TO: Senior Thesis

TITLE: A Study of Inherent Errors in Nuclear Diffusion Codes due to Source TermApproximation

This study defines the effect of the errors generated Intwo-group neutron diffusion codes and shows that these errorsstem from the diffusion equation's source term approximation.Using a modified finite difference code, changes in core fluxshape and Keff are analysed for a number of nodal coarse meshmodels. Sequential solution methods prove less accurate thansimultaneous solutions due to the greater dependance of theformer on source term variance. Results also show that in-creased coarse mesh methods can not follow the detailed fluxplot of a finite meoh technique due to the loss of source shapein the matrix formulation process. Analysis on a quadraticflux shaping code displays a similar dependence on source termapproximation effects.

UNIVERSITY OF LOWELLPAPER ABSTRACT

AUTHOR: Jim RobichaudADVISOR: Dr. Gilbert J . Brown


CANDIDATE FOR: M.S.

PAPER RELATED TO: Term Paper

TITLE: Analysis of the RETRAN Computer Code

RETRAN is a thermal-hydraulic computer code, used for analyzingtransients in light water reactor systems. It solves the conservationequations for mass, momentum, and energy. This presention discusses theformulation and solution of these equations. In addition, inherent codelimitations are presented.

S A F E T Y

A N D

E C O N O M I C S

B-lUNIVERSITY OF IDWELL

PAPER ABSTRACT

AUTHDR: David ftstti

AIVISCR: Prof. Norman Rasmussen

MAJOR FIELD: Reactor SafetyUNIVERSITY: Massachusetts Institute of Technology

CANDIDATE FOR: Ph.D.


TITLE: The Radiological Source Term: An Overview

An overview of the radiological source term is presented in anattempt to convey the technical problems surrounding this crucial issue. Thekey phenomena affecting fission product behavior in severe reactor accidentsare presented. Such topics as fission product release from fuel, fissionproduct chemistry and aerosol behavior as well as fission product transportand deposition in both t:he reactor coolant system and containment arediscussed.

B-2UNIVERSITY OF IOVELL

PAPER ABSTRACT

AUTHOR: Laura R o s s e l l

ADVISOR: Dr. Mohammed Modarres

MAJOR FIELD: Nuclear Engineer ingUNIVERSITY: U n i v e r s i t y o f Maryland

CANDIDATE FOR: B .S .

PAPER RELATED TO: Term paper

TITLE: Fault Tree Analysis of U MD TRIGA Reactor Control Rod System

Analysis was performed on Maryland's TRIGA reactor to determinechances of inablility to raise or lower control rods or to scram.

Ihe reactor is a 250kW swimming-pool design seven feet in diameterwith 17 kg of 20% enriched uranium fuel. The three control rods are identicalaluminum-encased boron carbide structures utilizing three identical butindependent circuits for control.

The fault tree top event, failure of control rods to act ascommanded, included the loss of scram capability as well as the ability toraise or lower rods as desired. Causes were mechanical or electrical failure,or operator error.

It was found that the most significant contribution to the filialprobability was due to operator error.

B-3UNIVERSITY OF LCWELL

PAPER ABSTRACT

AUTH3R: Mbhsen S h a r i r l i

ADVISOR: Dr. Marvin Roush

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: Univers i ty of Maryland

CANDIDATE FOR: B.S. M.S. Ph.D. X

PAPER RELATED TO: Hi.D. Dissertation X M.S. ThesisTerm paper Other

TITLE: An Evaluation of Importance Measures for Success Tree Analysis

One can obtain some valuable information about a system by examiningthe ways by which the system succeeds. This area of study can be referred toas Success-Tree Analysis. A systematic approach to success-tree developmentis discussed. Further, analysis is done on the development and applicationsof the importance measures tailored to the needs of success-tree analysis.

B-4UNIVERSITY OF IOWELL

PAPER. ABSTRACT

AUTiDR: John Gale

ADVISOR: Prof. Barry Hyman - - U Wash-Seattle

MAJOR FIELD: Mechanical EngineeringUNIVERSITY: U n i w r s i t y of Lowell

CANDIDATE FOR: B.S.


TITLE: Backfi t t ing on Nuclear Power P l a n t s : The PGE-Trojan Affair

This case study prepared under the WISE program i s a r e a l world lookat the backfitting problem. It is a study of the efforts of a nuclear powerplant to comply with the post-TMI backfitting requirements. The technicalproblems at the plant and the regulatory issues in Washington are examined andtheir interrelations are discussed.

B-5UNIVERSITY OF IDWELL

PAPER ABSTRACT

AUTHOR: Raymond L. Cbxe, J r .

ADVISOR: Prof. L. M. Lidsky

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: Massachusetts I n s t i t u t e of Technology

CANDIDATE FOR: Ph.D.


TITLE: Financial Risk and Investment Decisions: A Study of the NuclearElectric Utility Industry

In the recent past, many US electric utilities have cancelled nuclearprojects, often citing financial difficulties or unacceptable financial riskposed by the project. A study of the investment and decision making process inthe electric utility industry is useful1 in highlighting the financialproblems posed by nuclear projects, particularly for small utilities. Thispaper describes historical cost accounting and how its use increases financialrisk. Three models of the utility investment decis5.on making are considered:"utility" theory, the capital asset pricing model, and more traditional "rulesof thumb" for determining acceptable financial risk. The final section of thepaper presents the results of applying some "rules of thumb" to the USelectric utility industry.

F U S I O N

C-lUNIVERSITY OF LOWELL

PAPER ABSTRACT

AUTHOR: L. David LaFleur (Physics) , Roma Mohanti, Randall Pf lueger, WilliamDuggan, Asad Majid, Dave Loveless

ADVISOR:

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: Renssalaer R>lytechnic Institute

CANDIDATE FOR: B.S., M.S., Ph.D.


TITLE: Compact Design of a Tokamak Fusion Reactor with High NeutronWall Loading

The economic potential of fusion power is significantly affected bythe size and wall loading of the reactor system. Designs which stress reducedsize and high wall loading are referred to as "compact .

This paper describes the conceptual design of a compact Tokamakfusion reactor operating at a neutron wall loading of 10MW/m(2) • Tneresultant design, referred to as the (DMpact TORoidal fusion device, COMTOR,has a field-on-axis of 55T, a plasma radius of 1.1m, and an aspect ratio of5. Tne inboard distance between the superconducting toroidal field coils andthe first wall of the blanket is about 1.5m. Tne breeding blanket is composedof LiA10(2) t while the inboard shield consists of layers containing mixturesof either boron carbide or Tungsten.

Plasma operating conditions, based on an optimistic assumption of a

10 ('volume aveEflged beta of 10%, are a temperature of 20KeV and a density of 2 X

Size reduction is constrained by space requirements for the ohmicheating coils and the radiation shields. The ohmic heating coils are providedto generate the plasma current but it is assumed that alternate methods areincorporated to maintain the operating current.

C-2UNIVERSITY OF IOWELL

PAPER ABSTRACT

AUTHOR: Ibnel V. Bursus

ADVISOR: Dr. Ian Hutchinson

MAJOR FIELD: Nuclear Engineering

UNIVERSITY: Massachusetts Institute of Technology

CANDIDATE FOR:

PAPER RELATED TO:

TITLE: Diagnostics of High-Temperature Plasmas Using Laser InducedResonance Fluorescence

A complete and correct knowledge of the role played by hydrogenneutrals in a fusion machine was proved to be important.

The principle of the method is based on comparing theoretical andexperimental values of the change in the population of a certain atomiclevel. The change is produced by resonance pumping; the fluorescence photonsare measured. Several features of the method are presented.

Tne advantages of the method are: a minimal knowledge of the electrontemperature and density, accuracy in determining both the spatial and absolutemagnitude of neutrals density and access to other plasma parameters.


PAPER ABSTRACT

AUTH)R: Thomas C. Haley

AIVISCR: Prof. Don Ste iner

MAJOR FIELD: Nuclear EnmgineeringUNIVERSITY: Renssalaer Polytechnic I n s t i t u t e

CANDIDATE FOR: B.S.


TITLE: Engineering Problems of Lithium Breeding in Tokamak Fusion ReactorBlankets

In Tokamak devices the most promising fusion react ion i s the D-Treaction, but the inavailability of tritium as a natural resource requiresthat i t be bred. This is most economically achieved by using the neutronpopulation escaping the Tokamak reactor's magnetic field in a Li(6)[n,alpha]Treaction. Sufficient breeding requires that the lithium breeding material bein the reactor's primary structure, creating many engineering problems whichthis paper examines. The first of these problems is the nature of thebreeder; should solid or liquid lithium be used, should i t be a part of thecoolant system, and how will the system affect overall reactor engineeririg.Secondly, how will the bred tritium be removed for use, and how much tritiumwill be required to provide for the continuous operation of the reactor aswell as the start-up of others.


PAPER ABSTRACT

AUTHOR: Rene J. LeOLaire, Jr.

ADVISOR: Dr. J. E. Meyer

MAJOR FIELD: Nuclear Engineering/ Fusion TechnologyUNIVERSITY: Massachusetts Institute of Technology

CANDIDATE FOR: M.S. ; Ih.D.

PAPER RELATED TO: M.S. thesis

TITLE: Aspects of Long Pulse Commercial Tokamak Reactor Design

Ibssibilities of very long burn pulse operation in commercial Tokamakreactors are analyzed. Long pulse operation could reduce or eliminatelifetime limits due to fatigue in the first wall, blanket and structuralmaterial and make the reactor more attractive from the standpoint of theelectric ultility. Very long pulse lengths can be achieved with the tokamaksusing inductive current drive if the major radius is increased to accomodate alarge ohmic transformer.

Illustrative design parameters have been developed for an Ultra-LongRaise Tokamak Reactor (ULTR.) with a pulse length of 24 hours. Tne principTesdeveloped for the 24 hour pulse length ULTR design have also been used in ascoping study for machines with shorter pulses. Barameters for a machine witha 4 hour pulse length are given.

The ULTR design has an ohmic transformer which is optimized tosatisfy the conflicting requirements of maximized OH drive and for reaction ofthe inward forces of the TF coil. Tne toroidal magnet is completelymodularized, with each coil in its own cryostat and shearing panels at roomtemperature.

Analysis of effects of thermal fatigue on a representative first walldesign has been performed. Windows of allowed operation have been found,limited by primary stress, swelling and fatigue. The analysis has beencarried out for first walls made of stainless steel or vanadium.

C-5UNIVERSITY OF IDWELL

PAPER ABSTRACT

AUTHOR: Gteorgios Varsamis

ADVISOR: Mark Embrechts

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: Rensselaer Iblytechnic I n s t i t u t e

CANDIDATE FOR: M.S.


TITLE: A Low Lithium Inventory Blanket Approach for Fusion Reactors

Hie current generation of fusion reactors requires a fuel supplyconsisting of tritium and deuterium. The general approach is to produce(breed) tritium in the blanket (the part of the fusion reactor surroundingthe plasma region) , with the neutrons resulting from the fusion reaction.Conventionally *iiis is done by means of a lithium blanket via the Li(6)[n,alpha]T and Li(7) [n,n'alpha]T reactions. In order to have an adaquatesupply of tritium, the tritium breeding ratio (that is the ratio of tritiumatoms produced per neutron generated in the fusion reaction chamber) has to begreater than one. Major disadvantages of the conventional approach stem fromthe fact that lithium is an extremely reactive chemical.

A novel blanket structure which produces tritium via neutron capturefrom deuterium in heavy water will be presented. A major advantage of thisapproach is that the heavy water technology is already mature enough to handlethe engineering problems (production, tritium handling, etc.). Nevertheless apure D(2)0 blanket with a neutron multiplier (e.g. Be) near the first wall(the structural component separating the blanket from the plasma region),generally will not provide an adequate tritium breeding ratio. Therefore,small amounts of lithium must be disolved in the D(2)o, but those amounts arefar less than those required in the conventional approaches (solid lithiumcomponents or lithium dissolved in water) , because a significant fraction ofthe tritium will be bred from the deuterium and the neutron absorbtion indeuterium is less than that in hydrogen.

The conditions for adequate tritium breeding from this family of^^2)0 blankets will be discussed. The tritium breeding ratios are calculatedusing the Los Alamos discrete ordinates neutronics code ONEDANT. This novelblanket concept looks promising to provide an adequate tritium breeding ratiowith very low lithium inventories.


PAPER .ABSTRACT

AUTHOR: Kbsuke Kato

AIVISOR: Ian Hutchinson

MAJOR FIELD: Applied Plasma PhysicsUNIVERSITY: Massachusetts Institute of Technology

CANDIDATE FOR: Ph. D.

PAPER RELATED TO: Ph.D. dissertation

TITLE: Wave Absorption Measurement of Microwave Beam Dumps for Use inFusion Diagnostics

Microwave absorption measurements were carried out for beam dumps ofvarious configurations made from several vacuum compatible materials. Thematerials used are graphite, alumina, Macor, and Phyrex. A broadband source(H(g arc lamp) and an InSb detector were used for the measurement. Resultsshow that greater than 99 % absorption of the wave may be achieved with Macorand Pyrex dumps, while the absorption by graphite and alumina dumps areconsiderably lower.

C-7UNIVERSITY OF LOWELL

PAPER ABSTRACT

AUTHOR: Latresia A. WilsonADVISOR: Prof. James Kelly

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: University of Virginia

CANDIDATE FOR: B.S.


TITLE: Radiation Effects on The F i rs t Wall o f a Fusion Reactor

This report i s on state of the ar t analysis on f i r s t wall effects infusion reactors. In th is study, various parameters and interact ion models arediscussed including sputtering, hydrogen absorption, b l i s te r ing andi n t e r s t i t i a l void production. These effects have proved worthy of analysisdue to potential hazards created that could jepordize the in tegr i t y of thefusion reactor 's structure and plasma.

T H E R M A L

H Y D R A U L I C S

D-lUNIVERSITY OF IOWELL

PAPER ABSTRACT

AUTHDR: Oluwole A. Adekugbe

AJDVISCR: Profs. A.L. Schor & M.S. Kazirai

MAJOR FIELD: Fission Reactor TechnologyUNIVERSITY: Massachusetts I n s t i t u t e of Technology

CANDIDATE FOR: M.S.


TITLE: Loop Simulation in Sodium Boiling Expts.--Application to a NaturalConvection loop

One-dimensional whole loop simulation capability is implemented inthe sodium coolant thermal-hydraulic code—THERMIT. Hitherto, THERMIT hasproduced good results from the analyses of the test sections of experimentalsodium loops and of core conditions of full-scale LMFBR power plants. Suchanalyses had required the use of boundary conditions at the inlet and outletplena. The present work simulates the entire primary coolant loop andeliminates the need for suggesting boundary conditions at the plena. Anumerical scheme is implemented in the code to accomplish constant temperatureplena during transients. A series of sodium boiling experiments performed atthe test facility at the Oak Ridge National Laboratory has been simulated withthe details of geomoetry and experimental conditions preserved. The resultsobtainded have been in very close agreement with the experimental data.

D-2UNIVERSITY OF IDWELL

PAPER ABSTRACT

AUTH3R: Victor Iarmello

AIV1SCR: Prof. Neil E. Todreas

MAJOR FIELD: Ifeat Transfer and Fluid FlowUNIVERSITY: Massachusetts I n s t i t u t e of Technology

CANDIDATE FOR: B.S.


TITLE: Feed and Bleed in Pressurized Water Reactors Analyzed under Uncertainty

A methodology to assess the primary feed and bleed process inpressurized water reactors (PWRs) subject to uncertainty in input parametersand modeling is presented. The study has three major sections. The firstpart develops the modeling of PWR subsystems, from which a fast-running codeis created. The second part uses this code to perform a thermal hydraulicanalysis of the feed and bleed procedure. The last part of the study examineshow the transient calculation changes with variations in the inputparameters. For the distribution chosen to describe the input parameters, theanalysis performed indicates that the probability of adequately cooling thecore using the feed and bleed procedure is 64L

D-3UNIVERSITY OF IOWELL

PAPER ABSTRACT

AUTHOR: Chiy J . Chen

AIVISCR: Dr. G i l b e r t Brown

MAJOR FIELD: Nuclear Engineer ingUNIVERSITY: U n i v e r s i t y o f Lowell

CANDIDATE FOR: M.S.


TITLE: Thermal Conductivity Measurements for Reinforced Concrete: Rebar Effecton Heat Conduction

A method for obtaining effective thermal conductivity of reinforcedconcrete has been developed through the design of a convenient device whichuses the comparative method to generate the essential data.

Six concrete molds were subjected to temperature measuring underspecific conditions. Simultaneous (quickly switched) reading of temperatureat several separate times was obtained during the heating period. From thedata, plots of temperature versus distance and of effective thermalconductivity ratio versus volume ratio were produced. It is found that thevolumetric homogeneous model overestimates the thermal conductivity ofreinforced concrete because it neglects the rebar orientation factor. Afibrous composite model has been introduced. This paper, in detail, describesthe technique used as well as presents data of effective thermal conductivitythat is consistent with the fibrous model prediction.


PAPER ABSTRACT

AUTHDR: S. H. Kim

AIV3SCR: Prof. M. Z. Podowski

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: Renssalaer Polytechnic I n s t i t u t e

CANDIDATE FOR: M.S.


TITLE: An Analysis of Core Meltdown Accidents in BWRs

A new Computer Code for the analysis of BWR Degraded Core Phenomena,"MELRPI", was developed at Rensselaer Polytechnic Ihstistute, under thesponsorship of Oak Ridge National Laboratory. The "MELRPI" Code uses amechanistic approach in modelling such phenomena as two dimensional heattransfer, coolant thermal-hydraulics for partially or fully covered core,metal oxidation, amd melting/relocation of individual core materials. Thepurpose of this paper is to highlight differences between "MELRPI" and the"March" Code, including both the modelling concepts and results. The TQUVsequence was used for the numerical comparicon. It has been shown that thesetwo codes yield considerably different results. This is an important result,in that of application as the only tool available for analysis for degradedBWR cores, is far more conservative than MARCH ( the most widely used code todate) . This dispells the notion that MARCH yields conservative results. Italso has far-reaching implications for the design of BWR operating procedures,and licensing mechanisms.

D-5UNIVERSITY OF IDWELL

PAPER ABSTRACT

AUTHOR: Robert J. Witt

AIVJSOR: Prof. J. E. Meyer

MAJOR FIELD: Nucl. Eng. / Reactor Eng. / Fusion Reactor TechnologyUNIVERSITY: Massachusetts Institute of Technology

CANDIDATE FCR: M.S.


TITLE: Computer Techniques for Sensor Validation During EBR-2 NaturalCirculation

Sensor validation is one way of giving reactor operators a highdegree of confidence in their measurements. Although many sensor validationprograms have been developed for reactors running at full flow and full powerin steady state, relatively few have been developed for reactors operating ina transient, low flow (natural circulation) regime. The number of reliablesensors in the natural circulation regime will be compared to the number ofreliable sensors in the steady state regime for the specific case of EBR-2,and the implications of this comparison on model development will bediscussed. Specific analytical models for predicting the flow through theE3R-2 reactor during natural circulation will be presented, and the results ofthese models will be compared to data compiled from EBR-2 natural circulationtest procedures.


PAPER ABSTRACT

AUTHDR: Shih - Ping Kao

AIVISOR: Prof. J .E . Meyer

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: Massachusetts I n s t i t u t e of Technology

CANDIDATE FOR: Fh.D.

PAPER RELATED TO: Ph.D. dissertation

TITLE: Computer Code Applications : PWR Thermal Ifydraulics Simulation

Objective is to develop a faster-than-real time thermal-hydraulic simulationcode to assist the operators of a FWR plant to assess the primary systemconditions during operational transients. Transients of interest range fromroutine power level maneurering to anticipated transients such as scram, pumpcoastdown, and natural circulation. Analytical information rpovided by thecomputer model is most valuable when plant sensors can no longer providemeaningful values. The model may be readily adopted by on-line safety systemssuch as the Safety Paramenter Display System (SPDS), and the DisturbanceAnalysis Surveilance System (DASS) on a plant computer.In this model, the FWR primary system is sectionalized into the core, reactorvessel upper and lower plena, hot-legs, steam generators, and pressurized. Aform of donor cell differencing scheme is used; hence, flow reversal ispermitted. In the reactor vessel plena where multiple streams enter or emergefrom the cell, perfect enthalpy mixing is assumed. Drift flux formulation isapplied whenever bubbly or slug flow is encountered. A two-fluid model isdeveloped to predict pressure dynamics. The momentum equation is decoupledfrom the energy equation by adopting a semi-implicit method. The MomentumIntegral Model is used with the assumption that flow is uniform in each loop.The code, System and Pressurizer Kode (SPK), has been tested on the DEC PDP-11mini computer, and the Honeywell DPS 8/70 M mainframe,with computational speedof to to thirty times faster than simulation time.

0-7UNIVERSITY OF LOWELL

PAPER ABSTRACT

AUTHOR: Jamal M. Abdel ghanyADVISOR: Dr. Muses Yeung and Dr. Y. Chang

MAJOR FIELD: Mechanical Engineering and Chemical EngineeringUNIVERSITY: University of Lowell

CANDIDATE FOR: M.S.

PAPER RELATED TO: M.S. Thesis

TITLE: Hydrodynamics of a Spray Column

The model equations are an attempt to describe the influence ofhydrodynamic effects on the p ro f i l e of the model var iable; the variable beingthe hold-up of the dispersed phase i n the column.

The model parameter used to describe these hydrodynamic effects i sthe Peclet number of the continuous phase. Hydrodynamic effects in th isinstance refer to the deviation of the flow structure from truecounter-current due to back mixing, a phenomenon encountered i n continuousl iqu id extraction equipment which affects adversely the eff ic iency of the masstransfer process in the column.

The model thus enables one to obtain the hold-up p ro f i l e which inturn would induce better understanding of the mass transfer mechanism in thecolumn.

D-8UNIVERSITY OF LOWELL

PAPER ABSTRACT

AUTHOR: Richard L. Boehling, J r .

ADVISOR: J . L. Kelly


CANDIDATE FOR: B.S.


TITLE: Boehling Heat Engine

The Boehling Heat Engine, a rotary 2-T gas cycle heat engine, i s anew addition to the f i e l d of heat engine design. Application of theoreticalpr inciples i n thermodynamics, heat t ransfer, and applied math have resulted i na theorectical model that i s a thedrectical carnot cycle.

E- lUNIVERSITY OF IOWELL

PAPER y»STRACT

AUTHOR: Michael Barry

ADVISOR: John R. White

MAJOR FIELD: Nuc lea r Engineer ingUNIVERSITY: U n i v e r s i t y o f Lowell

CANDIDATE FOR: M.S.

PAPER RELATED TO: M.S. t h e s i s

TITLE: The Evaluation of the 1 MeV Relative Neutron Damage Factorin the University of Lowell Reactor

A good deal of research is being done in evaluating the 1 MeV neutronrelative damage factor (R. D. F.). This R. D. F. may be thought of as thef luence of 1 MeV neutrons which would cause an equivalent amount of damage aswould a unit fluence of neutrons (that is, fast neutrons, defined as neutronshaving kinetic energies greater than or equal to 10 KeV) from a givenspectrum.

Silicon is referenced in this case as what would be damaged since itis an integral part of weapons guidance systems. The equation to find theR.D.F. is

18 MeVD(E>p(E) dE

.01 MeVR. D. F. =

(18 MeVD(l MeV) J 0(E) dE

' .01 MeV

where D(E) is silicon displacement as a function of energy, values .of whichhave been experimentally determined, (j)(E) is the flux spectrum, and D(l MeV)is the silicon displacement at 1 MeV.

The RDF is evaluated using foil activation techniques. Tnispresentation will be concerned with these techniques, the use of the SAND-IIcode to unfold a flux spectrum from the foil activities, and the use of theDAMAGE code to solve the equation above for the RDF.

E-2UNIVERSITY OF IDVELL

PAPER ABSTRACT

AUTH3R: Randall J . Pflueger

ADVISOR: Dr. John Core l l i

MAJOR FTETD: Nuclear EngineeringUNIVERSITY: Rencsalaer Polytechnic I n s t i t u t e

CANDIDATE FCR: M.S.


TITLE: Photo-Ionization Spectroscopy of Defect Associated Electronic Statesin Neutron Irradiated Silicon

A technique is described whereby the transition energies and carriertrapping/relaxation kinetics may be determined. These transitions are notamenable to examination via conventional I. R. techniques. Thetrapping/relaxation kinetics will be examined as a function of sampletemperature, and recent important links to research on thermal donors in heattreated silicon will be discussed.

E-3UNIVERSITY OF IDWELL

PAPHl ABSTRACT

AUTH3R: Midshipman Dean Miller

ADVISOR: Dr. Martin E. Nelson

MAJOR FIELD: Marine EngineeringUNIVERSITY: U. S. Naval Academy

CANDIDATE FOR: B.S.


TITLE: Measurement of Neautron Attenuation Coefficients with a NE-213 Detector

Accurate dose measurements due to neutron and gamma radiation are anessential requirement for the nuclear engineering, for health safety purposesas well as shailding design references. A portable detector that accuratelydetermines doses from both thermal and fast neutrons and gamma radiation isthen beneficial to the nuclear industry. To demonstrate the potential of aNE-213 detector system for such use, neutron attenuation coefficients for14-MeV neutrons were determined for several materials.

The NE-213 detector is an organic scintillating detector and is usedin a neutron spectrometer system. The detector is sensitive to both neutronand gamma radiation, which are distinguished by the phenomena of rise time.To obtain a neutron or gamma ray spectrum, the output of the detector iscounted by a dual parameter multi-channel analyzer. The two inputs to theanalyzer are rise time and incident radiation energy. Since neutrons have alonger rise time than gamma radiation, the counts are usually separated alongthe rise time axis into two sets of data: Counts versus energy for both typesof f luence as a function, from which a highly accurate dose calculation isobtained. To calculate the neutron attenuation coefficient for a material,the fluence under the neutron source peak is found for several thicknesses.The exponential decrease of the source peak is the attenuation coefficient,which is compared to existing values.

The results of the research confirmed the ability of the system as aneutron spectrometer and therefore a dose detection device. Several neutronand gamma ray spectrums were obtained as well as neutron attenuationcoefficients for many materials.

E-4UNIVERSITY OF LOWELL

PAPER ABSTRACT

AUTHOR: Mathew J . Scannell ;

ADVISOR: Dr. George Chabot

MAJOR FIELD: Radiological SciencesUNIVERSITY: University of Lowell

CANDIDATE FOR: M S.


TITLE: Cr i t i ca l Review of a Commercially Available Extrapolation Chamber

Extrapolation chambers are becoming more popular in the nuclearindustry as a primary instrument fo r beta dose measurements as greateremphasis has been placed on evaluating beta exposures. Although most shamberscurrently employed are of an "in-house" design, some such as the NuclearEnterprises Incorporated (N.E.I . ) chamber are commercially avai lable. Thischamber is a paral lel plate ionizat ion chamber whose active volume i svar iable. The chamber employs the fundamental concept of dE/dm and allowsdetermination of the change in current col lected as the active volumechanges. The chamber is composed of a high voltage electrode of aluminizedmylar and a col lect ing electrode of t issue equivalent conducting p las t ic .This chamber has been observed to repond 28% lower than accepted values whenmeasuring beta doses from a depleted uranium slab. The resons for th is largeerror i n reponse has been determined to be due to geometrical problems andproblems associated with the col lect ing electrode design. The geometricalproblems include a l imi ted viewing angle, a factor important for measurementson a d is t r ibuted source, and a recessed high voltage electrode, a factorimportant for determining surface beta dose rates or beta dose rates under 7ing/cm. The col lect ing electrode design suffers from a retaining screwcentered on the col lect ing electrode composed of a re la t ive ly non-conductivematerial which creates a deformation due to the screw head s lo t on theotherwise f l a t co l lect ing surface and results in a perturbed e lec t r ic f i e l d .The combination of these design problems reduces the accuracy of th is chamberwhen measuring beta doses/dose rates from any widely d is t r ibuted source.

E-5UNIVERSITY OF IOWELL

PAPER. ABSTRACT

AUTHDR: Midshipman Heidi M. Merk

ADVISOR: Dr. M. Nelson

MAJOR FIELD: Health PhysicsUNIVERSITY: U. S. Naval Academy

CANDIDATE FCR: B.S.


TITLE: Comparison of Dose from the AN-PDR 70 t o the U.S.N.A. NeutronSpectrometer

The major objec t ive of t h i s paper i s t o compare the dose reading fromthe AN-PDR 70 t o tha t of the U.S. Naval Academy neutron spectrometer. TheAN-PDR 70 i s used by the Navy extensively and i t measures neutron dose withthe use of a BF(3) counter and a polyethylene moderator which can de t ec t f a s tneutrons and slow them t o thermal neutrons so they can be picked up by thede tec to r . The U.S. Naval Academy neutron spectrometer employs a NE-213de tec to r whose output can be co l lec ted and analyzed through the use of acomputer program developed—UNFOLD. The UNFOLD program takes da ta from thehigh gain and low gain runs and determines the f luence of the 14 MeV peak anddetermines the dose o l the neutron spectrum. Since the output of the AN-PDR70 has u n i t s of mrem/hr and the UNFOLD program y ie lds an output i n r ads / s ec ,die qua l i ty fac tor w i l l need t o be determined i n order t o r e l a t e the two dosereadings. This qua l i ty fac tor w i l l be obtained from ANSI, This paper w i l ly i e ld spec i f ic r e s u l t s from experiments conducted i n die l a s t few mondis.

E-6UNIVERSITY OF IOWELL

PAPER /©STRACT

AUTHOR: Susan M. Reil ly

ADVISOR: Dr. Richard K. Lester

MAJOR FIELD: Nuclear Engineering

UNIVERSITY: Massachusetts I n s t i t u t e of Technology

GANDffiATE FOR: M.S.

PAPER RELATED TO: M.S. thes i s

TITLE: Radiation Damage t o Cation, Anion, and Mixed Bed Ion Exchange Resins

In an effort to investigate the potential detrimental effects ofgamma radiation on radiation on radionuclide retention capability, cation,anion and mixed bed ion exchange resins have been irradiated in the BrookhavenNational Laboratory cobalt-60 gamma pool. Total absorbed doses ranged from 10exp(5) to 5 x 10 exp(8) rads, delivered at a rate of 1.4 exp(6) rads/hr.Changes in resin structure , mass, pH, and exchange capacity were recorded asa function of radiation dose, and severe damage was observed when total doseexceeded 10 exp(7) rads. In general, anion exchangers were found to be lessradiation-resistant than cation resins.

Radiation may also affect the leachability of solidified resins, apoint relevant to the storage of radioactive wastes. To simulate possibledisposal conditions, mixed bed resins were solidified in vinyl ester-styreneand in portland III cement, and the solidified forms were irradiated. Totaldoses ranged from 10 exp(6) to 5 x 10 exp(8) rads, and after irradiation thesamples were subjected to the Anerican NUclear Society 16.1 Standard LeachTest. Leachability of Cs-137, CO-60, Sr-85, and S-35 was investigated, andthe release from the polymer samples was below the detection limit, indicatinga fractional release of less than 10 exp(-5) in 24hrs. Data for cementsamples show that the release of Cs-137 and Sr-85 was significantly reduced inthe irradiated samples, but phenomenon is attributed to greater cement curingduring irradiation (due to the elevated sample temperature), rather than toany beneficial effects of the radiation.


PAPER ABSTRACT

AUTHOR: Frederick F. McWilliams

ADVISOR: George E. Chabot


CANDIDATE FOR: M.S.


TITLE: The Producation and Characterization of High Energy Photon RadiationFields a t the University of Lowell

The University of Lowell has characterized two sources of high energyphotons, 6 and 7 MeV, at the University of Lowell's Radiation Laboratory, f o rthe purpose of measuring the response to personnel dosimetry and radiat ionprotection instruments.

The radiation f ie lds were generated from a N{16) source at the 1 MWresearch reactor and from a F(19) [p , alpha-gamma], 0(16) reaction using aCaF(2) target on the Van de Graff accelerator.

Radiation f i e l d characterization required the iden t i f i ca t ion anddetermination of the extent of ; the electron component, the low energy lowy ie ld photons from competing reactions and positron annih i la t ion photons,andradiation f i e l d uniformity wi th in a volume of in terest . Determination of theradiat ion f i e l d in tensi t ies required an extension of the Bragg-Gray Theory f o rnon-electronic equil ibrium conditions. I t was found that useful radiat ionf i e l d in tensi t ies ranged from 3.9 mR/hr to 150 mR/hr for the N(16) source andfrom 50 mR/hr 2.5 R/hr from the F(19) [ p , alpha-gamma] 0(16) reaction.


PAPER ABSTRACT

AUTHOR: Robert J . Hegarty, Reginald P.T. Tomkins, Gene S. Hall (Rutgers Univ.)

ADVISOR: Dr. William Savin

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: New Jersey Inst i tu te of Technology

CANDIDATE FOR: B.S.


TITLE: Proton Induced X-ray Emission (PIXE) of Oil Shale Samples

A multi-elemental analysis of o i l shale samples from a minimum ofeight geographic locations was obtained by the method of Proton Induced X-rayEmission(PIXE). Preliminary results show trace amounts of Lead, Arsenic,Cadmium and a large percentage of Iron and Titanium. The advantage of usingPIXE analysis i s that i t i s a non-destructive technique using small amounts ofthe sample. Multi-elemental analysis may quickly be acheived with l i t t l e orno chemical preparation of the sample. The conclusion to be drawn w i l lprovide necessary information on the heavy metal cot<centration in o i l shalewhich d i rec t ly affects the environment.


PAPER ABSTRACT

AUTHOR: David A. McLaughlin

ADVISOR: George Chabot


CANDIDATE FOR: M.S.


TITLE: Improvements in a ZnS Sc in t i l l a t i on Chamber for the Direct Measurementof Radon-222

Much research has been devoted to thedevelopment of more re l iab le measuring techniques for radon noble gases andthei r progeny. This presentation reports on improvements made in a standardzinc-sul f ide s c i n t i l l a t i o n chamber (Lucas Cell) fo r the d i rect measurement ofradon-222. To increase the l i g h t output detected by a photomultiplier tubethe 1400cc in ternal ly ZnS(Ag)-coated clear polyethylene chamber has beencovered external ly with a var iety of re f lec t ive surfaces, including aluminizedmylar and f la t -whi te paint . For an increased ef f ic iency, the chamber has alsobeen equipped with an internal anode and cathode to induce a constant e lec t r icf i e l d result ing in the migration of the posi t ively charged daughter ionstoward the detecting medium. This feature also reduces the ef fect of anyelect r ica l f i e l d created by an operating photomult ipl ier tube. Design of thechamber allows for i t s disassembly and removal of the ZnS(Ag) i f contminationfrom the long l ived Pb-210 daughter of the Rn-222 occurs. An NBS traceableca l ib ra t in was performed u t i l i z i n g a radon generation source obtained from thePylon Electronic Development Company of Canada, Ver i f icat ion of the Rn-222emanation rate and ac t i v i t y concentrations of col lected Ice gas samples wasconducted via gamma spectroscopy analysis of the Pb-214 and Bi-214 photopeaksassociated with the decay of Rn-222 daughters. Field test ing of the apparatusis reported as v.'ell as a comparison with results obtained from othermeasurement techniques of the same environment.


PAPER ABSTRACT

AUTHOR: Keith SymmersADVISOR: Prof. Jack Brenizer

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: Universi ty o f V i rg in ia

CANDIDATE FOR: B.S.


TITLE: Neutron Radiation Effects on Integrated Injection Logic Circuit

In this undergraduate thesis, the neutron effects on integratedinjection logic circuits are investigated. In addition, a discussion of thehistory of radiation effects on semiconductors and integrated logic (IZL)technology is included.

The neutron fluence of 4.5 x 1012n-cnr2 was found to render anI2L circuit inoperative. In comparing these results to those of similarexperiments conducted on complimentary-metal-oxide semiconductors (C-MOS), theI L circuit was not as resilient to neutron radiation; but the I2L devicecould withstand more gamma radiation than could C-MOS devices.

R A D I A T I O N

S T U D I E S

E-llUNIVERSITY OF LOWELL

PAPER ABSTRACT

AUTHOR: Peter d. Spacher

ADVISOR: George Chabot


CANDIDATE FOR: M.S..


TITLE: The Use of Semiconductor Devices in Detecting High Energy / HighIntensity Radiation

In th i s study, s i l i con (p-n junct ion) so lar-cel ls have been used, inan unbiased mode of operation, to detect 60Co gamma-rays at exposure ratesbetween 1.02 R/hr to 1O6 R/hr. A l inear reponse of photon-generatedvoltage as a function of exposure rate was observed. Radiation induceduegradation of the c e l l , as measured by output voltage, was observed at highexposure rates only af ter prolonged i r rad ia t ion .

F-lUNIVERSITY OF IDWELL

PAPER ABSTRACT

AUTH3R: George Budeck

ADVISOR: Dr. Gavrilas and Dr. Munno


CANDIDATE FOR: B.S.


TITLE: Silver Retention in Resin Beds

In the radioactive waste processing system in a nuclear power plant,resin beds are used to retain soluble materials from the waste water. Tnisexperiment checks the degree of silver retention by the resin beds used atCalvert Cliffs Nuclear Rawer Plant.

Simulated primary coolant water was made with different pHconcentrations and different chlorine concentrations. To each sample onemilligram per liter of silver nitrate was added. These solutions were runthrough the resin bed columns and samples of water and resin were collected.The samples were analyzed by instrumental neutron activation, and the silvercontent studied as a function of pH and chlorine content.

F-2UNIVERSITY OF IDWELL

PAPER ABSTRACT

AUTHDR: Mircea I . Gavrilas

ADVISOR: Dr. Ma^-ia Gavrilas

MAJOR FIELD: Elec t r ica l EngineeringUNIVERSITY: University of Maryland

CANDIDATE FOR: B.S.


TITLE: Correlations Between Isotopes i n Liquid Effluent Releases and Isotopesin Biological Material

The l i n e a r cor re la t ions between isotopes i n the l iquid effluentre leases a t Calvert Cliffs Nuclear Rawer Plant (C.C.N.P.P.), and the l i nea rcor re la t ions between elements found by isotope neutron ac t iva t ion analysis(I.N.A.A.) in oysters (Crassosea Virginica) w i l l be discusseu.

Functional cor re la t ions between the rad ios i lve r (AG-110 m) releasedfrom C.C.N.P.P. and tha t ex i s t ing i n oysters from the Chesapeake Bay w i l l beemphasized. Information about the b io logica l h a l f - l i f e of r ad ios i lve r i noysters w i l l be obtained.

F-3UNIVERSITY OF I0WELL

PAPER ABSTRACT

AUTK)R: Ruth Chiang Carter

AEVISOR: Dr. Frank Munno

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: d i v e r s i t y of Maryland

CANDIDATE FOR: B.S.

PAPER. RELATED TO: Other

TITLE: Sr-90 Search i n Vegetation from the Vicini ty of Calvert Cl i f f NuclearEbwer Plant

The level of Sr-90 concentration i s evaluated i n vegetat ion from nearthe v i c i n i t y of the Calvert Cliff Nuclear Rwer Plant . Since Sr-90 can be oneof the eff luents from the nuclear power p l an t , i t i s in t e re s t ing t o know i f i tcan be detected In vegeta t ion.

Tobacco leaves were taken as our sample, s ince tobacco farming i spredominent in eas tern and southern Maryland where CCNPP i s located. Thetobacco leaves were dr ied and incinerated. The ash samples were prepared t obe radiologically evaluated in three different radiation detection devices:Liquid-Scintillation Counter, Phoswitch detector, wide Beta counter.

This paper is an evaluation of Sr-^0 in tobacco leaves and adetermination of the best method of Sr-90 detection.

F-4UNIVERSITY OF IJDWELL

PAPER ABSTRACT

AUTIDR: Michelle S. Neuder

ADVISOR: Dr. M. Gavrilas, Dr. F. Munno


CANDIDATE FOR: M.S.


TITLE: The Corrosion of Silver as a Function of pH and Dose in the PrimaryCoolant of a Nuclear Power Plant

The appearance of radiosilver in the primary coolant of a nuclearplant, thought to originate from activated metallic silver comprisingcomponents of the primary, prompted the running of solubility tests on thesilver. By varying the pH (3.3-9.2) of both gamma-irradiated (10 krad/hr) andnon-gamma-irradiated water samples, dissolution of silver added to thesesamples could be determined. Every two weeks, samples were collected, dried,and subjected to neutron activation analysis in order to measure silverconcentration s.

Of most importance and interest is the rapid appearance of suspendedsilver arising in the garama-irradiated water of pH 9.2. By using scanningelectron microscopy, the physical dimensions of these suspensions have beenmeasured, and provide the first step in understanding the chemistry of thissolid. The results of these analyses will be discussed in terms of the effectof pH and absorbed dosp.

F-5UNIVERSITY OF IOWELL

PAPER ABSTRACT

AUT1DR: Angela Munno

ADVISOR: Dr. Maria Gavrilas, Dr. F. Munno


CANDIDATE FOR: B.S.


TITIE: A Study of Liquid Effluents from Calvert Cl i f fs Nuclear Power Plant

Small quant i t ies of radioisotopes a re released in to the ChesapeakeBay by the Calvcrt Cl i f fs Nuclear Power Plant in the form of l iquid waste.These isotopes can be e i t h e r f i ss ion products or ac t iva t ion products. Fissionproducts a re released as a r e s u l t of pin hole leaks o r fa i led fuel .Activation products r e s u l t from ac t iva t ion of corrosion products o r ofimpurities in the water. Tne a c t i v i t y of the l iquid eff luents va r i e s withtime and can be correla ted to plant operat ions. Liquid wastes from both t h i t1 and Unit 2 a re discharged through the same Radioactive Waste System. Bycorre la t ing the a c t i v i t y of l iquid re leases t o the operation of Unit 1 andUnit 2, i t may be determined which plant ( i f e i the r ) i s more responsible forthe discharge activity.

Otter applications of studying liquid effluents include possibleindication of failed fuel elements, and recognition of modes of operation thatconsistently yield higher releases. This could provide information to assistin improving ALARA practices.

F-6UNIVERSITY OF LOWELL

PAPER ABSTRACT

AUTHDR: Susan M. Rei l ly

ADVISOR: Mr. Lincoln S. Clark, J r . & Prof. Otto K. Harling

MAJOR FIELD: Nuclear Engineering /Heal th IfrysicsUNIVERSITY: Massachesetts I n s t i t u t e of Technology

CANDIDATE FOR: M.S.

PAPER RELATED TO: M.S. t h e s i s

TITLE: Reducing the Emission of Argon-41 from the MIT Reactor

Argon-41 i s the major gaseous e f f luent from most research r e a c t o r s ,being generated by neutron ac t iva t ion of the argon-40 t h a t i s na tu r a l l ypresent in the a i r . Argon-41, with a half l i f e of 110 minites, presents ahealth hazard as a garana (E= 1.29 MeV) and a beta (E= 1.20 and 2.49 MeV)emitter.

While the release of argon-41 from the MIT reactor is well within thelimits currently imposed by the Nuclear Regulatory Commission, it is possiblethat these limits will be significantly reduced if new EnvironmentalProtection Agency regulations are adopted. In view of this, amd also in lightof the ALARA (as low as reasonably achievable) concept, work is beingperformed to quantitatively identify the sources of argon-41 production in thereactor, and to propose engineering solutions to reduce or eliminate thesesources. This paper will discuss the current status of this project, which isanticipated to be continued until May, 1984.


PAPER ABSTRACT

AUTHOR: Cynthia dark

ADVISOR: Dr. Gavrilas


CANDIDATE FOR: B.S.

PAPER RELATED 10: Other

TITLE: INAA Analysis of the Chesapeake Bay Oysters

In order to evaluate the effects of the liquid releases from CalvertCliffs Nuclear Power Plant on the Chesapeake Bay fauna a study is in progressto determine the elemental composition of the oysters in the bay. The oyster(Crassostria virginica) is very well suited for such a study because of itsability to accumulate high concentrations of metals in its soft tissues.

The elemental composition of the oysters was measured by instrumentalneutron activation analysis (INAA). A total of 64 samples collected from July1978 to August 1983 were used. These samples were taken from two locations.One location, Kenwood Beach, upstream from Calvert Cliffs is tine controlpoint, while Camp Conoy is downstream from Calvert Cliffs. A comparison ofthe concencrations of different elements in the oyster meat from the twolocations ws done. In the limit of experimental errors there appears to be nodifference in the elemental composition of the oysters from the twolocations. Tnis leads to the. conclusion that there is significant impact fromthe liquid releases on the Chesapeake Bay oysters. We also performed acomparison of the mean concentrations of metals in our oysters to similar datafrom literature.


PAPER ABSTRACT

AUTHOR: Mathew J. SchorADVISOR: Prof. Jack Brenizer


CANDIDATE FOR: B.S.


TITLE: Radioisotooes i n Aquatic Life i n Charlottesvi l le

The University of Virginia operates a two megawatt research reactor.The pond next to the reactor occasionally receives low level l i qu id waste fo rd i lu t ion before being released to the surrounding environment. Thispresentation i s a progress report on samples that have been taken from thepond and a local stream not affected by the pond run-off . The gross alpha andbeta ac t i v i t y of sediment, f lora,and fauna w i l l be measured. Also the gammaemitting isotopes w i l l be ident i f ied via gamma spectroscopy.

E N V I R O N M E N T A L

A N A L Y S I S

R E A C T O R R E S E A R C H

A N D

D E S I G N

G-lUNIVERSITY OF IOWELL

PAPER ABSTRACT

AUTHDR: Midn 1/C Steven J . Berninger

ADVBCR: Prof. Martin E. Nelson

MAJOR FIELD: Marine EngineeringUNIVERSITY: U.S. Naval Academy

CANDE&TE FOR: B.S.


TITLE: Sens i t iv i ty Analysis of U. S. Naval Academy Spectrometer

The USNA neutron and gamma spectrometer, which employs an NE-213de tec to r i s present ly being used t o measure shielding coeff ic ients and theadaquacy of ce r t a in neutron and gamma detect ion equipment. For a givenmeasurment the spectrometer gives the enegry spectrum and dose associated witha given rad ia t ion f i e l d . Hawever, fbe bas i s of the analys is involves a numberof ana ly t ica l techniques such as date ranormalization and smoothing. Inaddition, the analysis is apparently affected by such factors as differencesin neutron intensity between runs. Tne purpose of this paper is toinvestigate the influence of these factors on determination of the shieldingcoefficients and energy spectrum as determined by the analysis of thespectrometer data.

G-2UNIVERSITY OF IOWELL

PAPER ABSTRACT

AUTHOR: Juan Vitale

ADVISOR: Dr. William G. Vernetson

MAJOR FIELD: Nuclear EngineeringUNIVERSIIY: University of Florida

CANDIDATE FOR: B.S.


TITLE: HTCR Application for Enhanced Recovery of Heavy Oil

'Ihe high temperature gas-cooled reactor (HTCR) operation in theprocess Sceam / cogeneration (PS/C) application is discussed The processsteam phase is used for supplying steam for enhanced recovery of heavy oil andthe cogeneration phase to export electricity. The technical merits of an 1170MW(t) HTGR PS/C are compared with those of coal- fired plants and oil-firedboilers for this application.

G-3UNIVERSITY OF IOWELL

PAPER ABSTRACT

AUTHDR: VLttorio Pareto

ADVISOR: Dr. J . Driscol l

MAJOR FIEID: Nuclear EngineeringUNIVERSITY: Massachusetts I n s t i t u t e of Technology

GAND1MTE FOR: Ph.D.


TITLE: Duplex Fuel Pellets

A duplex fuel pellet is a solid cylindrical fuel pellet with twodistinct enrichment zones. The central zone is made of depleted or naturaluranium, and the annulus of enriched uranium.

Most of the power of a duplex pellet is generated in the outerannulus. This results in coasiderable reduction in both the center-line andthe pellet average temperatures. For example, a 20% core volume duplex pelletirradiated at 5.725 kW/ft was found to have a volume average temperature66.5 F lower at BOL and 32.8 F lower at EOL than a homogeneous design.

The benefits from: lower fission gas release, higher operatingmargins, lower pellet clad interaction, and reactivity gains from selfshielding, were quantitatively analyzed. Also the additional cost of a duplexpellet was determined to be $25/kgHM higher than for standard homogeneouspellets for the 25% core volume case.

This higher cost, which translates to 1 - 2 % of the total fuel cyclecost, suggests that utilities will only accept duplex pellets if they perceivea commensurate increase in capacity factor for their use. For large reactorsthis may well be the case.

G-4UNIVERSITY OF LOWELL

PAPER ABSTRACT

AUTHOR: Fred Carpenito

ADVISOR: Dr. John R". White


CANDIDATE FOR: M.S.


TITLE: Three Dimensional Modeling of Optimum Moderation in New Fuel Storage

C r i t i c a l i t y analyses of new fuel storage i n the presence of foam ormist has lead some people to the conclusion that stages of superc r i t i ca l i t yare possible at high moderator void. However, th is conclusion may be due tounreal is t ic geometric modeling of new fuel storage configurations. Inpar t i cu la r , the axial and radial components of leakage become more importantto c r i t i c a l i t y at high moderator void. I t i s the purpose of th is work toshow, that three dimensional modeling of new fuel storage is necessary toperform a rea l i s t i c c r i t i c a l i t y analysis at high void.

We have studied new and spent fuel storage c r i t i c a l i t y using theNITAWL-KENO-IV methodology with the 123-Group XSDRN l i b ra ry . This methodologyhas been validated at Yankee fo r new fuel storage rack c r i t i c a l i t y analysis.We have analyzed new fuel storage c r i t i c a l i t y as a function of moderator voidconfigurations. They a l l show the same resu l ts ; that two dimensional modelingleads to extraordinary high values of Ke f f a t optimum moderation andthree-dimensional modeling usually leads to values which are well below theNRC l i m i t of .98.

G-5UNIVERSITY OF IDWELL

PAPER ABSTRACT

AUTHOR: Robert Broughman

ADVISOR: Dr. Ralph Belcher


CANDIDATE FOR: B.S.


TITLE: Detection of Fuel Rod Pinholes by Pool Water Analysis

A Ge-Li de tec tor w i l l be used t o determine the i so top ic content ofthe poolwater from the U of Md's 250kW TRIGA reac tor . The presence of f i s s ionproducts in the water would be an indicat ion of pinholes i n the fuel rods .This method i s cur rent ly i n use a t t he U of Md. and w i l l be discussed.


PAPER ABSTRACT

AUTHOR: Bouvard HostickaADVISOR: Prof. Bryce Shriver

MAJOR FIELD: Nuclear EngineeringUNIVERSITY: Univers i ty o f V i rg i n i a

CANDIDATE FOR: B.S.


TITLE: A Heated Fast Neutron I r r ad ia t i on F a c i l i t y

An irradiation facility has been designed, built, andtested that permits easy access to a dry, heated Volumein the reflector of a M.T.R. type research reactor.Resistance heaters arranged in redundant zones andthermocouples intermixed with the materials under irradiationprovide; a closed loop temperature control system that willmaintain the test samples at a constant temperature over therange of 200 to 450°C. The exterior of the facility isinsulated from the heated region and cooled by divertingapproximately 1% of the primary coolant flow to channelswithin the facility. Boron shielding reduces the thermalneutron fJux that will activate the samples while the fastflux (K>\ MKV) is 5E12 nv. Access to the heated volume ofabout 350 ml is provided by a dry Lube extending from the coreto above the pool water level. The entire assembly occupiesone fuel or graphite assembly location in a standard M.T.R.type pool reactor. These facilities are currently being usedto irradiate prospective pressure vessel steel samples in theUniversity of Virginia Reactor.


PAPER ABSTRACT

AUTHOR: David Chapman, Ernie Lee, Andrew Nicholson, Ray Roy, John GaleLionel Wertz, Mark Durrenberger, and Jocelynne Guay

ADVISOR: Dr. James Phelps, Dr. Gil Brown


CANDIDATE FOR: B.S.


TITLE: A Liquid Fuel Gas Cooled Reactor (LFGR): An Inherently Safe Concept

In response to th is year's A.N.S. Student Design top ic , an inherently safereactor concept i s proposed which incorporates the concepts of modularizing onl i ne fuel reprocessing, and constant degassif ication. The reactor i s a l i qu idfueled, gas cooled, graphite moderated concept u t i l i z i n g a "kidney"reprocessing feature. The inherent safety i s real ized through constantremoval of the source term.


PAPER ABSTRACT

AUTHOR: Pedro Perez



CANDIDATE FOR: M.S.

PAPER RELATED TO: Thesis

TITLE: Space Dependent Neutron Noise in a Multi-Region Reactor

A nuclear chain reacting system i s basical ly a complex non-linearent i ty i n the time domain. The dynamic variables describing such a systemfluctuate in a stochastic fashion about a mean value. I t i s impossible toexactly predict future values of these variables, but rather one can onlyspecify the probabi l i ty that they w i l l assume a cer ta in value. The dynamicresponse character ist ies of a reactor can be described in an average sense bythe f luctuat ions in power due to periodic disturbances. The responseobtained, as a function of the frequency of the pertubation, is cal led thereactor 's transfer funct ion.

american nuclear society eastern regional …

Documents