slide presentation by general atomic on gas turbine ... · ulw 0] i--z w a x5 u-4000 3000 2000 1000...

I. [ /rt .2

GT-MHRADVISORY GROUP-OConstelationO Nt'ear

5fDominion-

WHO,WHAT & WHYPre-application NRC Meeting

12/03/01Entergy

NM7 )Uf)

I

UTILITY ADVISORY MEMBERS--WHO

* EntergyNuclear- Dan Keuter, Utility Advisory Board Chairman

Entergy

NMo)* Nuclear Management Company* Dominion* Omaha Public Power District* PSE&G* Constellation

:Dominion-

ConstelationO Nicear

* Other

Current Support - > 30 % of IndustryI

UAG STRUCTURE

I.

ACADEMIC ADVISORY GROUP (AAG)

Members* University of California at Berkley

- Per Peterson, Chair* MIT* University of Michigan* Oregon State* Texas A&M* Wisconsin* University of Florida* Ohio State* Purdue* Penn State

UTILITY. ADVISORY MEMBERS--WHAT

UAB Purpose .-.. .-* Provide Industry Guidance on:

- Development and Deployment of GT-MHR

- Coordination with Industry (NEI, NRC,EPRI & DOE)'Activities to MaximizeEfficiency & Prudence of Efforts

* Facilitate Incorporation' of Lesson Learned FromEarlier Gas Reactor' Licensing and OperationalExperience'

U.S. Commercialization of GT-MHR

"SUPER-SAFE" DESIGN --WHY

* Meltdown Proof-High Temperature Fuel Capacity-Passive & Conductive Cooling

* Low Security Risk-Below-Grade Construction Arrangement-Silo-No Power Required

* No Active Safety Systems-No Emergency Core Cooling-No Emergency Diesels

* Proliferation Resistant-Ceramic Fuel Makes Retrieval Difficult-Low Fissile Fuel Volume Fraction-High Fuel Burn-up / Pu Degradation

GEN IV Benefits at CCGT Prices

Gas Turbine - Modular Helium ReactorSafety A pproach

.

- .Presented to NRC Staff3 December 2001

Laurence L ParmeManager, Reactor Safety & Licensing

General Atomics

. . . .

- : - . +GENERAIL ATOMICS

Modular Gas-Reactor Safety ApproachDiffers From Earlier Reactor Designs

GT-MHR safety emphasizes

- Keeping radionuclides at source during all accidents- Minimizing reliance on active/complex engineered systems

* Passive safety design based on reoptimized application ofestablished HTGR technology- High temperature compatible fuel and core- Single phase, chemically & neutronically inert coolant- Specially tailored core power and geometry

Conservative, robust design with defense-in-depth remain keystones of safety

+ GENERAL ATOMICS

Key to GT-MHR SafetyMultiple Ceramic Fuel Coatings1. . I I ~ ',I : . .. , , ,, 7

.I"

_ A c :S z bOr a *'_ ~ b,- w

Pyrolytic CarbonSilicon CarbidePorous Carbon BufferUranium Oxycarbide

TRISO Coated fuel particles (left) are formed into fuelrods (center) and inserted into graphite fuel elements(right).

"IIIF,. III,I',

,II

'I',

I'

III

Ale,=. .7 -6

-, 71s1" .:

II- _I -

5~t _7i Adkrfl .id

PARTICLES COMPACTS FUEL ELEMENTS

+ GENERAL ATOMICSL-029(5)4-14-94

Coated Particles Remain IntactEven at Very High Temperatures

LGuX z_, [~sbe p A.s.._ ., _S.s-_; w_...,.*_.w.j.i .. ~ .- ..... ...... 48 !0-1.0

0.8

z0U

LL

U-

0.6

0.4

0.2 -

1 001 000 1200 '1400 1600 1800 2000 2200 2400 2600

FUEL TEMPERATURE (DC)

L-266() 4+ GENERAL ATOMICS7-28-94W-9

Safety Focused on AssuredFuel Particle Integrity

Retain Radionuclides in Fuel

Control Heat Generation Remove Core Heat Control Chemical Attack

* Fission (heat generation) shut down without rod motion

* Heat removal assured by reactor design- Low power density- Low thermal rating per module- Annular core and high LID ratio

* Chemical attack limited by design & materials- No high pressure water source in gas-turbine plant- Nuclear graphite, geometry, and limited air control-

potential oxidation

-+ CENERAL ATOMICS

Heat Generation Stops DuringLoss of Cooling Without Rod Motion

.-I - . . . . - I - . -------

TIME (DAYSI20 1 3 450 I l l l l

1-

I-

0!R-j

V-

U-

C3

0

U,

0.

I,-I-

0.

40

30

/ NO REACTOR SCRARA Pressurized Loss of Forced Cooling

Power controlled by negative00 temperature coefficient

1REACTOR RECRITICAL

Af A^ _ _ _ _

20-

10

I. ,_ I. 'I0

-16 0 16 32 48TIME (HOURS)

64 so 96 112

+ GENERAL ATOMICS

Core Temperatures Maintained at SafeLevels With and Without Reactor Trip

1Ms~~o r .zJD4bt- = _ _; _

U

3-

2000

150 '1

..1000

I500

0 50

TIME (HOURS)

1W0

+ GENERAL ATOMICS

Passive Heat RemovalChanges Reactor Design Philosophy

--. a . . -.* . X'., _ ... A . b ., . _ W. , .-. 4 i t-H

0

111

w

UlW

0]

I--

zwaX5u-

4000

3000

2000

1000

4000

3000LARGE HTGRsI--nsv^Ss

RADIONU CLID ERETENTION IN

I.JUUU MIN(t).1 FUEL PARTICFSV F i ;-1

lj jPEACH BOTTOM

[115 MW(T)]

MHR

;LES

zzzzzzd2000

1000

I I I1967 1973 1980 1985

CHRONOLOGY

SIZED AND CONFIGURED TO WITHSTAND EVEN A SEVERE ACCIDENT

+ GENERAL ATOMICS1-222(1)1-12-96

ANNULAR CORE LIMITS FUELTEMPERA TURE DURING A CCIDENTS

X 36 X OPERATINGCONTROL RODS

CORE

.I .-t~ ... .

I , . .. I I

ACTIVE CORE102 COLUMNS10 BLOCKS Hi

BORATED PINS (TYP)

REFUELING-PENETRATIONS

-12 X START-UPCONTROL RODS

'18 X RESERVESHUTDOWNCHANNELS

ANNULAR CORE USES EKISTING TECHNOLOGY-+ GEiERAL ATOMICS

L-199(10)6-9-95

Temperature Gradient Provides DrivingForce for Residual Heat Removal

600 MW/102 Column2000

35001800

1600 -- ------ -------- - - -m - m- 3000

~-1400

10 1200

CenRadiu Vesselhes)

1000 ReflectorE800 10' 600

400 RSR RSR PS

200So0 10 20 30 40 50 60 70 80 90 100 110 120 130 140150

Radius (inches)

+ GENERAL ATOMICS

Heat Removed PassivelyWithout Circulation or Coolant

HEAT REMOVED BY:I .

. * CORE CONDUCTION

- - CORE INTERNAL RADIATION

I VESSEL RADIATION'

* RCCS CONVECTION

CORE

AIR COOLEDRCCS PANELSVESSEL

CONTROL RODS

+ CENERAL ATOMICS

FUEL TEMPERA TURES REMAIN BELOW DESIGNLIMITS DURING LOSS OF COOLING EVENTS

1800

1600

C-

a)L..

3

L-

a)0-EWI-

U.

1400

1200

1000

800

6000 2 4 6 8

Time After Initiation (Days)

passive design ensures fuel remains below 1600C

+ GENERAL A TOMICSL-340(3)11-16-94

Risk From Water IngressSignificantly Reduced in G T-MHR

* No steam generators therefore no high pressuresteam source

* Precooler and intercooler water pressure belowprimary coolant operating pressure

* Low water pressure in heat exchangers greatlyreduces potential for water ingress during normaloperation

* Liquid water transport to core under depressurizedconditions as unlikely as in steam cycle system

. .

ju CENERAL ATOMICS

Leakage is Out of Primary CoolantSystem Following Tube Break

_ ..i_._4.s i _.b_.. .. &..a..a4..J....& &I I I-.I.... ..... .je _ ' '.4 4Ji-aa eI ..:. -a-

0.1 F ' ''

-0.2

E- -0.5

0LL -0.8CZa)

-j

-1. 1

-1.4 I I I-1. 39 79 120 160 2)00

Time After Initiation (sec)

+ GENERAL ATOMICS

Inherent and Passive FeaturesControl Air A ttack

* Non-reacting coolant (helium)

Embedded ceramic coated particles

* Air ingress limited (requires failure of Class Ivessels) -

* Below grade, closed reactor silo (isolation)

* Air flow rate limited by core flow, area (L/D > 700)

* Slow oxidation rate (nuclear grade graphite)

4 GENERAL ATOMICS

Low Potential for Graphite Fires

* Test results successfully compared favorably tocomputer code (AIP) predictions

* Extremely low probability of burning graphite- requires temperatures above those during

operation or accidents, and- requires large quantities of air

* MHTGR analyses show introduction of air resultsin limited, decay heat driven oxidation

+ GENERAL ATOMICS

Graphite OxidationLimited by A vailable Ail

OPENING AT TOP I

/Z - INGRESS OF ONE VESSELI - NEGLIGIBLE OXIOATION

I .A

VOLUME

CROSS DUCT VESSEL FAILUbRE-s

- INGRESS OF ONE SILO VOLUME- OXIDATION MINIMAL

1. ~ ._ . ..

. 1 , I

OPENING AT BOTTOM

- NO INGRESS- NO OXIDATION

+ GENERAL ATOMICS

- OXIDATION SMALL

Mass Transfer, Core Temperature, &Graphite Purity Limit Oxidation Rate

-.S _~fj-ziz :X .........................................*_O ..._47._XiZb*$,_; .................J1 l_4_b---*1.

1a0

LU

CL,

uJ

U

ac

LU

CI-

LO

LA.

10-1

10-2

10- 3

10-4

22 FT2 CROSSDUCT VESSEL FAILUREWITH UNLIMITED AIR SUPPLY (APP. G.41

22 FT2 CROSSDUCT VESSEL FAILURE(APP G.4)

LU

-j

8 K

9Es

1 M

0.0513 IN.2 RELIEF VALVE FAILURE (DBE-10)

0.05 IN.2 INSTRUMENT LINE LEAK (DBE-11)

VI . I I l- I10-50 5 10 15 20 25 30

TIME PAST INITIATING EVENT (DAYS)

+ GENERAL ATOMICS

Below-Grade Siting AugmentsEnhanced Safety

Reactor equipment Positioner Refueling Reactormaintenance and machine auxiliaryrepair building building * Reduced seismic

Crane central room responseElectrical-technical

building \ Earth provides ultimateIf ' 1 j heat sink

IL, t - fjZ. * Robust structure~ ~ J~ -Additional holdup of

accident releases"

7i-R, Reduces vulnerability of- 17 rmI r ocore and key safety

oe , Reaco features to surface

Reactor

Reactor building + CENERAL ATOMICS

GT-MHR Optimization of EstablishedGas Reactor Features Provides

* Enhanced, easily understood safety

* Assured accomplishment of safety functions withsimple, passive features

* Limited consequences, even for beyond designbasis accidents

SAR intended to provide fulldemonstration of safety

+ GENERAL ATOMICS

Pre-Application Licensingfor the

Plan

Gas Turbine - Modular Helium Reactol*XA-.-- ...- d .- _ , l. ; , w~-

Presented to NRC Staff3 December 2001

Laurence L ParmeManager, Reactor Safety & Licensing

General Atomics

+ GENERAL ATOMICS

Objectives olPre-application Interactions

* Seek NRC licensability statement on- GT-MHR design licensability- Safety and licensing approach

* Establish foundation for future application- Combined License (COL) for a first module- Design Certification for the GT-MHR plant

NRC Advanced Reactor Policy guidance encouragesearliest possible interaction- Most effective regulation for advanced reactors- Timely, independent assessment of the safety

characteristics of advanced reactor designs

+ GENERAL ATOMICS

Licensing Plan OutlinesPre-application Activities

W

* Identify and schedule pre-application activities

* Define objectives and expectations

* Ensure planned activities facilitate future application

* Record NRC staff / GT-MHR agreement on plannedactivities

+ GENERAL ATOMICS

Significant History olHTGR Licensing Exists

Peach Bottom 1 ('67 -'74)

- Construction License

- Operating License ='r

- Decommissioned E ie

* Fort St Vrain ('79 - '88)- Construction License- Operating License- Decommissioned

i Large HTGR (mid '70s)- Summit 1 & 2 construction permit

issued- Fulton I & 2 PSAR submitted

+ GENERAL ATOMICS

MHTGR - Starting Point folGT-MHR Interaction

* Steam cycle MHTGR interaction withNRC in mid-1 980s

* Key items submitted for review- Top-level regulatory criteria- Risk informed licensing bases- Probabilistic Risk Assessment- Prelim Safety Information Document

* Extensive review by NRC staff andnational labs

* MHTGR evolved to Brayton cycle GT-MHR in early 1990s- Similar safety characteristics- Similar licensing approach

+ GENERAL ATOMICS

5 Areas Proposed forDiscussion

* Programmatic and Process Topics

* Licensing Approach

* Technology Development- Fuel- Graphite- Metals

* Design Description

* Accident Analyses

+ CENERAL ATOMICS

Pre-applica tion TopicsAddress draft SAR

b.... ... -~,j M n T Safety AnalysisMeeting Topics . epr

I - - - - - Chapter 3|Opening - - - - - LicBasis

Programmatic ChapterI ,_ _ _i _m _____Capte 4Issues _ _ - ---- Reactor-

_I ll I II__ _ ____Reactor __

Licensing Approach -- - j j j Chapterr Fue I -llj VesselsFuel I ll I

Technology _I Chapter 6 -1 1 0Graphite I lii r-- Other SystemsI Technology

Metals F- l _ _ _ ChapterlI 1Technology Op RN Control

| u Dsi g n --- - - --- r-- Chapter14…-~ LTesting

Accient nalyis -- 7'Chapter15I| tA alysisrF-Accident Analysis

+ CENERAL ATOMICS

Proposed Schedule of ActivityTied to Design

MILESTONE DATE

Pre-Application Phase

Opening meeting December, 2001Programmatic and process topics January-March, 2002Licensing approach February-April, 2002Technology development April - August, 2002Design Assessment June - November, 2002Submission of draft Safety Analysis Report (SAR) March, 2003NRC licensability statement June, 2004

Application Phase

Submission of SAR July, 2004- Combined License (COL) application- Design certification application

Combined License Issued June, 2007Design Certification Issued TBD

+ GENERAL ATOMICS

Interaction Processduring Pre-application Phase

* Topical Meeting- GT-MHR presentation on topic or issue- NRC comments or questions at meeting

* GT-MHR follows up meeting with writtendocumentation of presentation- Letter- Report- Draft SAR format

* Written comments or queries from NRC

* GT-MHR response

Licensability statement is final comment+ CENERAL ATOMICS

GT-MHR PLANT DESIGNOVERVIEW*

,.

;- . I .l 'Presented to NRC Staff. . II- December 3, 2001

Arkal ShenoyDirector, Modular Helium Reactor

General Atomics

M-273(1)8-27-01

+ GENERAL ATOMICS

Presentation Outline

* Design goals & requirements

* Design description

* International Program

* Commercial Program

* Design status and deployment schedule

* Conclusions

+ GENERAL ATOMICS

PLANT USER REQUIREMENTS

Plant sizes:300-1 200 MW(e) range

Equivalent availability >80%-

* Meet existing safety and licensing criteria with norelease.requiring public sheltering greater than5X1 O-7 per year

* 1 0% power cost advantage over Fossil Fuel

M-273(5) G GENERAL A TOMICS8-27-01

ADDITIONAL REQUIREMENTS

* Utilize inherent characteristics for passive safety

* Do not require operator action (insensitive tooperator error)

* Provide long time intervals for corrective action

* Actively support of users and suppliers duringdesign and licensing

+ GENERAL ATOMICSM-273(6)8-27-01

MODULAR HTGR DEVELOPMENT FOCUSEDON GEN IV GOALS (for past 15+ years)

K* i,-, J.. a~4,^a.. ?A.*Wb 4 -1fl: ;-a.:.M @i L S'y.~J C.'. .'4$*; Av*.I8A.4tJ 6*.4.. e. * 4tli.AWB 4r"en. S*g.>'4d^4s *a.*.,.4.- t x.. _

* Modular HTGR first'-conceptualized in early '80s toprovidedsimple,' enhanced SAFETY

* GT-MHR conceptualized in early '90s to provideenhanced ECONOMICS

* Gas reactor'TRISO coated particle fuel form ideal forspent fuel WASTE

* Fissile fuel inventory, isotopic composition, and fuelform' provides PROLIFERATION resistance

+ GENERAL ATOMICS

MHR DESIGN A PPROA CH

* Utilize inherent characteristics- Helium coolant - inert, single phase- Refractory coated fuel - high temp capability, low release- Graphite moderator - high temp stability, long response times

* Utilize existing technology, successfully demonstratecomponents and experience

* Develop simple modular design- Small unit rating per module- Below-grade installation

* Develop passively safe design- Annular core, large negative temperature coefficient- Passive decay heat removal system- Minimized powered reactor safety systems

M-273(7) + GENERAL ATOMICS8-27-01

SUMMA R Y DESCRIPTION OF G T-MHR DESIGN

Plant Design- Electrical output 286 MW(e) per module, efficiency = 48%- Four identical reactor modules located below grade- Each module includes Reactor and Power Conversion System

* Reactor System Design-;;600 MW(t), 102-column annular core.-> Hexagonal prismatic blocks similar to FSV.-- TRISO ceramic particle fuel- Redundant reactivity control system

* Power Conversion System Design- Generator, turbine, and two compressor sections on a single shaft- Magnetic bearings

- Plate-fin recuperator

- Cross-counterflow, water-cooled precooler and intercooler

M-273(26) + GENERAL ATOMICS8-27-01

, - _ - I _ - -

GT-MHRCOMBINES

MEL TDO WN-PROOFADVANCEDREACTOR

WITHHIGH EFFICIENY

GAS TURBINE

POWER LEVEL600 MWt

+ GENERAL ATOMICS

4 MODULES COMPRISE, STANDARD-.... .-...-. PLA N T

... . ... ........... .... . . .. - -... ...--------.................-.......- . ... ........... -... ..................... ..

.. .. ; .I .- .. - I .;

. .I I

M-273(27)8-27-01

+ CENERAL ATOMICS- . . . . .. I .- .

U.S. AND EUROPEAN TECHNOLOGY BASES FORMODULAR HIGH TEMPERATURE REACTORS

b . i. ... -!. .. I I . .... . . . . .

BROAD FOUNDATION OF HELIUM REACTOR TECHNOLOGY

+ GENERAL ATOMICS

MODULAR HELIUM REACTOR CHARACTERISTICSA TTRA CTIVE FOR- GEN IV GOALS

Helium gas coolant (inert)

h Refractory fuel(high temperature capability)'-

- * Graphite reactor core. . .. -(high'temperature stability),

* Low power density (order of magnitudelower than LWRs)

. Demonstrated technologies

.. .EFFICIENT, RELIABLE PERFORMANCEWITH INHERENT SAFETY

,(3) .. CENERAL ATOMICSL-2716-6-9 5

CERAMIC FUEL RETAINS ITS INTEGRITYUNDER SEVERE ACCIDENT CONDITIONS

Pyrolytic CarbonSilicon CarbidePorous Carbon BufferUranium Oxycarbide

TRISO Coated fuel particles (left) are formed into fuelrods (center) and inserted into graphite fuel elements(right).

I::

t

PARTICLES COMPACTS

L-029(5)4-14-94

FUEL ELEMENTS

+ GENERAL ATOMICS

a

ANNULAR REACTOR CORE LIMITS FUELTEMPERA TURE DURING ACCIDENTS

REPLACEABLE CENTRAL 36 X OPERATING& SIDE REFLECTORS CONTROL RODS

OPF RARRFL _ BORATED PINS (TYP)

I

ACTIVE CORE"102 COLUMNS''10 BLOCKS HIGH -

PER MANE NTSIDEREFLECTOR

REFUELING,.PENETRATIONS

-12 X START-UPCONTROL RODS

18 X RESERVESHUTDOWNCHANNELS

... ANNULAR CORE USES EKES77NQ TECHNOLOGY+ GENERAL ATOMICS

.... .. 'IL-199(10)6-9-95

POSSIBLE HEA T REMO VA L PA. THS. WHEN' NORMALPOWER CONVERSION SYSTEM IS UNA VAILABLE

#, , , , , , , , , . '.1 - - :, � '- .. . - -�- ", t '.., , , , .. � , .. 4 - I- ,. I . � . 'I:., " . ��,

ReliefValve

A. 4

I

SurgeTank

A) Active ShutdownCooling System

B) Passive Reactor CavityCooling System

C) Passive Radiationand Conduction ofAfterheat to SiloContainment(Beyond DesignBasis Event)

.. D ENSE -INs-EPTH BUJTTRESSED VYINHlERENT CHARA CTETI1FS


F-

0

GT-MHR DEVELOPED FORENHANCED ECONOMICS

* Thermal Efficiency 'of HTGR Power Plants with.Rankine,-(Steam) Cycle 'Limited to -38%

* Direct Gas Turbine (Brayton) 'Cycle LongTimeVision and Incentive for HTGR Development

* Gas Turbine Brayton Cycle Improves Economics- Significantly increases thermal efficiency- Significantly reduces plant equipment requirements

.GENERAL A.OMICS

HIGH TEMPERA TURE GAS REA C TORS HA VEUNIQUE ABILITY TO USE BRA YTON CYCLE

, I . . ...1. -. - .1 . .. ... .. . . ...- -P -...I I A ... i-. ~. l , .. . .

we 0-

GT-MHR

LL)

U-

I-

z-j

50

40

STEAM CYCLE

(RANKINE)STEAM CYCLE

MHR

GAS TURBINECYCLE

(BRAYTON)

30400 1000 1 600

TURBINE INLET TEMPERATURE, -F


T-S DIAGRAM

2,000

-. 1,500IL.0

X 1,000aftnoE-2 5

F--500

0 - I0 .1 2 3 4 6 . 7

o0 I 1 2 3 4 5 .6 7Entropy (Btu/Ibm-R)

M.272(38)8-27-01

4. CENERAL ATOMICS

GT-MHR FLOW SCHEMA TIC* 3

LOW PRESSURECOMPRESSOR

+ GENERAL ATOMICSL-271(12a)8-14-94A-36

a

TECHNOL OG Y AD VANCEMENTSHA VE ENA BLED THE. GT-MHR

ai .. ga,.z:ae-'_ .xs ..\'_^ ._: 4fi.XjV} . g,.*. ;. t.s-Oh's.. .. J* .4. -I'V-% .At:, ._..w' .r..k..'t.g__4.-b: Aa~U.& c.¶%W ,b X , ti9 . . .:_ .Y w z ;a . ..

* Small Passively Safe Modular Helium Reactor- turbine size requirements reduced- insensitive to turbine failure accidents

* Large Gas Turbine Engines- significant increase in industrial applications .

- size now match modular reactor. size

I Magnetic Bearings:- eliminates oil ingress concerns- improves performance and reliability.,.- rapidly increasing industrial experience; larger sizes

* Compact Heat Exchangers- dramaticallyimproves efficiency- size improves design integration- extensive fossil operating experience

+ GENER AL ATOMICS

C S '.1l Nculmn - H Rctorcontrol vU\ Icc\asscnghiks

I,. -, ... m;.,., .>..... e>b\l I I

GA S I IPLANTGT-MHR COMBNCTE I

IEREACTOR PA CK,.GE

POWER LEVEL I

600 M L4t

Iil( ctIscI- Snii wrI A)'SICouin

+ GENERAL ATOMICS

d0

CONTROL BASED ON-3600-RPMS YNHRONIZED GENERA TOR

- Reactor controlled to maintain constant turbine :,inlet temperature'during normal power' operation

'* Turbine bypass valve provides short term control.^ ,Rapid load following

- Machinery protection

' Inventory (coolant pressure) control provides long'term load control while maintaining high cycleefficiency

* Motorizing- generator with frequency convertorprovides startup and shutdown cooling capability

M 27+(32) GENERAL A rOMICS8-27-01

HIGH LEVELWASTE

3

0

Cu

w pL.

qua>> 454- U

w t.mIiwf

G T-MHROFFERS MAJOR

ENVIRONMENTALBENEFITS

LWRs GT-MHR

ACTINIDEPRODUCTION

THERMALDISCHARGE

3

c0

4.- u 2= =320)00ah °

a- >.> 4.4. U

M c IUa,Lu

0

3

______________________t ��1I

LWRs Produce150% more

c0

,.. *r

s -ah p

0) >.

4> U.2 c 1

: U

iu

0LWRs GT-MHR LWRs GT-MHR


F.

a

GT-MHR IS PROLIFERA TION RESISTANT AND- SA TISFIES SAFEGUARD REQUIREMENTS

* GT-MHR utilizes low enriched fuel

* Fuel particle refractory coatings make fissile materialretrieval 'difficult

* Low fis'sile material volume fraction makes diversionof adequate heavy metal quantities -difficult "

* High spent fuel burnup degradation of Pu isotopiccomposition make it unattractive for weapons

* Neither a developed process nor capability anywherein world for separatin'g'fissionable material from GT-MHR'spent fuel'

+ GENERAL ATOMICS

IN SUMMA R Y, G T-MHRMEETS ALL DESIGN REQUIREMENTS

* High level of inherent safety eliminating core meltwithout operator action

* Brayton cycle power conversion system for highthermal efficiency (-50% higher than LWRs)

* Low electricity generation cost (reducedequipment capital and O&M; high thermalefficiency)

* Significantly reduced environmental impact* Superior radionuclide retention for long-term

spent disposal

* High proliferation resistance+ CENERAL ATOMICS

GT-MHR Being Designed for Prototypein Russia for Disposition of WPu

* April 1993: Minatom/GA MOU on joint GT-MHRdevelopment for commercial units

* June 1994: Russia proposes to build GT-MHR atSeversk to burn Russian WPu

* July 1994: GA and Minatom each pledge $1M for initialwork--

* Jan 1996: Framatome & Fuji Electric join GT-MHRprogram

* Dec 1997: Team completes Conceptual Design

* Sept 1998: GT-MHR becomes an option within theUS/RF Pu Disposition Strategy

* Jan- 2000: Work started on Preliminary Design

+ GENERAL ATOMICS

G T-MHR NOW BEING DE VEL OPEDIN INTERNA TIONAL PROGRA M

.a.. ......... . . . . . -. = . .

* In Russia under joint US/RF agreement formanagement of surplus weapons Plutonium

* Sponsored jointly by US (DOE) and RF (Minatom);supported by Japan and EU

* Conceptual design completed; preliminary designcomplete early 2002

+ GENERAL ATOMICs

INTERNATIONAL GT-MHR PROGRAM'M�- %.

* Design,operatemoduleRussia

construct andprototype GT-MHRby 2009 at Tomsk,

Reactor eqtiipmentmaintenance andrepair building.,

Positioner Refiteling Reactort machine auxiliary

/ building

* Design, construct, andlicense a GT-MHR Pu fuelfabrication facility in Russia

* Operate first 4-module GT-MHR by 2015 with a 250 kg

-plutonium/ year/moduledisposition rate

....Fuel contains Pu only... No fertile component

X Reactor building

+ GENERAL ATOMICS

COMMERCIALIZA TION PROGRAMi S.,.... .... .. -. 1. I, -. ... 1. -X -, v f, .: -.- - A. , i, ... .. ... ., u ^,. .:. 1. .. aI. -~ ,- A. ---. 4...M,.,*4. :;1I. I;- - ,.;- a. X, .-. .- .'_; d," . I . . ,: , v . . , " , -

COMMERCIALPROGRAM 1=

INTERNATIONALPROGRAM

TECHNOLOGY+

URANIUM FUELRATHER THAN

Pu FUELL . a. .. ...~ X ic'-Aid T O NE L>."ai ".C -....................

Plant construction can start in 5 years

+ GENERAL ATOMICS

q * . 6

so

LIMITED ENGINEERING WORKREQUIRED

-~~~. wsA e Gd-dA e i . .;.......................... : in.... wu -,% b .... X."--;*aw . =I IMr v~b,§_ tzW<e% *

COMMERCIALPLANT ..

ENGINEERINGt ~ ~ ~ ~ ~ ~ ~ C. 2-, ''i_ Cl...~.# ^0

I Y

DefineCommercial

PlantRequirements

ITransfer

InternationalProgram

Technology

IPrepare

IncrementalDesignItems

m

Safetyand

Licensing

PerformanceAssessments

+ GENERAL ArOMICS

slide presentation by general atomic on gas turbine ... · ulw 0] i--z w a x5 u-4000 3000 2000 1000...

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