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I. [ / rt .2 GT-MHRADVISORY GROUP- OConstelation O Nt'ear 5fDominion- WHO,WHAT & WHY Pre-application NRC Meeting 12/03/01 Entergy NM7 ) Uf) I

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Page 1: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

I. [ /rt .2

GT-MHRADVISORY GROUP-OConstelationO Nt'ear

5fDominion-

WHO,WHAT & WHYPre-application NRC Meeting

12/03/01Entergy

NM7 )Uf)

I

Page 2: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 3: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

UAG STRUCTURE

I.

Page 4: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 5: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 6: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

"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

Page 7: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

Gas Turbine - Modular Helium ReactorSafety A pproach

.

- .Presented to NRC Staff3 December 2001

Laurence L ParmeManager, Reactor Safety & Licensing

General Atomics

. . . .

- : - . +GENERAIL ATOMICS

Page 8: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 9: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 10: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 11: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 12: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

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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

Page 14: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 15: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 16: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 17: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 18: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 19: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

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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

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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

Page 22: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 23: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 24: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 25: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

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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

Page 27: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 28: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 29: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 30: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 31: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 32: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

5 Areas Proposed forDiscussion

* Programmatic and Process Topics

* Licensing Approach

* Technology Development- Fuel- Graphite- Metals

* Design Description

* Accident Analyses

+ CENERAL ATOMICS

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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

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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

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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

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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

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Presentation Outline

* Design goals & requirements

* Design description

* International Program

* Commercial Program

* Design status and deployment schedule

* Conclusions

+ GENERAL ATOMICS

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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

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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

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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

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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

Page 42: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

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, - _ - I _ - -

GT-MHRCOMBINES

MEL TDO WN-PROOFADVANCEDREACTOR

WITHHIGH EFFICIENY

GAS TURBINE

POWER LEVEL600 MWt

+ GENERAL ATOMICS

Page 44: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

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

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

. .I I

M-273(27)8-27-01

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

Page 45: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

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

BROAD FOUNDATION OF HELIUM REACTOR TECHNOLOGY

+ GENERAL ATOMICS

Page 46: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 47: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

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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

Page 49: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

+ GENERAL ATOMICSL-266(2)7-28-94

F-

Page 50: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 51: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

+ GENERAL ATOMICSL-029(4)6-9-94

Page 52: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 53: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

GT-MHR FLOW SCHEMA TIC* 3

LOW PRESSURECOMPRESSOR

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

Page 54: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 55: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 56: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 57: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

+ GENERAL ATOMICSL-592(2)11-14-95

F.

Page 58: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 59: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 60: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 61: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 62: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

Page 63: Slide Presentation by General Atomic on Gas Turbine ... · UlW 0] I--z w a X5 u-4000 3000 2000 1000 4000 3000 LARGE I--nsv^SsHTGRs RADIONU CLID E ... I VESSEL RADIATION' * RCCS CONVECTION

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

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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