ML20064K430

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Affidavit of Aftergood Re Contention Viii.Facility Could Be Converted from Using Weapons Grade Fuel to Low Enriched U,While Retaining Same Educational & Research Capabilities & Increasing Safety
ML20064K430
Person / Time
Site: 05000142
Issue date: 01/12/1983
From: Aftergood S
COMMITTEE TO BRIDGE THE GAP
To:
Shared Package
ML20064K001 List:
References
NUDOCS 8301180397
Download: ML20064K430 (24)
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION HEFORE THE ATCMIC SAFETY AND LICESING BOARD A

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In the Matter of '

THE REGE!frS & THE UNIVERSITY Docket No. 50-142 g4 4 ,

& CALIFURNIA (Proposed Renewal of b

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Facility License) J (UCLA Research Reactor)

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,a DECIARATION CF STEVEN AFTERGOCD AS TO CONTENTICN XIII -

I, Stev9n Aftergood, do declare as follows:

1. I am an environmental researcher with the Committee to Eridge the Gap and a member of the Southern California Federation of Scientists (SCFS).

A statement of professional qualifications is attached to my declaration as to Contention I.

2. As part of an SCFS project examining methods of reducing Highly Enriched Uranium (HEU) inventories worldwide because of the significant proliferation risks associated with HEU use, I have researched the availability of low Enriched Uranium (LEU) replacement fuel for conversion of non-peuer reactors currently operating with fuel of weapons grade. This review has included a search of the technical literature associated with th6 RERTR pro 6 ram (Reduced Enrichment for Research and Test Reactors) as well as direct contacts i
with manufacturers of research reactor fuels and with operators of a research reactor that has been converted from IE to LEU fuel.
3. It is my conclusion that LEU fuels are currently available; that a reactor

! such as UCLA's would, after conversion, have essentially the sare educational and research capabilities as it does presently and that such conversion to LEU fuel could have very significant safety benefits, in addition to the l Very important contribution to the national (and NRC) policy of reducing wherever possible HTJ inventories for non-proliferation reasons.

8301180397 830112 PDR ADOCK 05000142 G ..< PDR I

4 One firm currently offering LEU fuel commercially is the General Atomic Company of San Diego. General Atomic currently has available 19 7 % enriched TRICA-type fuel, specifically designed for use in research reactors presently using MTR-type flat-plate HEU fuel of the kind used in the UCLA reactor.

TheGeneralAtomicpublication"TRIGA"(attachmentA)atpage11showsa .

photograph of the replacement TRIGA bundle alongside a standard flat-plate bundle. As indicated in the section on "Research Reactor Conversions":

A number of reactors originally built for plate-type fuel elements have been converted to use TRIGA fuel. In most instances, the converted reactors have retained their existing core grfd structure, control rod drives, and control console.

5 Attachments B (p. 5) and C list numerous research reactors originally utilizing plate-type fuel which have been successfully converted to TRIGA fuel. These include Penn State, Washington State, the University of Wisconsin, I Texas A & M, the University of Maryland, and a number of others.

6. To confirm that such conversions are possible and to ascertain wh, ether any problems have arisen, I contacted a Dr. Muno of the University of Maryland i
reactor staff. The attached item C indicates that the University of Maryland reactor was converted in 1974, which Dr. Muno confirmed. The reactor now runs at about 250 k"th, with a thermal neutron flux in the range of

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2 to 5 x 1012, (UCLA, in its application at p. III/6-5 reports its 12 thermal flux at 100 kw as about 1 5 x 10 njc,2_,,,),

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l 7. Dr. Muno indicated that conversion was undertaken in part because there was concern that after 11 years in water, the aluminum cladding on the original flat-plate fuel might be losing its integrity. LEU fuel was chosen because it was anticipated that the NRC would eventually require a high degree of l security for HEU and tht it was unlikely the reactor staff could convince the University to. fund guards and the like. TRIGA fuel was chosen for its inherent safety features, prirarily the prompt negative temperature coefficient which provides a far greater degree of protection against destructive pcwer l excursions than found with flat-plate fuel. It was reasoned that it would ba "a lot easier to license" a reactor that had the protection against destructive reactivity incidents afforded by the TRICA fuel.

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8. A completely new control console was installed at the time because the old one was a vacuum tube system, and tubes were not easily available.

In addition, it was hard to find technicians who had been trained on tubes.

Dr. Muno indicated that a slight drop in flux upon conversion to TRIGA fuel can be compensated for by a more efficient geometry, and that in any case, the current flux (2 to 5 x 1012) was more than adequate for the University's needs (mainly activation analysis). One researcher in materials science occasionally requires a flux of around 101 , so he sends his samples off to Argonne or Oak Ridge.

9 I confirmed with the TRIGA division of General Atomic the current commercial availability of TRIGA LEU fuel for plate-type reactors and that conversion to LEU TRIGA fuel involves no significant drop in neutron flux. I was informed that the average flux is comparable the shape of the flux, however, will vary, tending to peak in the reflector region.

Water-filled flux traps can increase the available flux: even without such flux traps, though, the reactor would still be able to perform the same functions as prior to conversion. Conversion rarely requires changes to the control rod or cooling systems, furthermore.

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10. General Atomic, I was assured by its marketing division, currently has commercially available LEU TRICA fuel for conversion of plate-type f

reactors and is " ready, willing, and able" to provide conversions as they come up. Furthermore, I was informed, General Atomic has competitors in the LEU field--NUKEM in Germany and CERCA in Francs currently having available LEU flat plate fuel for research reactors.

11. I conclude that LEU fuel is currently available for use in the UCLA l reactor.

I declare under penalty of perjury that the foregni s true a og et to the best of my knowledge and belief. /pg n Steverf Aftergood/ /

Executed at Los Angeles, California, this /#, aday of January, 1983 l

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j Pulsing to 22,000,000 kw Pulsing Extends Applications. The TRIGA reactor's controlled pulsing operation, made po:sible by its built-in safety, has opened up important new reactor applications.

This pulsing capability may be used to investigat a reactor l'inetics and transient testing of power reactor fuel, or to Reackx Penod: 168 MSEC i study the effects of extreme radiation environments on _ReacMy insate: $4 60 p.22% WQ j biological and electronic systems. Pulsing may also be used for the production of very short half-life isotopes, and in many other basic studies where high-intensity pu'ses of -

neutron and gamma rad 5 tion are required.

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used extensively to prove the pulsing capability of TRIGA fuel. This reactor has been pulsed safely to peak power levels wellin excess of 8,000,000 kw. More than 50,000 -

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pulses on all TRIGA reactors have demonstrated the /

j performance, safety and high reliability of TRIGA fuel. _

Y8 W Annular core pulsed reactors have been designed for routine pulsing to power levels of 22,000,000 kw.

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Inherent Safety. The TRIGA reactor's inherent safety is A combined total of more than 500 reactor years of safe l due primarily to a physical property cif its uranium-zirconium operation has been achieved by TRIGA reactors throughout hydride fuci elements, which gives the TRIGA core a large the world. The proven and inherent safety of TRIGA prompt negative temperature coefficient. Power rises initiated reactors permits installation in a conventional building and by the rapid insertion of large amounts of excess reactivity siting in urban areas such as university campuses, hospitals are automatically suppressed without extemal controls and or classrooms. Installation within a conventional building the reactor immediately returns to normal operating levels. without the need for a pressure type containment results in l By contrast, a delayed negative temperature coefficient found significant savings in facility construction costs and the l on conventional reactors provides safety only against potential for economical installation in an existing building.

! relatively smallinsertions of excess reactivity.

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1 Research Reactor Conversions S

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l A number of reactors originally built for plate-type fuel i i elements have been converted to use TRIGA fuel. In most C ' ' "

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, i In addition to increased safety and flexibility, the TRIGA :t conversion has provided a dual steady state / pulsing 7; l "

capability with steady state performance levels up to 2 MW, l

still with natural convection cooling of the core. The conversion to a complete TRIGA core can be a step-wise ,

je process whereby TRIGA 4-rod clusters cre added a few at a  !

time to an operating p' ate-type core. j c q , g'" g;

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ADVANTAGES OF TRIGA FUEL FOR RESEARCH REACTORS

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ADVANTAGES OF TRICA FUEL FOR RESEARCH REACTORS All TRIGA fuel is made by GA with a uranium enrichment of Just under 20% and thus is classified as Low Enrichment Uranium (LEU) fuel.

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l The following discussion of advantages applies to TRIGA fuel clusters which can be inserted in existing grid plates to convert plate-type fueled reactors, and some pin-type fueled reactors, to TRIGA. TRIGA's advantages have motivated the owners of eelve plate-type fueled reactors to convert to the use of TRIGA fuel.

TRIGA LEU fuel is available now for use in existing reactors operating at steady state power levels to 50 MW.

1. UNIQUE SAFETY All of GA's research and test reactors are fueled with UZrH. This unique fuel provides the highest degree of safety available in any type of nuclear reactor. In these days of increasing public concern with perceivea hazards of nuclear facilities, the::s safety advantages alone should Justify use of UZrH fuel.

A. The UZrH fuel has a prompt negative temperature coefficient of reactivity, vs. a delayed coefficient in aluminum-clad plate-type fuel. This allows UZrH cores to safely withstand accidental reactivity insertions that have completely destroyed plate-fueled cores.

B. UZrH is chemically stable. I t can be safely quenched at 1200*C in water, i while exothermic metal-water reactions take place with aluminum at 650*C.

C. High-temperature strength and ductility of TRIGA's incoloy-800 fuel cladding provide a yield strength greater than 10,000 psi at 900*C. The aluminum cladding on plate-type fuels melts at about 650*C.

1 D. The UZrH fuel material has very superior fission product retention. The aluminum-clad plate-type fuels melt at 650*C, releasing 100% of the

. volatile fission products. Whereas, at this same temperature UZrH retains about 99.9% of these fission products even wi th the cladding removed.

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E. New TRIGAs do not require expensive pressure-containment buildings because of these unique safety features.

2. ECONOMY A. Major operating cost savings result from the fact that UZrH fuei contains i

several times as much U-235 as plate fuels. GA sells its fuel at standard published fixed prices with standard terms and a commercial warranty.

Although the initial cost of UZrH fuel is usually higher than plate fuel, the total fuel cycle costs are lower for UZrH due to the much longer core life, and reduced shipping and reprocessing costs.

8. Individual fuel rods within a cluster can be easily replaced in case of damage (vs. replacement of entire plate-type element).

C. There are fewer reactor shutdowns (with corresponding savings in fuel handling costs and increased experiment time / continuity) because fewer core changes are required with TRIGA fuel.

D. Uranium costs are lower because TRIGA's uranium lasts as long as that in several plate-type cores, which must be purchased at prices that are continuing to escalate.

E. Less time and money is spent on Inter government problems to export / import I

fuel and the contained uranium since TRIGA fuel outlasts several plate-type cores. Thus the potential for unplanned reactor shutdowns due to slow or delayed fuel delivery is significantly reduced.

3 PULSING OPERATION A. Routine pulsing is not possible wi th plate-type fuel but is a normal mode of operation with most TRIGAs. Since 1958, TRIGA reactors have pulsed over 50,000 times.

B. Standard TRIGA fuel with 8.5 wt-% uranium is licensed for routine pulsing with reactivi ty insertions of 3.2% ok/k up to a peak power of about 6,400,000 kW. The prototype TRIGA at GA has been pulsed with reactivity 2

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Insertions of 3.5% 6k/k to a peak power of about 8,400,000 kW. Pulsing allows production of very short-lived isotopes, transient testing of materials, and other unique applications.

,- C. The TRIGA-ACPRs (Annular Core Pulse Reactors) at the Japan Atomic Energy Research Institute and the Institute for Nuclear Technologies in Romania

. are in operation and pulsing to %20,000,000 kW for safety testing of power reactor fuels.

4. LARGER EXPERIMENT REACTIVITIES AND MORE FLEXIBLE OPERATIONS A. Due to its larger prompt negative temperature coefficient, TRIGA can safely withstand larger accidental reactivity insertions which mean maxi-mum flexibility for student use, training and experiments.

B. TRIGAs are licensed for in-core experiments having a reactivity worth of up to 2.1% 6k/k for one experiment and a total of 2.8% 6k/k for several.

C. TRIGA is also less sensitive than plate-fueled reactors to reactivity changes in the reflector region. As a result, the TRIGA core can be moved from a position with a void on one side to a position which is completely reflected by water without removing fuel elements.

D. TRIGA's special square wave mode of very fast reactor startup (rise to normal steady state power levels in a few seconds) is available on all TRIGA pulsing reactors. This mode of operation, which is possible due to TRIGA's large prompt negative temperature coef ficient, means higher utilization, more "on-line" time and reproducibility of irradiation doses.

5. LICENSE PRECEDENTS Because of their inherent safety, TRIGA reactors are currently licensed for the following types of experiments:

A. In-core pneumatic transfer systems under both steady-state and pulsing modes of operation; 3

B. In-core experiments at cryogenic temperatures; C. In-core experiments at temperatures of up to 2000*C; J

D. In-core experiments at elevated temperatures in which samples of fissile material can be subjected to both steady-state and pulsing conditions; E. In-core experiments in whi ch explosives are . detonated.

6. PROVEN RELIABILITY A. Sixty-three TRIGA reactors have been or are being constructed throughout the world, and of these, 34 routinely operate in the pulsing mode.

B. TRIGA reactors have greater than 800 reactor years of safe operating experience and over 50,000 pulses.

7 FUEL GUARANTEE AND SUPPLY A. TRIGA LEU fuel is the only LEU fuel currently available in power levels to 50 MW s teady s ta te.

B. GA designs, develops , manufactures, and guarantees the TRIGA fuel .

C. GA stocks spare fuel for the immediate, unplanned needs of customers; TRIGA fuel may be purchased a few elements at a time as the need arises.

D. The continuing requirements of the many TRIGA reactors in operation give assurance of a continuing, reliable fuel and spare parts supply.

8. PREFERENCE OF TRIGA BY EXPERIENCED CUSTOMERS I

A. More TRIGA reactors are in operation than those of any other research reactor manufacturer.

B. TRIGA is still the most widely chosen research reactor; no type of research reactor other than TRIGA has been purchased commercially anywhere in i the world since 1968.

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C. The TRIGA system was chosen by the following experienced reactor groups for conversion of their plate-type research reactors to TRIGA fuel:

1) Pennsylvania State University
2) Washington State University

. 3) Universi ty of Wisconsin

4) Texas A&M Universi ty
5) USAEC at the Puerto Rico Nuclear Center
6) University of Maryland
7) Aerojet Corp., California
8) University of Frankfurt, Germany (water-boiled type)
9) Office of Atomic Energy for Peace, Thailand
10) Nuclear Research Center, Iran
11) National Tsing Hua University, Taiwan
12) Atomic Energy. Commission, Phil!ppines o
9. GENERAL ATOMIC CAPA81LITIES/ SERVICES A. Corporate ascott of GA's owners is over $50 billion.
8. GA is the world's largest and only remaining U.S. research reactor supplier.

C. GA designs and manufactures control rod drives and complete nuclear instrumentation and control systems for reactor facilities which also wish to update these components. GA's instrumentation and control systems use state-of-the-art, micro processor-based electronics making extensive use of integrated circuits; these systens are used in power reactors  ;

and therefore are designed to meet stringent safety requirements. l D. GA's competent staf f of nuclear physicists, engineers, seismic experts 1 and reactor designers has the most modern techniques and omnputational equipment to perform any safety or reactor analyses that may be required ,

l as part of a reactor conversion or its licensing. The current TRIGA staff, with 200 man years of TRIGA reactor engineering experience, is also available for consultation on any aspect of nuclear facility plan-ning, engineering or operation.

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l E. G routinely conducts in-depth training and technology transfer programs for TRIGA customers. The two TRIGA reactors owned and operated by GA at its San Diego laboratories are utilized to provide " hands on" operational experience to supplement the lectures and honework assignments. At the ,

conclusion of the course, U.S. students take ths U.S. Nuclear Regulatory Comission Senior Reactor Operators IIcense examination; foreign students take a similar exam administered by the GA staff.

F. TRIGA owners in the U.S. and in Europe hold bi-annual TRIGA Owners Con-ferences where experimental work, innovative ideas, reactor modif! cations and comon problems associated with the nuclear community are discussed and, where appropriate, united actions taken. The proceedings of these meetings are published and distributed to all TRIGA owners.

G. GA's TRIGA Reactor Division is dedicated to the continuing improvement and reliability of TRIGA reactors.

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INSTALLATIONS AND CONVERSIONS -

. - ERAL ATN G8410 Pet 1900 INi11Al, LOCATX)N TYPG STGADY STATS PULSeNG CletTICAUTV Artsone 1 UrWeereoty of Artsons TNGA .*4ert i 200 kW 3lNL000 kW 12748 hacean Castfornaa 2 Generei Atomeo TNGA Mart i 2Ofr kW ann nna kW SSee San Dego .

3 General Atomic TNGA Mert F 1,300 kW 8,400,000 kW F240 Sen Diese 4 General Atomic TNGA 14ert IN DecaneNeesened 11748 San Dego 5 Norear Deweton of Northrop Cm TNGA Mert P 1.000 kW 1,000,000 kW &&43 Howthorne

$ Un#vereoty of Caesfornie T7100A Mort IN 1,000 kW 2,120.120 kW S16et Sette*ey F University of Casatom6e TNGA Idart 1 200 kW 280,000 kW 11-2540 levene 8 Operettone TFhGA Convereton 290 kW F448 Co.o,s . us Geo ece, S.,ve, TalGA - 1,00 kW 1.8.,00 kW uS40 oenver Idano 10 Argonne Net 1, Lees WestiHPSP,INEL) 77tf(.A Convereien 250 kW 1412-TF Ideno Faite latencAs 11 Unweresty of beinose TNGA heart N 1300 kW e are nnn kW StS40 Urtene Menees 12 Kenees State University TNGA Mart N age kW 200,000 kW 141642 Mannetten Maryland ti Harry Diemong Ledaorecortes $18. Army) T7tIGA Mars P Decommisesened 518.sti Forest Glen 14 Nucteer Agency (APftMfl THlGA Mart P 1,M kW 9 nnn nnn kW $342 Setneeds 16 Un#versity of Maryland TNGA Comeralen 200 ktRr 41SF4 Costage Park -

( MacNgan 18 The Dow Chemecal Company Midtend TNGA Mart I~~ 100 kW F447

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17 MecNgen State Un#veresty TNGA hiert 1 200 kW 2BILC00 kW S2148 East Leneeng Nebroene 18 Werene Aalmen6etretton Heepetal TNGA MMt i 18 kW 62800 l

l New Monsoo 19 Sendte Corporation $JSASC) N 000 kW 11ran nnn kW S24F Albuquentue New mrt ur CoeurnMe Un.ve,.y TNGA Me,t N 2 0 kW 2 0,000 kW ucensed New mrt 21 Corno64 Unhwesty TNGA Mort N 100 kW sen nna kW 11242 Ithese Oregoa 22 Oregon State Univoresty TNGA Mest M 1,000 kW t sna nnn kW 344F Corweiste 23 Head Coelege TNGA Mert 1 200 kW F.240 Portland Penneytvense 24 Pennoyevenee Stele University TNGA leert IN Un#vwesty Park Convereton 1.000 kW 9 nnn nnn kW 124148 Puerto Rico 28 Puerto Rico Nuoleer Center TNGA Conversten Desammiestened 1-ISF2 May*0ues Tones 20 Teves A & M Unevereoty TNGA Conversion 1,000 kW 9 nnn nna kW 6140 College Station 27 Un#veresty of Temas TRIGA Inert i 250 kW sen nna kW p243 Austen l

Uien 2e Un Meyof uten TNGA Marn 1 2s0kw iS2>rs SantemeCar Wisconsen 2e uewverocy of Wiesoneen TmGA Coenrosen 1,000 kW , nnn nna kW t1.i44F Masson ,

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. _ . . . M h%ington State Universely TMcGA Conversten 1,(N2 kW 2JX2.012 kW F144F Pue6enen 31 . z ; _ - "anforts . 300 Aree Tm M Metal 290 kW S26FF 9teniend l

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P.O. BOX 81608, SAN DIEGO, CAUFORNIA 92138 (714) 455-4255 TWX: 910-3351260 l

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l TRIGA* REACTORS n.0 ,cn Tr.inins, and liedrspe Pmducti0n

.. RAT,,eG teetTIAL LOCAT10se TYet sTEACY STATE PVLee880 CRmCAUTY Ausene St meesmiMenesaryof Edussesen TNGA heark N MOkW 200,000 kW ST43 vimma Songsaaleen M Opasteues of Nuotear Teofuustasy. Deens TIWGA heerei N 32 kW g enn nnn kW Under emneteesen Construenten eresN 34 Minas Gesase TmGA Mert 1 -

agekW 11440 eng.end = .pn. ores. C s se,is.eusereas TNGA isert i =0kW . .,1 8Hangnene. Tunessee ensend at The sense sneescues for 1tennsees Rosessen TmGA Mert N M kw 2sa00c kW Saf48 Hessenns Genneny 3F Gennen Caneer fassessen Center TNGA Mort i 200 kW  ?!* 54 Hessesterg as Jemannes Queenberg u,e eremy TmGA neert N 100 kW 2e0A00 kW e4es nemens 30 Assemiestun for Radnesten Rosessen TmeA More tu t,000 kW 2,000,000 kW 62&F2 houneen 40 edentesiCeNegeof Hansoor TNGA Mark 1,~ 2M kW 141T3 Henever ,

41 Uneveruseyof Prenerfurt .

TmeA Conseroton 1.0W kW 1 6 kW Under Frenefurt A -. - Conservee6en Indonente et Meelemal Asemme Energy Agency TNGA heart N 1,000 kW 161044 sendung 43 Namenes Asense energy Ageney TmGA esert N 2s0 kW igre M gyemene tren 64 Nuoteer Reemapen Center TmeA Conseroton 5,000rto,000 kW unser Tenrere Consensateen Hefy 46 Meetened Comunnee 9er Deusener Snesgy TRIGA Mort N 1,000 kW Sleep Resne 40 Unessassey of Posee TRIGA Most N 285kW 200,000 11-1645 Pause Josen TNGkACPR 300 kW ssannnne SJSFS 4F g Atenes Energy messesem inasseues as neumans Casses of 1hennecesy TmGA edest N 100 kW 1-26e3 16*se as Russysunsverusey TmeA Mark N 100 kW 12441 Weesume deres SR Heessaaf Aesssee Enesgyinseleuse TNGA heart N 290 kW S1942 assus 51 Neessnes A8essee EnesgyInsassuse TNGA Idest 181 2,000 kW 2,000.000 kW 41672 Seoul Menevees S3 lun tenimel Acesnee fessaaren Centre TNGA Mark N 1,000 kW 1snennakW Unest pu-a a - Ceneerusteen temstee $3 Nestenal Casunlessen 9er Nunemer Enesgy TNGA More lu 1,000 kW s nna nna kW 194m Menese CIry henseems 54 unsiesened v uneseremy TmGA seart I 100 kW unoer Reese Conserveteen lessnante 98 lasueuse for Nueemer lleannetagene TNGA.ACPR SCO kW 15,000,000 kW 12179 ausnerose SS Inseisuse for Nuoteer Teennetegies TNGA 14,000 kW 111679 Suonarese Tennen - SF Nestenet fleing Hun Uneserefey TNGA Case oreton 1,000 kW St-TF Teepes Theatend SS ONees of Aeosnee Ensegy for Pomme TRIGA Mest III Consorseen 2,000 kW s nnn nna kW 11.F.77 Benghet furney Se Teennenes uneserusty of lesensul TRIGA edert N 200 kW sen nnn kW S117T estensus Vlas Nase m enesseues of Numiser Roemeren TNGA Mark N Doesnuseestened 2-2643 Osses wagessess e et Jeest sessen pous sear sneenute TRIGA neert H 290 kyv S.140 LJWOlano Zeere et Hussear Selenee Comuneeseen TmeA neest N 1,000 kW i nna nna kW S27 SS (Congst Kinaneos,2etre l

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1. INTRODUCTION Nuclear research reactor facility capabilities must be expanded peri-odically to accommodate increased and more specialized experimental require-ments or face the alternatives of replacement or obsolesence. The most obvious route to augmented capability is to increase flux levels through greater reactor power or to make provision for special reactor performance, such as pulsing operation.

Administrators of many reactor facilities are also interested in 2 increasing the reliability of their systems because they recognize that fuel, electronics, and control systems decrease in reliability with age. 7' In addition, spare parts for older equipment are usually difficult to obtain because most of the original equipment suppliers are no longer in the re-search reactor busihass. These questions of reliability and availability and the awareness that an existing installation may not be adequate for more advanced experiments, such as for power reactor technology, lead a research facility staff to consider facility modification.

Section 2 presents some Laportant considerations to be evaluated before an alteration project is begun and explains how the TRIGA system can accom-

  • plish them. Section 3 discusses the specific approaches and engineering aspects of some completed reactor conversions. This paper provides informa-tion to assist a research reactor staff in solving the dilemma of expanding facility needs with limited finances and personnel.

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2. SPECIFIC CONSIDERATIONS FOR UPGRADING AND CONVERSION .

The upgrading of research reactors will be discussed in terms of provid-ing higher power levels, with corresponding higher fluxes, and providing for pulsing. One of the best approaches to fulfilling both of these requirements is to install TRIGA fuel. TRIGA fuel can operate in the natural convection mode at power levels up to 2.0 W (with forced convection the standard fuel can operate up to 3.0 W) and is uniquely designed for pulsing due to the prompt negative temperature coefficient of reactivity. Because of these factors, the characteristics of the TRIGA fuel are presentrsd briefly in the I following s'ection, followed by the considerations that are associated with upgrading and conversion of research reactors and the unique ability of TRIGA fuel to sa'tisfy upgrading / conversion requirements. ,

2.1. CHARACTERISTICS OF TRIGA TRIGA fuel is a second generation fuel system incorporating the latest advances in UZrH fuel technology. TRIGA fuel clusters are designed to replace MTR plate-type fuel and provide the many advantages of the TRIGA system.

Figure 1 shows the TRIGA 4-rod fuel cluster and standard MTR plate-type fuel.

i 2. l'. l . TRIGA Fuels .

Standard TRIGA and the TRIGA FLIP fuels are two basic versions of The standard fuel research reactor fuels available for reactor conversion. b, contains 8.5 to 12.0 we % uranium enriched to- 20% U-235 / and does not contain a burnable poison. This standard fuel is capable of routine high pulsing TRIGA FLIP fuel i operation and steady state operation at powers up to 2 W.

l (FLIP is the acronym for Fuel Life Improvement Program) is enriched to 70%

l in U-235, contains the burnable poison erbium-167, and provides an operating core lifetime of 10 to 20 W-years. TRIGA FLIP fuel is recommended for reactors with significant duty cycles of operation at 1 W or greater.

2

i The adjustable transient control rod on TRIGA pulsing reactors is 4

actuated by an electro-pneumatic system controlled from the reactor con-sole. The drive system permits the transient control rod to be used in the ste,ady state mode or the pulse mode of operation. In the pulse mode, the drive. system is adjustable so that any size pulse may be fired, up to the maximum reactivity worth of the control rod.

With a TRIGA pulsing reactor, an optional piece of control instrumen-tation can be provided to permit square-wave operation. In this mode, the reactor is pulsed to the desired preset steady state power level in a few seconds and automatically maintained at this level by a high speed servo drive. This unique mode of steady state operation provides a high degree of reproducibility in reactor startups and assures a reproducible integrated

  • flux to. test specimens in successive irradiations.

. 2.3. SAFETY

~ .

Increasing concern about the environment and the safety of nuclear reactors compel those planning any reactor upgrading program to strive for a reactor that is inherently safe, i.e. , not relying on engineered safe-guards systems. A safer reactor obviously increases operational flexibility and providee greater staff and community confidence.

I f TRIGA fuel has demonstrated the greatest inherent safety of any research g

reactor fuel in the world. These features are discussed in the following s

paragraphs.

l 2.3.1. Prompt Negative Temperature Coefficient TRIGA UZrH fuel has intrinsic properties that will prevent a nuclear accident in the event of human error or mechanical malfunction. Other

  • research reactors depend partially or entirely on electronic circuitry, moving parts, and the delayed negative temperature coef ficient of the fuel to counteract any large positive reactivity insertion. This type of de-layed shutdown mechanism depends on the transfer of heat from fuel material 13

to the water, responding somewhat slowly to any sudden increase in power level. This, if the reactivity addition is large, the power level can rise to a point that vaporizes the water moderator, resulting in dangerously _

high fuel temperatures.

'T On the other hand, TRICA fuel has a large, prompt negative temperature 4 coefficient of reactivity that effectively controls large prompt positive reactivity insertions. Any sudden increase in power heats both the fuel and the moderator simultaneously, causing the moderator to become less effective immediately and to return the reactor automatically and instan-taneously to normal operating levels. Such control is intrinsic to the TRIGA reactor fuel and does not rely on mechanical or electrical control devices. This most Laportant property is due to the fact that the fuel elements are constructed of a solid homogenous alloy of uranium fuel and .

zirconium hydride moderator, making them " fuel-moderator elements."

For the standard stainless steel alad

, 2.2.1.'l. Standard TRIGA Fuel.

UZrH fuel in a water-reflected core, the temperature coefficient is about 1.6

-1.26 x 10 6k/k per 'C. There are several factors contributing to this prompt coefficient. Their relative magnitude is noted below:

Approx Contribution (%)

l l 1. Cell ef fect--increased disadvantage factor with increased fuel temperature leading to a decrease

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in neutron economy 60 l

2. Irregularities in the fuel lattice due to control

~

positions--essentially same effect as item 1 above 10 i

l 3. Doppler broadening of U-238 resonances--increased resonance capture with increased fuel temperature 15

4. Leakage--increased loss of thermal neutrons from the core when the fuel is heated 15 14 l---- . - - - - . . . _ . . _ _ _ _ _ . , ._ _ . _ . _ _ ___ _ _ _ _ _ __

_. _- ._1. . _ _ . _ . = - - - . . . _x_

l IAEA-TECDOC 233 Agggg g RESEARCH EACTOR CORECONVERSION FROM THE USE OF IBGKY EluuCHEB URANRIN TO TIE ISE OF L85 EllRICIED URANIIM FUELS GBlDEM0K PREPARED BY A CONSULTANTS

  • GROUP,

' COORDINATED AND EDITED BY THE PHYSICSSECTION INTERNATIONAL ATObelC ENERGY AGENCY l

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1 A TECHfGCAL DOCURRENT ISSUED BY THE

> INTERNATIONAL ATOestC ENENGY AGENCY, VIENNA,1980 I

I

B-2 INTRODUCTION General Atomic Company has developed shrouded 4-rod and 16-rod clusters utilizing the TRIGA low-enriched uranium tirconium hydride .(UZrH) fuel for -

use in converting and upgrading existing MTR plate-type reactors and also for

' fueling new TRIGA reactors. The use of low-enriched uranium is in keeping wi th non-proli feration policies and is readily exportable. The 4-rod cluster is designed to operate at power levels up to 3 MW and the 16-rod cluster is

, designed for power levels up to 10 MW in existing reactor core structures.

i Both types of clusters use fuel-moderator rods which contain the well proven UZrH fuel in an incoloy cladding. The rod diameter in the 4-rod cluster

'I (3 24 cm) is only slightly smaller than that used in standard TRIGA fuel for

. more than 20 years. The 16-rod cluster uses a rod of 1.295 cm diameter and is identical in design to the fuel rods used in the 14 MW TRIGA now i n operation at tne Romanian Institute for Nuclear Technology. The fuel alloy used in the 4-rod cluster contains 20 wt-% uranium and in the 16-rod cluster 45 wt-%

uranium. This provides a very high U-235 content with low enrichment, i.e.,

440 grams U-235 in the 4-rod cluster and 880 grams U-235 in the 16-rod cluster.

A small amount of erbium is included as a burnable poison and is a major contrioutor to the prompt negative temperature coefficient', the dominant safety feature of the TRIGA fuel.

~

The high ' uranium loading combined with the burnable poison result in a very long burnup lifetime and favorable fuel cycle economics.

This Appendix is divided into two parts: 8.1, which der ribes a 2 MW reactor using the 4-rod cluster and B.2, which describes a 10 MO reactor using the 16-rod cluster.

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r" Contention XIV RESPONSE TO NRC STAFF ASSERTED MATERIAL FACTS

1. DISFUTED (Plotkin as to XIV,18-13)
2. NM DISFUTED 3 DISPUTED (Norton,261-68 Kaku, 180-81) 4 DISPUTED (PlotkinastoXIV,211;Pulido,232) 5 DISPUTED (Pulido,.P32)
6. LISPUTED(Pulido,232)
7. DISPUTED (Norton, 257-8,60-68)
8. DISFUTED(Norton, 257-8,60-68)
9. DISPUTED (Dupont,226-27)
10. NM DISPUTED
11. NOT DISPUTED
12. DISPUTED (Kaku, Dupont, Warf, Norton full declarations: Plotkin on XIV, 213)

RESTONSE 'It) UCIA ASSERTED FACT ,

18. DISPUTED (Kaku,Dupont,Warf,Norton,PlotkinonXIVfulldeclarations)

.

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