MINOR ACTINIDES TRANSMUTATION STUDIES AT CEA: SOME REACTOR PHYSICS ASPECTS. M. SALVATORES CEA/DRN/DER/SPRC CEN Cadarache, France

Transcription

1 MINOR ACTINIDES TRANSMUTATION STUDIES AT CEA: SOME REACTOR PHYSICS ASPECTS M. SALVATORES CEA/DRN/DER/SPRC CEN Cadarache, France 424

2 AN EXAMPLE SELF-RECYCLING IN A SUPERPHENIX-TYPE REACTOR (IN AN HOMOGENEOUS MODE): INITIAL REACTOR LOADING FROM STANDARD-PWR PU (AT 33GWd/t), INCLUDING MINAC; s SUCCESSIVE RECYCLING: - IRRADIATION CYCLE OF 960 DAYS AT NOMINAL POWER - COOLING TIME/AGEING: 1 YEAR - NO LOSSES AT REPROCESSING THE EQUILIBRIUM IS OBTAINED AFTER -12 CYCLES (THE INITIAL PU LOADING IS EQUIVALENT TO WHAT WOULD COME OUT FROM THE OPERATION OF A STANDARD PWR DURING 30 YEARS). 425

3 u) *- al L1 d H o N*.. 426

4 BASIC DATA INTEGRAL EXPERIMENTS CORE AND FUEL CYCLE STUDIES 427

5 BASIC DATA I 1- THE J13F-2 DATA BASE IS AVNLABLE (February 1990) MINAC NEUTRON DATA MOSTLY FROM JEF VALIDATION : CADARACHE SATISFACTORY RESULTS 3- NEW AND WIDER BENCHMARKING UNDERWAY 4- DATA/VALIDATION (PARTLY) MISSING UP-TO-NOW : - RESONANCE SELF-SHIELDING - DELAYED NEUTRON DATA - DECAY HEAT RELATED DATA - COVARIANCES - PHOTON PRODUCTION DATA 428

6 II INTEGRAL EXPERIMENTS AT CEA II IRRADIATED FUEL EXPERIMENTS : ==== ==== ==== ==== ==== ===,) FBR SPECTRA (PHENIX) :. SEPARATE ISOTOPE SAMPLES IRRADIATION (PROFIL-IAND PROFIL-11) - SPECIAL FUEL PINS IRRADIATION (TRAPU). ACTINIDE PINS IRRADIATION (SUPERFACT) b) LWR SPECTRA (MELUSINE). SHERWOOD (5 x 5 SQUARE LA ITICE WITH STANDARD 17 X 17 PWR FUEL) CENTRAL PIN WITH U0 2 PELLETS, DOPED WITH MINAC. ANALYSIS OF IRRADIATED FUEL IN STANDARD p~s (WITH VARYING BURN-UP), AND IN PWR WITH MOX RECYCLING 429

7 Scheme of a ~ I Samples Core J mid-plane Maximum of flux Fig.2 PROFIL pin irradiation in PHENIX Position (mm) E t= 150 k ljq > 70 L_Q Chfzmical II Isotope form Mass (mq) U235 u 0$4 22 Nd145 Nda O.a 22 WI05 Pd 21,7 CS133 Cs F 23,4 RulOl Ru 19,6 M095 MO 21,5 PU238 Pu M097 Mo 21,7 _Pu 239 Pu o% 1%1 o u 25 u Oq ~5 Am241 AmQ 10,0 U238 u Oc 2Z3 PU240 Pu Ot 3,7 Li nat. Li F 3,8 Pu 242 PU02 29 B nal. B If 5mU9 Sml 05 25,8 Pu 241 Pu Oe 4/ l=50 10 l== 0 u 235 u Oa 24,1-10 Pu 239 ko~ J-VI o - 20 B nat. B 1,0 I -30 [PU2401RJOZI 6 I la ml Phtonium an Am6ricium References d km&m I -110 I Pu240 j PUOZ I 6,3 I 12z4 Uranium Standard 3 PHENIX clad -150 Pd 105 Pd Pu 241 Pu O* l~s -?70 B naf. B 1,3-180 U 235 u 02 24,5-190 LI nat. IJF 4,2-200 Ru WI Ru p~ 242 fi (3= 25,-220 Nd 145 Nd203 20,2 I -230 j Pu 2381 l% Oz 12,6 J -240 k 97 MO I 19, Am 241 ) 1 J m TI:U3. ~~.~,- I lj [J I 430 L 1 4 > Q1 Fission produ Cts

8 TABLE V C/E values with JEF-1 data on 237 ND. reaction rme~. obtained from 237 Np sample analysis fter ;rr~di~tion h ths PHENIX core.! C/E! J ~ 237 I Np 1 o.90~o.05! c! 237 o Np! 1.19 ~ Ools(a) : n,2n 1 I (8) This results is ssociated to spcclfic branching ratio of the 236 Np (lotlg lived) 237 reaction Np > conaistant with CARDNER nd, CARDNER valuation. n,2u 236NP (short lived)

9 (n,2n) 237 NP (yln) 6- Co. < 236W a 1 = 2.85 y z 49 t 51 t 236 U c 1 DECAY SCHEME RELATED ~ 237 Np(II,21t) and (Ytn)

10 TABLE I ISOTOPIC COtiPOSITION OF TNE THREE TRAPU FUEL PINS Experiment % Pu isotope composition 2J8PU 1)9 i% PU abl Pu 2 2PU TRAPU TRAPU TRAPU TABLE II SEPARATE ISOTOPES IRRADIATION IN PROFIL EXPERIHENI S Experiment Th u Np Pu Am cm S 239 PROF I ~ PRoFIIr S

11 TABLE 3 C/E VALUES FOR T1[E PROFIL EXPERItlENTS USING JEF-1 DATA C/E WITH JEF-1 DATA TYPE (A) AVERAGE VALUE (PROFIL-l+PROFIL-2 ) a a o 0=( u ) u= ( 23 U ) a= ( 2y7Np) ( 2J7Np) CJc[ 2Y PU) a.( 2J PU) n,zn ( 239pu) n,zn ac( 2 PU) ( 2b Pu) & lpu) a= ( 2b2Pu) a=( Z Am) ~c ( 2byAm) atot( OB ) 0.97 * 1.4% 0.96 t 1.6% 0.90 t 4.1% 1.19t 15% 0.95 i 3 % 0.97 k 1.8% 1.38 k 11% 1.06 f 1.6% 0.83 k 14 % 1.11 t 3.7% 1.16 ~ 3.5% 1,03 k 1.4% 0.94 k 5 % (A) All the results are average reaction related to the 2JSU fission rate. rate ratios ( spectral indices ) 434

12 TABLE IV C/E VALUES ON FINAL (END OF IRRADIATION) COMPOSITIONS IN THE TRAPU EXPERIMENTS (PERCE~AGE VALUES) USING JEF-1 DATA 23~u=lo(j TRAPU-1 TIWW2 TRAPU u 21s u 23t u 2 ] 7NP 2 PU 2Jlpu 24 PU 2b1Pu abl~ 2*1 Am 2b3 Am 251 Am 2*2C8 2b3cm Z**cm 0.98 i 2.5% 0.99 *0.3X 0.98 t 0.5% 0.91 t * OO i 0.4% 0.99 k t 0.4% 1.08 i.o.sx 0.95 * i ~.6!C 1.08 f 3.6% 0.96 t t 2.02 I.oof 1.3% 1.01 * 0.2% 1.00 t 0.4% 0.90 * 3.3% 1.00* 0.4% 0.98 i 0.3% 0.98 f 0,3% 1.00 i 0.3% 1.03 * i 3,6X 1.41 t 4.0% 1.05 i 4.0% 0.95 * f 2.7% 1.15 * 2.2% 1.04 * 1.0% 1.01 t 0.2% 0.99 * 0.3% 0.85 k 3.2X 0.99 * 0.4% 0.98 * 0.3% 0.98 t 0.3% 1.02 to.3% 1.01 * 0.3% 0.97 i t 2.5X 1.08 t 2.5% 0.94 * 2.1% 1.13 t 2.6% 1.16 t 1.7% 435

13 SUPWACT 1 CAPSULE EXPERIMENTALE PHENIX REPARmlO#J DES AIGUIUES / VUE de DESSUS aiguiile

14 Reaction Rate Experimental value normalized tb the 23% fission reaction rate 23% fiso~ti~ ~ % Capture t 0.CX)3 23N Capture t o.m14 239PU capture 240 Pu Capture 1;s08 * (X3 ~ Pu Capture Y Pu Capture t Am capture 3.18s t Am Capture t CIII Capture z

15 / * enrlchlssement Initial REP standard I 2.I% 2.6%et 3.1% PWR T5w+ \ Dmaine de taux d Combust ion ===> 33 wj/t GQbt..t hauts taux de commst Ion Enr Jchlsserrmt f ttal &lev&/ I I 3.1% 4.5% ===> 58 GWj/t => 45 Guj/t / I \ PLAGES D ENRICHISSEMENT INITIAL ET DE TAUX DE COMBUSTION ET UDIES 438

16 C) HCLWR SPECTRA (MELUSINE). ICARE EXPERIMENTS: TWO EXPERIMENTAL PINS WITH U0 2 PELLETS, DOPED WITH MINAC, AT THE CENTER OF 261 PIN LAITICE OF MOX FUEL (8,5% ENRICHMENT). TWO VALUES OF THE Vm/Vf RATIO HAVE BEEN STUDIED : Vv nh = 0.5 and 0.9 (THESE EXPERIMENTS ARE CONSISTENT WITH THE CRITICAL EXPERIMENT PROGRAM ERASME, PERFORMED ln THE CRITICAL FACILITY EOLE AT CADARACHE) 439

17 i I i, I, Crayon exp&imentaux Crayons PU~ Assemblage DE SECTION CARREE 450x 450 mm 2 OCCUPANT IA PIACE DE 4 EtEME~ MEUJSINE FIGURE 6 440

18 I_RRADi AT ION ICARE DAM m.-. i!eiisine ---- I.., I m Puissance MELUSINE 8 MWTh Puissance 1 WMque I CARE -45 iu/cti Taux de cgmbust ion ICARE s 270 MWJ/t par mof: 441

19 CRITICAL EXPERIMENTS ==== ==== ==== === FISSION CHA.MBER MEASUREMENTS OF : F (Np-237) F (Am-241) F (Am-243) F (Cm-244) F (Pu-238) AND OTHER pu ISOTOPES A VARIETY OF CRITICAL CONFIGURATIONS: FBR SPECTRA IN MASURCA LWR SPECTRA IN EOLE 442

20 CORE NEUTRONICS AND FUEL CYCLE STUDIES. STRATEGY STUDIES (COSI CODE) RADIOTOXICITY IN DIFFERENT SCENARIOS FBR CORE STUDIES FOR TRANSMUTATION (ALSO ADVANCED LWRS) a HOW FAST AN EQUILIBRIUM (Np, Am) IS REACHED. DESIGN PARAMETERS UNCERTAINTY STUDIES IN FBRs: - N 2 VOID COEFFICIENT - DOPPLER - Aq/CYCLE (IBG) WHAT ARE THE DESIGNS FOR AN OPTIMUM BURNING STRATEGY e.g. a OUT OF CORE POSITIONS IN AN LMFBR = IF HOMOGENEOUS RECYCLING, WHAT INTERNAL BREEDING GAIN (IBG) SHOULD BE ADOPTED 443