PROCEEDINGS OF A SYMPO - IAEA Nuclear Data Services

More documents

Recommendations

Info

32 THOM and SCHNEIDER accuracy is as important as that of the nuclear calculations. Theoretical approximations have been performed [24] and the results incorporated in current plasma-core reactor analysis. <strong>Data</strong> required for improved composition calculations are electronic partition functions and the ionization energies for the uranium atom and its ions. The partition functions are not yet known to a desirable degree of precision. Ionization energies are theoretically predicted but not yet verified by experiment. For precisely predicting the radiant heat transfer, depending on the plasma composition, transition probabilities and atomic energy levels of the uranium atom and its ions have to be known as well as the optical absorption and emission coefficients of the uranium plasma. A weak reactivity feedback exists depending on these quantities, which in turn can alter the power and subsequently the plasma temperature that governs its composition. Some measurements of emission and absorption coefficients exist [15]. Also transition probabilities for U I and U II are known [25]. However, the transition probabilities for U III and U IV are not known. U III and U IV will be major species in the reactor core. At a fuel temperature of the order of 40000°K (or about 4 eV), the neutrons see high target velocities; the result is reduced average fission cross sections. This fuel temperature effect does not appear to be critical (owing to the large mass of the uranium nucleus); however, it is not negligible. An increase of the critical mass by less than 5% is typical. Possible bulk motion of the fuel would result in similar effects. More important is the upscattering of thermal neutrons by the hot hydrogen propellant [26, 27] which in plasma-core reactor schemes is placed between the fuel and the moderator. The reflected and moderated neutrons have to pass through this high-temperature hydrogen region before they can reenter the fuel region. Upscatter of neutron energy results in a substantial penalty for the critical mass requirement. This effect can become so severe that for a given temperature a maximum operating pressure and hydrogen layer thickness exist beyond which criticality cannot be achieved. Because of the strong negative reactivity feedback of the propellant flow, a sudden interruption of this flow can result in a severe reactor power excursion. In the coaxial flow concept hydrogen migrates into the fuel region by diffusion and eventually will establish and maintain a certain hydrogen partial pressure in the fuel region. The temperature of the hydrogen 1n the fuel region will be equal to the fuel temperature. Fig. 12 shows the consequences for the 500-atm case assuming a mixing ratio of 1:1. At 40000°K, about 68% of the particles would be electrons, 15% would be protons, 10% would be U IV, 4% U III, and 4% U V. Because of the high temperature of the hydrogen ('4 eV) a substantial hardening of the neutron spectrum would occur, with a larger penalty for critical mass requirement than due to the hardening caused by the hydrogen in the working fluid. Competing with this effect is the moderation of fission neutrons by this hydrogen component. In order to compute all these effects properly, a better knowledge of the still unresolved resonances would be helpful. Also computation models for scattering kernels for hydrogen up to 40000°K are required. Doppler coefficients for similar temperatures are also required. New codes for criticality calculations involving the effects of fuel mixing ought to be developed.
IA E A -S M -170/5 3 33 Temperature, °K F IG . 1 2 . C o m p o s itio n o f h y d r o g e n -u r a n iu m p la sm a at pressure o f 5 00 a tm o s p h e r e s. M ix in g r a tio = 1 :1 [ 3 2 ] . In contrast to conditions in solid-core reactors, the fuel in plasma core reactors has such a short residence time in the core that a portion of the delayed neutrons do not contribute to criticality. According to [28] there are more delayed neutrons in the low-energy region than previously assumed. These are competing effects whose relative contributions to criticality computations require more attention. Special analysis of the delayed neutron spectrum appears to be in order.
Page 1: PROCEEDINGS OF A SYMPO ■ i INTERN
Page 6 and 7: The follow in g States are M em ber
Page 8 and 9: N U C L E A R D A T A IN S C IE N C
Page 10 and 11: A cce le ra to r and Space Shieldin
Page 12 and 13: C r o s s -s e ctio n uncertainty e
Page 14 and 15: Evaluation of the ranges of fission
Page 17 and 18: CRITERIA OF CHOICE FOR COMPILATIONS
Page 19 and 20: SYMPOSIUM KEYNOTE 5 INTERNAL CRITER
Page 21 and 22: SYMPOSIUM KEYNOTE 7 are them selves
Page 23 and 24: SYMPOSIUM KEYNOTE 9 new techniques
Page 25: SYMPOSIUM KEYNOTE 1 1 [ 4 ] I n te
Page 28 and 29: C hairm an KOLSTAD (USA)
Page 30 and 31: 16 THOM and SCHNEIDER A frequently
Page 32 and 33: 18 TH OM and SCHNEIDER Three requir
Page 34 and 35: 2 0 TH OM and SCHNEIDER POTENTIAL A
Page 36 and 37: 2 2 THOM and SCHNEIDER 4 -ST flG E
Page 38 and 39: 24 THOM and SCHNEIDER the short wav
Page 40 and 41: 26 THOM and SCHNEIDER Three critica
Page 42 and 43: 28 THOM and SCHNEIDER TO EFFLUENT C
Page 44 and 45: 30 THOM and SCHNEIDER Small Light B
Page 48 and 49: 34 THOM and SCHNEIDER The radial di
Page 50 and 51: 36 THOM and SCHNEIDER [4] RAGSDALE,
Page 52 and 53: 38 THOM and SCHNEIDER energy losses
Page 54 and 55: 40 WOLKENHAUER and LEONARD 1. Histo
Page 56 and 57: 42 WOLKENHAUER and LEONARD \ NEUTR
Page 58 and 59: 44 WOLKENHAUER and LEONARD • POWE
Page 60 and 61: 46 WOLKENHAUER and LEONARD 4.2 The
Page 62 and 63: WOLKENHAUER and LEONARD F I G .7 .
Page 64 and 65: 50 WOLKENHAUER and LEONARD [13] SKE
Page 66 and 67: 52 STUBBINS and WOLFE and f u n c t
Page 68 and 69: 5 4 STUBBINS and WOLFE T A B L E I.
Page 70 and 71: 56 STÜBBINS and WOLFE T A B L E II
Page 72 and 73: ( TABLE III. 3-GROUP CROSS-SECTIONA
Page 74 and 75: TABLE IV. CRITICALITY REQUIREMENTS
Page 76 and 77: 62 STUBBINS and WOLFE A. E f f e c
Page 78 and 79: 64 STUBBINS and WOLFE T A B L E V .
Page 80 and 81: 6 6 STUBBINS and WOLFE average time
Page 82 and 83: 6 8 STUBBINS and WOLFE The economic
Page 85 and 86: I A E A - S M -1 7 0 /5 8 A STUDY O
Page 87 and 88: I A E A - S M -1 7 0 /5 8 73 T A B
Page 89 and 90: I A E A - S M -17 0 /5 8 75 T A B L
Page 91 and 92: I A E A - S M -1 7 0 /5 8 T A B L E
Page 97 and 98:
10 г- T3 - i ï 10 S _l -г < 10 1
Page 99 and 100:
О) I - o I A E A - S M -1 7 0 /5 8
Page 101 and 102:
I A E A - S M -1 7 0 /5 8 8 7 The r
Page 103 and 104:
SECTIONS EFFICACES DE CREATION DE D
Page 105 and 106:
1 .1. Choc élastique I A E A -S M
Page 107 and 108:
IAE A - S M - 1 7 0 /6 5 93 L'éner
Page 109 and 110:
Section efficace de dommage Energie
Page 111 and 112:
Page 113 and 114:
Page 115 and 116:
Page 117 and 118:
Page 119 and 120:
CONCLUSION IAE A - S M - 17 0 /6 5
Page 121 and 122:
I A E A - S M -1 7 0 /6 5 107 TABLE
Page 123 and 124:
IA E A -SM -1 7 0 /6 5 109 TABLEAU
Page 125 and 126:
I A E A - S M -1 7 0 /6 5 111 TABLE
Page 127 and 128:
I A E A - S M -1 7 0 /6 5 И З TAB
Page 129 and 130:
IA E A -S M -n o/6 5 115 TABLEAU V
Page 131 and 132:
I A E A - S M -1 7 0 /6 5 117 TABLE
Page 133 and 134:
IA E A -S M -1 70/65 119 TABLEAU V
Page 135 and 136:
I A E A - S M -1 7 0 /6 5 121 TABLE
Page 137 and 138:
IAE A -SM -1 7 0 /6 5 123 TABLEAU I
Page 139 and 140:
IAE A - S M - 1 7 0 /6 5 125 REFERE
Page 141 and 142:
Section II REACTOR TECHNOLOGY
Page 143 and 144:
IAEA- SM-170/91 ТОЧНОСТЬ Я
Page 145 and 146:
IAEA SM-170/91 131 3) Для без
Page 147 and 148:
IAEA SM -170/91 133 важност
Page 149 and 150:
IAEA SM -170/ 91 135 ваемых
Page 151 and 152:
ТАБЛИЦА II . (продолж
Page 153 and 154:
П римечания к табли
Page 155 and 156:
IAEA-S M -170/91 141 ZPR-III-48 и
Page 157 and 158:
I A E A - S M -1 7 0 /6 9 ROLES RES
Page 159 and 160:
I A E A - S M - 1 7 0 /69 145 L a q
Page 161 and 162:
I A E A -S M - 1 7 0 /6 9 147 de la
Page 163 and 164:
I A E A - S M -1 7 0 /6 9 149 FIG.
Page 165 and 166:
I A E A -S M - 1 7 0 /6 9 T A B L E
Page 167 and 168:
3 .5 . A u tr e s d em an d es I A
Page 169 and 170:
CROSS-SECTION UNCERTAINTY EFFECTS O
Page 171 and 172:
I A E A 'S M - 1 7 0 /7 T h e c o d
Page 173 and 174:
1Л n» О О О 'í 16.375 REG. A
Page 175 and 176:
I A E A -S M - 1 7 0 /7 161 T A B L
Page 177 and 178:
EL USO DE PARAMETROS NEUTRONICOS DE
Page 179 and 180:
IAE A - S M - 1 7 0 /2 165 En un r
Page 181 and 182:
I A E A - S M -1 7 0 /2 1 6 7 E STI
Page 183 and 184:
I A E A - S M -1 7 0 /2 169 T A B L
Page 185 and 186:
I A E A - S M -1 7 0 /2 1 7 1 A d e
Page 187 and 188:
I A E A - S M -1 7 0 /2 173 P a r t
Page 189 and 190:
I A E A - S M -1 7 0 /1 8 ASSESSMEN
Page 191 and 192:
I A E A -S M -1 7 0 /1 8 177 routin
Page 193 and 194:
I A E A - S M -1 7 0 /1 8 179 TABLE
Page 195 and 196:
I A E A - S M -1 7 0 /1 8 181 and
Page 197 and 198:
I A E A - S M -1 7 0 /1 8 183 WIMS
Page 199 and 200:
IAEA-SM-170/18 185 For the discrepa
Page 201 and 202:
I A E A - S M -1 7 0 /1 8 187 exper
Page 203 and 204:
IAEA -S M -1 7 0 /6 7 UTILISATION D
Page 205 and 206:
1. 5. Nouvel intérêt des m esures
Page 207 and 208:
IA E A -SM -17 0 / 67 193 P ar aill
Page 209 and 210:
Section III SAFEGUARDS
Page 211 and 212:
THE ROLE OF NUCLEAR DATA IN NUCLEAR
Page 213 and 214:
IA E A -S M -1 70/7 8 199 I n s t e
Page 215 and 216:
IA E A -S M -1 70/78 201 s t a t e
Page 217 and 218:
IA E A -S M -1 70/78 203 s p e c t
Page 219 and 220:
TABLE V . DECAY ENERGY Q, H A L F-L
Page 221 and 222:
IA E A -S M -170/78 207 e . g . , o
Page 223 and 224:
IA E A -S M -1 70/7 8 209 TA B L E
Page 225 and 226:
IA E A -S M -1 70/7 8 211 T a b l e
Page 227 and 228:
IAEA-SM “ 17 0 /7 8 213 (1) E v e
Page 229 and 230:
IA E A -S M -1 70/78 l_ 36 / G O Z
Page 231 and 232:
IA E A -SM -П О /5 4 THE ROLE OF
Page 233 and 234:
IAEA-SM-170/54 The assay of a fuel
Page 235 and 236:
IA E A -S M -1 7 0 /5 4 221 FIG. 3.
Page 237 and 238:
IA E A -S M -17 0 /5 4 223 FIG. 6.
Page 239 and 240:
LAEA-SM-17 0/5 4 225 w hich time th
Page 241 and 242:
IAEA-SM-170/54 227 energies b elow
Page 243 and 244:
IAEA-SM-17 0/54 229 coincidence rat
Page 245:
IAEA-SM-17 0/54 231 [8] MENLOVE, H.
Page 248 and 249:
234 EDER and LAM M ER In a "forward
Page 250 and 251:
236 EDER and LAM M ER decay during
Page 252 and 253:
238 EDER and LAM M ER The ra tio o
Page 254 and 255:
240 EDER and LAM M ER Step 3: The n
Page 256 and 257:
242 EDER and LAM M ER FIG . 2 100 1
Page 258 and 259:
244 EDER and LAM M ER gamma ray mea
Page 260 and 261:
246 EDER and LAM M ER T A B L E I.
Page 262 and 263:
248 EDER and LAMMER TA B L E III. F
Page 264 and 265:
250 EDER and LAM M ER T A B L E III
Page 266 and 267:
252 EDER and LAMMER О . О 2 5 З
Page 268 and 269:
254 EDER and LAMMER T A B L E V . E
Page 270 and 271:
256 EDER and LAMMER T A B L E V (co
Page 272 and 273:
258 EDER and LAMMER T A B L E V I.
Page 274 and 275:
260 EDER and LAMMER I n a f o r w a
Page 276 and 277:
262 EDER and LAMMER 5 . 1 . 3 . D e
Page 278 and 279:
264 EDER and LAMMER 5.3. Examples o
Page 280 and 281:
266 EDER and LAMMER REFERENCES r d
Page 282 and 283:
268 EDER and LAMMER c a r r i e d o
Page 284 and 285:
270 BERENYI claims for radioactive
Page 286 and 287:
T A B L E I. H A L F -L IF E O F R
Page 288 and 289:
T A B L E II. Y IELD O F G A M M A
Page 290 and 291:
T A B L E lib . CONTIN U ATIO N Rad
Page 292 and 293:
T A B L E lid . CO N TIN U ATIO N R
Page 294 and 295:
280 BERÉNYI future: it would be ve
Page 296 and 297:
282 BERÉNYI [29] ARDISON, G. et MA
Page 299 and 300:
Section IV LIFE SCIENCES
Page 301 and 302:
LE ROLE DES DONNEES NUCLEAIRES DANS
Page 303 and 304:
IA E A -S M -1 70/97 289 FIG. 1. S
Page 305 and 306:
C IB L E Hg PARTICU LES iA E A -S M
Page 307 and 308:
IA E A -S M -1 7 0/9 7 293 ou syst
Page 309 and 310:
IAEA -SM -1 7 0 /9 7 295 Le princip
Page 311 and 312:
IA E A -S M -1 70/97 nous examinero
Page 313 and 314:
IA E A -S M -1 70/97 299 T A B L E
Page 315 and 316:
IA E A -S M -1 70/9 7 301 capture
Page 317 and 318:
lA E A -S M -1 7 0 /9 7 303 T A B L
Page 319 and 320:
IA E A -S M -17 0 /9 7 305 FIG. 10.
Page 321 and 322:
c o m p o s itio n du co r p s h u
Page 323 and 324:
IA E A -S M -17 0 /9 7 309 (3) BÈR
Page 325:
IA E A -S M -1 7 0/9 7 311 D I S C
Page 328 and 329:
314 DENNIS However, these aspects a
Page 330 and 331:
316 DENNIS D O S E ( K r a d s ) FI
Page 332 and 333:
318 DENNIS F IG .6. An illustration
Page 334 and 335:
TABLE I. SUMMARY OF I. C. R . P. RE
Page 336 and 337:
322 DENNIS F IG .9. Specific energy
Page 338 and 339:
324 DENNIS Similar details are requ
Page 340 and 341:
326 DENNIS C l J LAURIE, J., ORR, J
Page 343 and 344:
IAEA -SM-170/64 PROBLEMES POSES PAR
Page 345 and 346:
IAEA-SM-170/64 331 liè r e s , dan
Page 347 and 348:
IAEA-SM- П О /64 333 Le rendem en
Page 349 and 350:
NUCLEAR DATA AND NEUTRON ACTIVATION
Page 351 and 352:
IAEA-SM-170/3 T A B L E lia . A C T
Page 353 and 354:
IAEA-SM-170/3 339 At th is stage mo
Page 355 and 356:
T A B L E V b . IS O T O P IC SEN S
Page 357 and 358:
IAEA-SM-ИО/З 343 TABLE VI. ELEM
Page 359 and 360:
IAEA-SM-ПО/З 345 The follow ing
Page 361 and 362:
IAEA-SM- ПО/З 347 TABLE IX . DET
Page 363:
IAEA-SM-170/3 349 [10] SEELMANN-EGG
Page 366 and 367:
352 COHEN L es radioélém en ts de
Page 368 and 369:
354 COHEN TABLEAU II. CONSTANTES NU
Page 370 and 371:
356 COHEN On peut pen ser que les t
Page 373 and 374:
I A£ A-SM-170/92 APPLICATION OF NU
Page 375 and 376:
IAE A-SM-170/92 361 The p roblem s
Page 377 and 378:
4. 20N e(p ,tf)18F 5. 160 (a , 2n)1
Page 379 and 380:
T A B L E I. (continu ed) 13. Oak R
Page 381 and 382:
T A B L E II. SP E C IF IC A T IO N
Page 383 and 384:
IAEA-SM-170/92 369 Neutrons produce
Page 385 and 386:
8.3. A c c e le r a t o r p ro d u
Page 387:
IAEA-SM-170/92 373 R.В.R. PERSSON:
Page 390 and 391:
Chairman K.H. LIESER (Federal Repub
Page 392 and 393:
378 GÓRSKI Unfortunately, the labe
Page 394 and 395:
380 GÓRSKI several billions of yea
Page 397 and 398:
NUCLEAR DATA REQUIRED FOR THE INTER
Page 399 and 400:
IAEA-SM -170/28 385 dissipated by t
Page 401 and 402:
100 10 IAEA-SM -17 0/28 387 1 5 10
Page 403:
IAE A -S M -17 0/28 389 m ay not be
Page 406 and 407:
Chairman G. В. YANKOV (USSR)
Page 408 and 409:
394 CROUCH it was thought proper to
Page 410 and 411:
396 CROUCH its uncertainty; the cha
Page 412 and 413:
398 CROUCH It should also be mentio
Page 414 and 415:
400 CROUCH Table I I Ac Pile Neutro
Page 416 and 417:
402 CROUCH Table III (cont) Th then
Page 418 and 419:
404 CROUCH Table IV Pa Pile neutron
Page 420 and 421:
406 CROUCH Table V I 'Th Pile neutr
Page 422 and 423:
408 CROUCH Table V (cont) 'Th Pile
Page 424 and 425:
410 CROUCH 77 Ge As 347 347 Table V
Page 426 and 427:
412 CROUCH Table VII (cont) 233 U T
Page 428 and 429:
414 CROUCH Table VII (cont) U Therm
Page 430 and 431:
Page 432 and 433:
Page 434 and 435:
420 CROUCH Table VIII (cont) U Ther
Page 436 and 437:
422 CROUCH Table VIII (cont) U Ther
Page 438 and 439:
424 CROUCH Table VIII (cont) 235 U
Page 440 and 441:
426 CROUCH 1 2 Table VIII (cont) 23
Page 442 and 443:
428 CROUCH T a b l e V I I I ( c o
Page 444 and 445:
1 83 89 91 97 99 103 105 106 109 11
Page 446 and 447:
432 CROUCH Table X 239 Pu Thennal n
Page 448 and 449:
434 CROUCH Table X (cont) 239 Pu Th
Page 450 and 451:
436 CROUCH T a b le X ( c o n t ) P
Page 452 and 453:
438 C R O U C H T a b le X ( c o n
Page 454 and 455:
440 C R O U C H Table XI Pu Thermal
Page 456 and 457:
442 CROUCH T a b l e X I ( c o n t
Page 458 and 459:
4 4 4 CRO U CH T a b l e X I ( c o
Page 460 and 461:
1 83 84 89 90 91 92 93 95 97 99 103
Page 462 and 463:
1 89 95 97 99 103 106 109 111 112 1
Page 464 and 465:
450 C R O U C H T a b l e XVI ( c o
Page 466 and 467:
452 c r o u c h Table XVI (cont) Re
Page 468 and 469:
454 CROUCH T a b l e X V I ( c o n
Page 470 and 471:
456 C R O U C H T a b l e X V I ( c
Page 472 and 473:
458 C R O U C H m y m e m o r y goe
Page 474 and 475:
460 W ALKER o b t a i n y i e l d s
Page 476 and 477:
462 W ALKER a v e r a g e i s o n l
Page 478 and 479:
464 W ALKER TABLE II. RELATIV E ELE
Page 480 and 481:
Fission Product А Л a ± Да - b
Page 482 and 483:
468 W ALKER p e r i o d . T h e t h
Page 484 and 485:
470 W ALKER T A B L E IV. M A J O R
Page 486 and 487:
472 W ALKER d e t e c t o r t o s o
Page 488 and 489:
474 W ALKER T A B L E V . N U C L I
Page 490 and 491:
476 W ALKER [1 1 ] H a w k i n g s
Page 492 and 493:
478 DEVILLERS e t a l. sont sn effe
Page 494 and 495:
480 DEVILLERS e t a l. . 2 3 8 U' :
Page 496 and 497:
482 DEVILLERS e t a l. Les modes de
Page 498 and 499:
DEVILLERS e t a l. Une table de pro
Page 500 and 501:
suivantes : DEVILLERS e t a l. Les
Page 502 and 503:
488 DEVILLERS e t a l. G ESTION P E
Page 504 and 505:
T A B L E A U III. E N E R G I E L
Page 506 and 507:
492 DEVILLERS e t a l. F I G .3 . D
Page 508 and 509:
494 DEVILLERS e t a l. T A B L E A
Page 510 and 511:
4 9 6 DEVILLERS e t a l. F i l e 1
Page 512 and 513:
4 9 8 DEVILLERS e t a l. F i l e 1
Page 514 and 515:
500 DEVILLERS et al. F i l e 1 MT =
Page 516 and 517:
502 DEVILLERS et al. (2) (3 ) (4 )
Page 519 and 520:
DISCUSSION OF FISSION-PRODUCT YIELD
Page 521 and 522:
IAEA-SM-170/13 507 In their evaluat
Page 523 and 524:
T A B L E I (continu ed) IAEA-SM-17
Page 525 and 526:
IAEA-SM-170/13 511 also measured, t
Page 527 and 528:
IAEA-SM-170/13 513 contribute to th
Page 529 and 530:
LAEA-SM-170/13 515 The accuracy of
Page 531 and 532:
IAEA-SM-170/13 517 The samples used
Page 533 and 534:
LAEA-SM-170/13 519 An example o f t
Page 535 and 536:
IAEA-SM-170/13 521 In the discussio
Page 537 and 538:
IAEA-SM-170/13 523 data have been c
Page 539 and 540:
T A B L E II (con tin u ed) fissio
Page 541 and 542:
IAEA-SM-170/13 527 Apart from the f
Page 543 and 544:
IAEA-SM-170/13 529 mass peak only w
Page 545 and 546:
T A B L E IV (continu ed) Mass No.
Page 547 and 548:
T A B L E IV (continued) Mass No. 1
Page 549 and 550:
T A B L E V (continued) Mass Ko. Th
Page 551 and 552:
T A B L E V (continued) Mass No. Th
Page 553 and 554:
T A B L E VI (continued) Mass No. t
Page 555 and 556:
T A B L E VI (continu ed) Mass No.
Page 557 and 558:
IAEA-SM-170/13 543 and Scadden [9 2
Page 559 and 560:
T A B L E VII (continued) Mass No.
Page 561 and 562:
IAEA-SM-170/13 547 in a forthcoming
Page 563 and 564:
IAEA-SM-170/13 549 [48] WAHL, A. C
Page 565:
IAEA-SM-170/13 551 D I S C U S S I
Page 568 and 569:
554 GRUPPELAAR 2. PRESENT SITUATION
Page 570 and 571:
556 GRUPPELAAR FIG. 1. Calculated c
Page 572 and 573:
558 GRUPPELAAR R E F E R E N C E S
Page 574 and 575:
560 RUSTICHELLI H ow ever, by using
Page 576 and 577:
562 RUSTICHELLI The en ergies of th
Page 578 and 579:
T A B L E I. A B SO L U T E RANGES
Page 580 and 581:
T A B L E II (continu ed) Phosphoru
Page 582 and 583:
T A B L E II (continu ed) Ces i urn
Page 584 and 585:
TABLE II (continued) Americî um Am
Page 586 and 587:
572 RUSTICH ELLI The ra tio in air
Page 589 and 590:
Section VII ACCELERATOR AND SPACE S
Page 591 and 592:
I A E A - S M -17 0 /4 2 USE OF NUC
Page 593 and 594:
I A E A - S M -17 0 /4 2 579 a n d
Page 595 and 596:
I A E A - S M -17 0 /4 2 581 is onl
Page 597 and 598:
I A E A - S M -17 0 /4 2 583 m a g
Page 599 and 600:
IA E A -S M - П 0 /4 2 585 to assa
Page 601 and 602:
I A E A - S M -17 0 /4 2 587 dead l
Page 603 and 604:
I A E A - S M -1 7 0 /4 2 589 phosp
Page 605 and 606:
I A E A - S M -17 0 /4 2 591 T A B
Page 607 and 608:
I A E A - S M -17 0 /4 2 593 [22] V
Page 609 and 610:
I A E A - S M -17 0 /3 5 NUCLEAR DA
Page 611 and 612:
I A E A - S M -1 7 0 /3 5 597 t r o
Page 613 and 614:
I A E A - S M - n O /3 5 599 o u t
Page 615 and 616:
I A E A - S M -17 0 /3 5 601 r e a
Page 617 and 618:
I A E A - S M -17 0 /3 5 603 F IG .
Page 619 and 620:
I A E A - S M - n O /3 5 605 s y s
Page 621 and 622:
TRANSPORT OF NEUTRONS INDUCED BY 8
Page 623 and 624:
MAIN BEAM UNE IAEA-SM-17 0 /4 5 609
Page 625 and 626:
I A E A - S M -17 0 /4 5 611 F I G
Page 627 and 628:
(a) A cy lin d rica l geometry was
Page 629 and 630:
I A E A - S M -17 0 /4 5 F IG . 7 .
Page 631 and 632:
I A E A - S M -17 0 /4 5 REFERENCES
Page 633 and 634:
I A E A - S M -17 0 /4 5 619 is o f
Page 635 and 636:
H O W T O O RD ER IAEA PUBLICATIONS
show all

PROCEEDINGS OF A SYMPO - IAEA Nuclear Data Services

You also want an ePaper? Increase the reach of your titles

Delete template?

Save as template?