Fission Product Yield Data for the Transmutation of Minor Actinide ...

More documents

Recommendations

Info

[3.1.48] DUSHIN, V.N., et al., Statistical analysis of experimential data on the cross sections of 233,235,238 U, 237 Np, 239,242 Pu fission by neutrons of energy 2.6, 8.5, and 14.5 MeV, At. Energ. 55 (1983) 218–222. [3.1.49] ADAMOV, V.M., et al., Absolute measurements of fission cross-sections of heavy elements for fast neutrons, Yad. Konstanty 24 (1977) 8–15. [3.1.50] ZASADNY, K.R., et al., Nuclear data/reactor instrumentation, Trans. Am. Nucl. Soc. 47 (1984) 425–438. [3.1.51] KALININ, V.A., et al., Absolute measurements of the 237 Np and 233 U fission cross-sections at the neutron energy of 1.9 MeV using the TCAP method with magnetic analysis, Vopr. At. Nauki Tekh. (Ser. Yad. Konstanty) 4 (1987) 3–10. 41
42 3.2. EVALUATED REFERENCE FISSION YIELD DATA FILE The Chinese reference fission yield file has been established, in which all experimental data available at the time of evaluation were considered. The data were processed using the AVERAG codes for calculating weighted averages, and ZOTT for the simultaneous evaluation of experimental input data. Our evaluated data were compared with those from ENDF/B-VI, JEF-2, JENDL-3 and CENDL/ FY. The data were updated and improved, and uncertainties were considerably reduced in comparison with JEF-2 and CENDL/FY. 3.2.1. Introduction Fission yield data used as standards in fission yield measurements and evaluations or as monitors in the nuclear industry for decay heat calculations, burnup studies, etc., are referred to as ‘reference fission yields’. These reference fission products and their yields were selected and recommended by an earlier IAEA CRP [3.2.1]. The uncertainties of relative yield measurements depend directly on the accuracy of the standard data, and the same situation applies to yield data derived from measured ratios and R values. Applied calculations, such as decay heat and burnup, etc., also depend on the accuracy of the monitor fission yield. A summary is given of the formulation of this file, including the evaluation method and the system of supporting activities, the result of this evaluation, and the comparison with yield data from other evaluated libraries. Details of the evaluation can be found in Refs [3.2.2–3.2.8], which describe the evaluation of 235 U and 238 U reference fission yields from 1997 to 2001. 3.2.2. Evaluation method 3.2.2.1. Data collection and selection Experimental data were retrieved from the EXFOR master data library and evaluated by using the fission yield data evaluation system FYDES [3.2.9]. Relevant data were also collected from the Liu Tingjin, Liang Qichang China Institute of Atomic Energy, China open literature. All of the data collected are listed in the tables of Refs [3.2.2–3.2.8]. The EXFOR BIB information and papers were carefully studied and the method and physics background were analysed. The adoption or rejection of the data was based on the date of the original study, the measurement method and discrepancies compared with other data. In general, the following data were discarded: (a) The parameter(s) measured are not relevant to this evaluation. (b) There is something wrong with the measurement or data analysis. (c) Compared with other data, the discrepancy is large and the measurement method is not reliable, or no detailed information is given concerning the experiment and/or analysis. (d) The values or the reliability of the adopted standard data in measurements of relative data are not given in the paper. Such information is indispensable in the evaluation of ‘reference yield data’, and data cannot be used that are based on standards of unknown value or reliability. As a result, about half of the data were discarded, and half were used (for details, see Refs [3.2.2– 3.2.8]). 3.2.2.2. Data correction If necessary, the measured data were corrected for the values used for the standards, g ray intensities and fission cross-sections (in absolute measurements). As mentioned above, the relative data were generally not used as published. Such data were only selected when the standard yields used by the authors correspond to, or agree with, the recently evaluated values, or if they can be corrected using our reference yields. These corrections were made by using the equation: U U U = 0 U 8 SO (3.2.1)
Page 1 and 2: Fission Product Yield Data for the
Page 3 and 4: AFGHANISTAN ALBANIA ALGERIA ANGOLA
Page 5 and 6: COPYRIGHT NOTICE All IAEA scientifi
Page 7 and 8: CONTRIBUTING AUTHORS Denschlag, J.-
Page 9 and 10: 3.2.1. Introduction . . . . . . . .
Page 11 and 12: 6. BENCHMARK EXERCISE . . . . . . .
Page 13 and 14: However, this CRP entered an entire
Page 15 and 16: ‘Provisional masses’ are determ
Page 17 and 18: Three scientists were invited to pa
Page 19 and 20: 8 (d) Prompt or delayed neutron emi
Page 21 and 22: [2.1.40] ITKIS, M.G., OGANESSIAN, Y
Page 23 and 24: [2.1.96] PATE, B.D., et al., Distri
Page 25 and 26: [2.1.152] JACOBS, E., et al., Produ
Page 27 and 28: 16 2.2. MEASUREMENTS OF THE ENERGY
Page 29 and 30: FIG. 2.2.3. 94 Sr: best experimenta
Page 31 and 32: FIG. 2.2.15. 132 Te: best experimen
Page 33 and 34: FIG. 2.2.27. 146 Ba: best experimen
Page 36 and 37: 3. EVALUATIONS 3.1. ACTINIDE NUCLEO
Page 38 and 39: 3.1.2. Statistical model At least t
Page 40 and 41: J Â K=-J 2 2 2 ^ sym Krot ( U, J)
Page 42 and 43: nuclei with N > 144. However, for h
Page 44 and 45: neutron number. The observed fissio
Page 46 and 47: FIG. 3.1.6. 235 U(n,f) fission cros
Page 48 and 49: FIG. 3.1.10. 237 Np(n,f) fission cr
Page 50 and 51: from higher fission chances [3.1.43
Page 54 and 55: where Y S is our new standard, and
Page 56 and 57: TABLE 3.2.2. EVALUATED REFERENCE FI
Page 58 and 59: TABLE 3.2.2. EVALUATED REFERENCE FI
Page 60 and 61: TABLE 3.2.3. EVALUATED REFERENCE YI
Page 62 and 63: TABLE 3.2.3. EVALUATED REFERENCE YI
Page 64 and 65: The comparisons of our evaluated da
Page 66 and 67: TABLE 3.2.4. COMPARISON OF RECOMMEN
Page 94 and 95: TABLE 3.2.8. COMPARISON OF THE UNCE
Page 96: REFERENCES TO SECTION 3.2 [3.2.1] I
Page 99 and 100: where N C , N U are the modified an
Page 101 and 102: activities were recorded with a pro
Page 103 and 104:
3.3.4. Results and discussion The r
Page 105 and 106:
FIG. 3.3.10. Li Ze et al. data: com
Page 107 and 108:
96 Annex 3.3.1 EVALUATED EXPERIMENT
Page 109 and 110:
Li Ze et al. [3.3.8] Thierens et al
Page 111 and 112:
100 Annex 3.3.3 EVALUATED DATA SET
Page 113 and 114:
The range of target nuclides availa
Page 115 and 116:
condensation of cross-sections by t
Page 117 and 118:
(h) REFERENCE (C,80KIEV,171,1980) i
Page 119 and 120:
uncertainties of the calculation. T
Page 122 and 123:
4. SYSTEMATICS AND MODELS FOR THE P
Page 124 and 125:
FIG. 4.1.2. 235 U total cross-secti
Page 126 and 127:
FIG. 4.1.9. Total and mode separate
Page 128 and 129:
4.2. SYSTEMATICS OF FISSION PRODUCT
Page 130 and 131:
A - = (PA - NT)/2 (4.2.1b) 4.2.2.3.
Page 132 and 133:
FIG. 4.2.4(a). 238 U + 5.5 MeV n, L
Page 134 and 135:
FIG. 4.2.8(a). U238 + 300 MeV p, LS
Page 136 and 137:
TABLE 4.2.1. EQUATIONS FOR SYSTEMAT
Page 138 and 139:
values (points) and the derived fun
Page 140 and 141:
distributions. Values of N(A) seldo
Page 142 and 143:
FIG. 4.2.19. Systematic Z P paramet
Page 144 and 145:
FIG. 4.2.21. Systematic Z P paramet
Page 146 and 147:
FIG. 4.2.23. Nuclear charge displac
Page 148 and 149:
FIG. 4.2.24. Number of protons emit
Page 150 and 151:
epresenting model values and thus s
Page 152 and 153:
FIG. 4.2.36. n T(A) for CF249T. FIG
Page 154 and 155:
FIG. 4.2.41. U235T, line: model; po
Page 156 and 157:
The FAST subroutine in the CYFP pro
Page 158 and 159:
[4.2.28] BELHAFAF, D., et al., Kine
Page 160 and 161:
4.3. FIVE GAUSSIAN SYSTEMATICS FOR
Page 162 and 163:
Derived from measured data Fitted r
Page 164 and 165:
FIG. 4.3.7. Mass distribution of 23
Page 166 and 167:
FFIG. 4.3.12. Mass distribution of
Page 168 and 169:
4.4. PHENOMENOLOGICAL MODEL FOR FRA
Page 170 and 171:
where = 2mE is the wavelength, E
Page 172 and 173:
FIG. 4.4.4. Fragment mass distribut
Page 174 and 175:
Page 176 and 177:
fragment mass distributions are des
Page 178 and 179:
Page 180 and 181:
FIG. 4.4.10. Fragment mass distribu
Page 182 and 183:
P LD È Ê * E - 44. 7ˆ ˘ = Í1 +
Page 184 and 185:
FIG. 4.4.13. Pre-neutron emission m
Page 186 and 187:
FIG. 4.4.15. Post-neutron emission
Page 188 and 189:
FIG. 4.4.17. Post-neutron emission
Page 190 and 191:
fragment mass and charge distributi
Page 192 and 193:
of the energy dependence of the fus
Page 194 and 195:
4.5. MODAL APPROACH TO THE DESCRIPT
Page 196 and 197:
This information was used for the p
Page 198 and 199:
two neighbouring isotopes at differ
Page 200 and 201:
FIG.4.5.2. Experimental relative ma
Page 202 and 203:
Frequently, the yields Y i (M) are
Page 204 and 205:
the nine optimum description parame
Page 206 and 207:
TABLE 4.5.6. RELATIVE CONTRIBUTIONS
Page 208 and 209:
TABLE 4.5.8. RELATIVE CONTRIBUTIONS
Page 210 and 211:
Extracted values of s 2 M,S demonst
Page 212 and 213:
FIG. 4.5.10. Fission fragment charg
Page 214 and 215:
FIG. 4.5.12. Unchanged charge densi
Page 216 and 217:
FIG. 4.5.16. Mass yield variance fo
Page 218 and 219:
FIG. 4.5.20. Experimental mass yiel
Page 220 and 221:
[4.5.24] GOVERDOVSKII, A.A., MITROF
Page 222 and 223:
TABLE 4.6.1. FISSION PRODUCT YIELD
Page 224 and 225:
TABLE 4.6.2. FIT PARAMETER VALUES O
Page 226 and 227:
FIG. 4.6.2. Charge distributions fo
Page 228 and 229:
model which is elucidated elsewhere
Page 230 and 231:
the agreement is better. The observ
Page 232 and 233:
inner barrier is much lower than th
Page 234 and 235:
e determined in a self-consistent m
Page 236 and 237:
FIG. 4.6.11. Overview of the coupli
Page 238 and 239:
cross-section also has to be incorp
Page 240 and 241:
FIG. 4.6.16. Same as Fig. 4.6.15, b
Page 242 and 243:
FIG. 4.6.20. Pre-neutron emission m
Page 244 and 245:
present have a reasonable contribut
Page 246 and 247:
TABLE 4.6.5. ACCURACIES OBTAINED FR
Page 248 and 249:
[4.6.7] BEIJERS, J.P.M., et al., Se
Page 250 and 251:
5. NEW MODELS AND SYSTEMATICS: DEFI
Page 252 and 253:
therefore his benchmark calculation
Page 254 and 255:
mass distributions and practically
Page 256 and 257:
5.2. BENCHMARK EXERCISE 5.2.1. Benc
Page 258 and 259:
thorough and detailed analysis of t
Page 260 and 261:
the fissioning nucleus and the numb
Page 262:
should be undertaken — such a stu
Page 265 and 266:
experimental method in order to der
Page 267 and 268:
256 Valley heights and peak-to-vall
Page 269 and 270:
FIG. 6.2.3. Benchmark exercise, par
Page 271 and 272:
260 Wahl uncert. margins Wahl uncer
Page 273 and 274:
Page 275 and 276:
264 Wahl uncert. margins (adj. Wahl
Page 277 and 278:
Wahl (1.6-160 MeV): Distributions a
Page 279 and 280:
TABLE 6.2.2. 238 U PRE-NEUTRON EMIS
Page 281 and 282:
as most features are very similar t
Page 283 and 284:
FIG. 6.2.14. Benchmark exercise, pa
Page 285 and 286:
Page 287 and 288:
Page 289 and 290:
278 REFERENCES TO SECTION 6 [6.1] B
Page 291 and 292:
As mentioned above, the mass distri
Page 293 and 294:
I.3.2.6. Liu Conggui et al. [I.8] M
Page 295 and 296:
after prompt-neutron emission, and
Page 297 and 298:
286 Zöller (1995) 89-110 MeV, post
Page 299 and 300:
(1) Data were linearly interpolated
Page 301 and 302:
1. 290 Annex to Appendix I RECOMMEN
Page 303 and 304:
1.2. E n = 5.5 MeV 292 Nagy et al.
Page 305 and 306:
1.3. E n ª 8 MeV 294 Chapman (1978
Page 307 and 308:
1.5. E n = 14-15 MeV 296 Daroczy et
Page 309 and 310:
1.7. E n = 27.5 (22-33) MeV, Zölle
Page 311 and 312:
1.9. E n = 99.5 (89-110) MeV, Zöll
Page 313 and 314:
3. 302 239 Pu NEUTRON INDUCED FISSI
Page 316 and 317:
Appendix II DATA ADJUSTMENT FOR MAS
Page 318 and 319:
Vivès [II.8], Zöller [II.7] and
Page 320 and 321:
Annex 1 to Appendix II ADJUSTED DAT
Page 322 and 323:
Zöller (1995) [II.7] E n = 13 (11.
Page 324 and 325:
E n = 50 (45-55) MeV Post-neutron e
Page 326 and 327:
Äystö et al. (1998) [II.9] E p =
Page 328 and 329:
E n = 1.60 MeV Pre-neutron emission
Page 330 and 331:
E n = 27.5 (22-33) MeV Post-neutron
Page 332 and 333:
E n = 99.5 (89-110) MeV Post-neutro
Page 334 and 335:
Appendix III FISSION YIELD SYSTEMAT
Page 336 and 337:
FIG. III.6. Dependence of chain yie
Page 338 and 339:
TABLE III.2. Ln(y)-LINEAR(E) FIT CO
Page 340 and 341:
FIG. III.14. Dependence of paramete
Page 342 and 343:
FIG. III.26. Comparison of the mass
Page 344 and 345:
FIG. III.38. Comparison of the mass
Page 346 and 347:
TABLE III.3. QUADRATIC FUNCTION FIT
Page 348 and 349:
Uncertainty ratio or uncertainty Ad
Page 350:
CONTENTS OF THE CD-ROM The attached
Page 353:
This publication reports on a coord
show all

Fission Product Yield Data for the Transmutation of Minor Actinide ...

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

Delete template?

Save as template?