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

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TABLE 3.2.5. COMPARISON OF RECOMMENDED YIELDS FROM 238 U FISSION WITH THOSE FROM OTHER LIBRARIES (cont.) Nuclide Library <strong>Fission</strong> spectrum 14 MeV YIELD Y UNCERT (%) DIFF (%) YIELD Y UNCERT (%) DIFF (%) 62-Sm-147 JENDL-3 2.5298E+00 0.00 –0.13 2.0969E+00 0.00 –2.97 62-Sm-147 CENDL/FY 2.5149E+00 1.54 0.46 2.0617E+00 11.62 –1.24 62-Sm-149 THIS WORK 1.5850E+00 1.20 0 1.2038E+00 2.84 0 62-Sm-149 ENDF/B-VI 1.6253E+00 1.00 –2.54 1.4582E+00 6.00 –21.13 62-Sm-149 JEF-2 1.6647E+00 4.34 –5.03 1.3409E+00 7.96 –11.39 62-Sm-149 JENDL-3 1.6076E+00 0.00 –1.42 1.4227E+00 0.00 –18.18 62-Sm-149 CENDL/FY 1.5866E+00 6.82 –0.10 1.4303E+00 99.92 –18.82 62-Sm-151 THIS WORK 7.8691E–01 3.12 0 6.5409E–01 2.60 0 62-Sm-151 ENDF/B-VI 7.9940E–01 1.40 –1.59 8.0147E–01 4.00 –22.53 62-Sm-151 JEF-2 8.0914E–01 3.62 –2.82 7.8719E–01 9.61 –20.35 62-Sm-151 JENDL-3 8.0064E–01 0.00 –1.74 8.0144E–01 0.00 –22.53 62-Sm-151 CENDL/FY 7.9910E–01 1.70 –1.55 8.1694E–01 99.93 –24.90 62-Sm-152 THIS WORK 5.2168E–01 1.11 0 62-Sm-152 ENDF/B-VI 5.3023E–01 1.00 –1.64 62-Sm-152 JEF-2 5.4985E–01 7.17 –5.40 62-Sm-152 JENDL-3 5.2075E–01 0.00 0.18 62-Sm-152 CENDL/FY 5.1920E–01 1.80 0.48 63-Eu-156 THIS WORK 6.7100E–02 3.13 0 1.0900E–01 2.66 0 63-Eu-156 ENDF/B-VI 7.6034E–02 2.00 –13.31 1.1437E–01 2.80 –4.92 63-Eu-156 JEF-2 6.3156E–02 4.92 5.88 1.1232E–01 6.75 –3.05 63-Eu-156 JENDL-3 6.7481E–02 0.00 –0.57 1.0798E–01 0.00 0.93 63-Eu-156 CENDL/FY 7.5269E–02 3.53 –12.17 1.1259E–01 4.47 –3.29 65-Tb-161 THIS WORK 1.1436E–03 7.87 0 8.2450E–03 6.12 0 65-Tb-161 ENDF/B-VI 1.2150E–03 2.80 –6.24 8.4690E–03 4.00 –2.72 65-Tb-161 JEF-2 1.1559E–03 40.50 –1.08 7.8741E–03 31.30 4.50 65-Tb-161 JENDL-3 1.2798E–03 0.00 –11.91 8.4897E–03 0.00 –2.97 65-Tb-161 CENDL/FY 1.1881E–03 18.30 –3.89 8.7347E–03 3.73 –5.94 TABLE 3.2.6. COMPARISON OF RECOMMENDED YIELDS FROM 235 U FISSION WITH THOSE FROM OTHER LIBRARIES Energy Æ Nuclide B-VI T JEF CFY Total B-VI F JEF CFY Total B-VI H JEF CFY Total Total 33-As- 85 L L 2 N N 2 34-Se- 79 N N 0 35-Br- 88 N N 0 35-Br- 89 L L 2 N N 2 35-Br- 90 L L 2 N N 2 35-Br- 91 L L 2 N N 2 36-Kr- 83 0 0 N 0 36-Kr- 86 0 0 N 0 77
TABLE 3.2.6. COMPARISON OF RECOMMENDED YIELDS FROM 235 U FISSION WITH THOSE FROM OTHER LIBRARIES (cont.) Energy Æ T F H Nuclide B-VI JEF CFY Total B-VI JEF CFY Total B-VI JEF CFY Total 36-Kr- 87 0 0 N 0 37-Rb- 93 L 1 N N 1 37-Rb- 94 0 N N 0 37-Rb- 95 L 1 N N 1 38-Sr- 89 0 0 0 0 38-Sr- 90 0 0 0 0 38-Sr- 92 0 N N 0 39-Y - 91 0 0 0 0 39-Y - 99 L 1 N N 1 40-Zr- 91 0 0 0 0 40-Zr- 93 0 0 0 0 40-Zr- 96 0 0 N 0 41-Nb- 95 0 0 N 0 42-Mo- 95 0 0 N 0 42-Mo- 97 0 0 N 0 42-Mo-100 0 0 N 0 43-Tc- 99 0 N N 0 44-Ru-101 0 0 N 0 44-Ru-102 0 0 N 0 44-Ru-103 0 0 0 0 44-Ru-104 0 L 1 N 1 44-Ru-106 0 L L L 3 0 3 45-Rh-103 0 0 0 0 45-Rh-106 0 N N 0 46-Pd-105 0 0 L 1 1 46-Pd-107 0 N N 0 47-Ag-109 0 N N 0 47-Ag-111 L L 2 L L 2 L L 2 6 48-Cd-115 L L L 3 L L L 3 L L 2 8 48-Cd-115M L L 2 L L L 3 L L 2 7 50-Sn-126 0 0 N 0 51-Sb-125 L 1 0 N 1 51-Sb-135 0 N N 0 52-Te-132 0 0 0 0 53-I -129 L L 2 L 1 0 3 53-I -131 0 0 0 0 53-I -135 0 0 0 0 53-I -137 L L L 3 0 N 3 53-I -138 0 N N 0 53-I -139 L L L 3 N N 3 54-Xe-131 0 0 N 0 78 Total
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Fission Product Yield Data for the
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AFGHANISTAN ALBANIA ALGERIA ANGOLA
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COPYRIGHT NOTICE All IAEA scientifi
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CONTRIBUTING AUTHORS Denschlag, J.-
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3.2.1. Introduction . . . . . . . .
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6. BENCHMARK EXERCISE . . . . . . .
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However, this CRP entered an entire
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‘Provisional masses’ are determ
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Three scientists were invited to pa
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8 (d) Prompt or delayed neutron emi
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[2.1.40] ITKIS, M.G., OGANESSIAN, Y
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[2.1.96] PATE, B.D., et al., Distri
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[2.1.152] JACOBS, E., et al., Produ
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16 2.2. MEASUREMENTS OF THE ENERGY
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FIG. 2.2.3. 94 Sr: best experimenta
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FIG. 2.2.15. 132 Te: best experimen
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FIG. 2.2.27. 146 Ba: best experimen
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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 52 and 53: [3.1.48] DUSHIN, V.N., et al., Stat
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
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values (points) and the derived fun
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distributions. Values of N(A) seldo
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FIG. 4.2.19. Systematic Z P paramet
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FIG. 4.2.21. Systematic Z P paramet
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FIG. 4.2.23. Nuclear charge displac
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FIG. 4.2.24. Number of protons emit
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epresenting model values and thus s
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FIG. 4.2.36. n T(A) for CF249T. FIG
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FIG. 4.2.41. U235T, line: model; po
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The FAST subroutine in the CYFP pro
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[4.2.28] BELHAFAF, D., et al., Kine
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4.3. FIVE GAUSSIAN SYSTEMATICS FOR
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Derived from measured data Fitted r
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FIG. 4.3.7. Mass distribution of 23
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FFIG. 4.3.12. Mass distribution of
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4.4. PHENOMENOLOGICAL MODEL FOR FRA
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where = 2mE is the wavelength, E
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FIG. 4.4.4. Fragment mass distribut
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fragment mass distributions are des
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FIG. 4.4.10. Fragment mass distribu
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P LD È Ê * E - 44. 7ˆ ˘ = Í1 +
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FIG. 4.4.13. Pre-neutron emission m
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FIG. 4.4.15. Post-neutron emission
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FIG. 4.4.17. Post-neutron emission
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fragment mass and charge distributi
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of the energy dependence of the fus
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4.5. MODAL APPROACH TO THE DESCRIPT
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This information was used for the p
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two neighbouring isotopes at differ
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FIG.4.5.2. Experimental relative ma
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Frequently, the yields Y i (M) are
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the nine optimum description parame
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TABLE 4.5.6. RELATIVE CONTRIBUTIONS
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TABLE 4.5.8. RELATIVE CONTRIBUTIONS
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Extracted values of s 2 M,S demonst
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FIG. 4.5.10. Fission fragment charg
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FIG. 4.5.12. Unchanged charge densi
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FIG. 4.5.16. Mass yield variance fo
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FIG. 4.5.20. Experimental mass yiel
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[4.5.24] GOVERDOVSKII, A.A., MITROF
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TABLE 4.6.1. FISSION PRODUCT YIELD
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TABLE 4.6.2. FIT PARAMETER VALUES O
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FIG. 4.6.2. Charge distributions fo
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model which is elucidated elsewhere
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the agreement is better. The observ
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inner barrier is much lower than th
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e determined in a self-consistent m
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FIG. 4.6.11. Overview of the coupli
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cross-section also has to be incorp
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FIG. 4.6.16. Same as Fig. 4.6.15, b
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FIG. 4.6.20. Pre-neutron emission m
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present have a reasonable contribut
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TABLE 4.6.5. ACCURACIES OBTAINED FR
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[4.6.7] BEIJERS, J.P.M., et al., Se
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5. NEW MODELS AND SYSTEMATICS: DEFI
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therefore his benchmark calculation
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mass distributions and practically
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5.2. BENCHMARK EXERCISE 5.2.1. Benc
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thorough and detailed analysis of t
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the fissioning nucleus and the numb
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should be undertaken — such a stu
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experimental method in order to der
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256 Valley heights and peak-to-vall
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FIG. 6.2.3. Benchmark exercise, par
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260 Wahl uncert. margins Wahl uncer
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264 Wahl uncert. margins (adj. Wahl
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Wahl (1.6-160 MeV): Distributions a
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TABLE 6.2.2. 238 U PRE-NEUTRON EMIS
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as most features are very similar t
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FIG. 6.2.14. Benchmark exercise, pa
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Page 287 and 288:
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278 REFERENCES TO SECTION 6 [6.1] B
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As mentioned above, the mass distri
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I.3.2.6. Liu Conggui et al. [I.8] M
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after prompt-neutron emission, and
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286 Zöller (1995) 89-110 MeV, post
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(1) Data were linearly interpolated
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1. 290 Annex to Appendix I RECOMMEN
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1.2. E n = 5.5 MeV 292 Nagy et al.
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1.3. E n ª 8 MeV 294 Chapman (1978
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1.5. E n = 14-15 MeV 296 Daroczy et
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1.7. E n = 27.5 (22-33) MeV, Zölle
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1.9. E n = 99.5 (89-110) MeV, Zöll
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3. 302 239 Pu NEUTRON INDUCED FISSI
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Appendix II DATA ADJUSTMENT FOR MAS
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Vivès [II.8], Zöller [II.7] and
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Annex 1 to Appendix II ADJUSTED DAT
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Zöller (1995) [II.7] E n = 13 (11.
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E n = 50 (45-55) MeV Post-neutron e
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Äystö et al. (1998) [II.9] E p =
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E n = 1.60 MeV Pre-neutron emission
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E n = 27.5 (22-33) MeV Post-neutron
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E n = 99.5 (89-110) MeV Post-neutro
Page 334 and 335:
Appendix III FISSION YIELD SYSTEMAT
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FIG. III.6. Dependence of chain yie
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TABLE III.2. Ln(y)-LINEAR(E) FIT CO
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FIG. III.14. Dependence of paramete
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FIG. III.26. Comparison of the mass
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FIG. III.38. Comparison of the mass
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TABLE III.3. QUADRATIC FUNCTION FIT
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Uncertainty ratio or uncertainty Ad
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CONTENTS OF THE CD-ROM The attached
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This publication reports on a coord
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