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

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TABLE 3.2.4. COMPARISON OF RECOMMENDED YIELDS FROM 235 U FISSION WITH THOSE FROM OTHER LIBRARIES (cont.) Thermal spectrum <strong>Fission</strong> spectrum 14 MeV YIELD Y UNCERT (%) DIFF (%) YIELD Y UNCERT (%) DIFF (%) YIELD Y UNCERT (%) DIFF (%) Nuclide Library 54-Xe-134 JEF-2 7.7486E+00 1.14 –3.07 7.7783E+00 4.76 –1.09 54-Xe-134 JENDL-3 7.8258E+00 0.00 –4.10 7.5739E+00 0.00 1.57 54-Xe-134 CENDL/FY 7.9319E+00 0.52 –5.51 7.6109E+00 7.54 1.09 54-Xe-135 THIS WORK 6.7770E+00 2.66 0 54-Xe-135 ENDF/B-VI 6.5385E+00 0.70 3.52 54-Xe-135 JEF-2 6.5792E+00 2.38 2.92 54-Xe-135 JENDL-3 6.5315E+00 0.00 3.62 54-Xe-135 CENDL/FY 6.4191E+00 2.57 5.28 54-Xe-136 THIS WORK 6.3213E+00 1.13 0 6.2763E+00 0.77 0 54-Xe-136 ENDF/B-VI 6.3127E+00 0.35 0.14 6.2153E+00 0.50 0.97 54-Xe-136 JEF-2 6.2704E+00 1.66 0.81 6.1953E+00 6.18 1.29 54-Xe-136 JENDL-3 6.3059E+00 0.00 0.24 6.1429E+00 0.00 2.13 54-Xe-136 CENDL/FY 6.3162E+00 2.10 0.08 6.1756E+00 4.13 1.60 54-Xe-137 THIS WORK 6.3361E+00 1.03 0 5.8200E+00 5.00 0 54-Xe-137 ENDF/B-VI 6.1283E+00 1.00 3.28 5.9931E+00 1.40 –2.97 54-Xe-137 JEF-2 6.1571E+00 8.77 2.83 5.8449E+00 14.57 –0.43 54-Xe-137 JENDL-3 6.1109E+00 0.00 3.55 5.9044E+00 0.00 –1.45 54-Xe-137 CENDL/FY 6.2011E+00 4.16 2.13 5.7848E+00 4.03 0.60 54-Xe-138 THIS WORK 6.3810E+00 2.36 0 6.1200E+00 5.00 0 54-Xe-138 ENDF/B-VI 6.2969E+00 1.40 1.32 6.0093E+00 1.40 1.81 54-Xe-138 JEF-2 6.4079E+00 7.56 –0.42 5.9138E+00 13.45 3.37 54-Xe-138 JENDL-3 6.3731E+00 0.00 0.12 6.0324E+00 0.00 1.43 54-Xe-138 CENDL/FY 6.3356E+00 4.17 0.71 5.9612E+00 3.82 2.59 55-Cs-133 THIS WORK 6.7996E+00 0.71 0 6.7457E+00 0.89 0 55-Cs-133 ENDF/B-VI 6.6991E+00 0.35 1.48 6.7236E+00 0.50 0.33 55-Cs-133 JEF-2 6.6149E+00 1.05 2.72 6.6100E+00 2.64 2.01 55-Cs-133 JENDL-3 6.7019E+00 0.00 1.44 6.7299E+00 0.00 0.23 55-Cs-133 CENDL/FY 6.6467E+00 0.46 2.25 6.6037E+00 2.87 2.11 63
TABLE 3.2.4. COMPARISON OF RECOMMENDED YIELDS FROM 235 U FISSION WITH THOSE FROM OTHER LIBRARIES (cont.) 64 Thermal spectrum <strong>Fission</strong> spectrum 14 MeV YIELD Y UNCERT (%) DIFF (%) YIELD Y UNCERT (%) DIFF (%) YIELD Y UNCERT (%) DIFF (%) Nuclide Library 55-Cs-135 THIS WORK 6.5311E+00 0.66 0 6.5240E+00 0.64 0 5.6990E+00 6.00 0 55-Cs-135 ENDF/B-VI 6.5390E+00 64.00 –0.12 6.6013E+00 64.00 –1.18 5.7288E+00 64.00 –0.52 55-Cs-135 JEF-2 6.5803E+00 2.23 –0.75 6.3696E+00 3.68 2.37 5.7721E+00 10.41 –1.28 55-Cs-135 JENDL-3 6.5337E+00 0.00 –0.04 6.5711E+00 0.00 –0.72 5.9116E+00 0.00 –3.73 55-Cs-135 CENDL/FY 6.5300E+00 0.35 0.02 6.3696E+00 1.73 2.37 5.4936E+00 79.67 3.60 55-Cs-136 THIS WORK 5.4965E–03 6.70 0 55-Cs-136 ENDF/B-VI 5.5376E–03 64.00 –0.75 55-Cs-136 JEF-2 8.7521E–03 34.94 –59.23 55-Cs-136 JENDL-3 5.4718E–03 0.00 0.45 55-Cs-136 CENDL/FY 6.1531E–03 125.87 –11.95 55-Cs-137 THIS WORK 6.2052E+00 0.82 0 6.2008E+00 0.86 0 55-Cs-137 ENDF/B-VI 6.1883E+00 0.50 0.27 6.2214E+00 0.50 –0.33 55-Cs-137 JEF-2 6.2444E+00 8.64 –0.63 5.9962E+00 14.07 3.30 55-Cs-137 JENDL-3 6.2686E+00 0.00 –1.02 6.2032E+00 0.00 –0.04 55-Cs-137 CENDL/FY 6.1844E+00 2.86 0.34 6.1237E+00 0.87 1.24 56-Ba-140 THIS WORK 6.2059E+00 0.99 0 6.1514E+00 1.60 0 4.5963E+00 2.53 0 56-Ba-140 ENDF/B-VI 6.2145E+00 1.00 –0.14 5.9777E+00 1.00 2.82 4.4949E+00 2.80 2.21 56-Ba-140 JEF-2 6.2760E+00 1.19 –1.13 5.7817E+00 0.99 6.01 4.3034E+00 1.48 6.37 56-Ba-140 JENDL-3 6.2946E+00 0.00 –1.43 6.1187E+00 0.00 0.53 4.4477E+00 0.00 3.23 56-Ba-140 CENDL/FY 6.2801E+00 1.38 –1.20 5.9274E+00 9.02 3.64 4.4743E+00 8.07 2.65 57-La-140 THIS WORK 6.4070E+00 1.72 0 57-La-140 ENDF/B-VI 6.2197E+00 1.00 2.92 57-La-140 JEF-2 6.2767E+00 1.19 2.03 57-La-140 JENDL-3 6.3000E+00 0.00 1.67 57-La-140 CENDL/FY 6.1538E+00 14.62 3.95 58-Ce-141 THIS WORK 5.9823E+00 0.85 0 5.6817E+00 1.56 0 4.5883E+00 3.08 0 58-Ce-141 ENDF/B-VI 5.8470E+00 1.00 2.26 5.9491E+00 2.80 –4.71 4.4855E+00 6.00 2.24 58-Ce-141 JEF-2 5.8527E+00 5.28 2.17 5.6784E+00 10.12 0.06 4.4280E+00 10.57 3.49
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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
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 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
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FIG. 4.1.9. Total and mode separate
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4.2. SYSTEMATICS OF FISSION PRODUCT
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A - = (PA - NT)/2 (4.2.1b) 4.2.2.3.
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FIG. 4.2.4(a). 238 U + 5.5 MeV n, L
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FIG. 4.2.8(a). U238 + 300 MeV p, LS
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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
Page 256 and 257:
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
Page 265 and 266:
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:
Page 289 and 290:
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
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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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