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 58-Ce-141 JENDL-3 5.7967E+00 0.00 3.10 5.9536E+00 0.00 –4.79 4.3742E+00 0.00 4.67 58-Ce-141 CENDL/FY 5.7555E+00 2.22 3.79 5.9961E+00 4.72 –5.53 4.6061E+00 9.94 –0.39 58-Ce-143 THIS WORK 5.9993E+00 0.77 0 5.6022E+00 1.01 0 3.7919E+00 2.67 0 58-Ce-143 ENDF/B-VI 5.9558E+00 1.40 0.73 5.7312E+00 1.40 –2.30 3.8147E+00 2.80 –0.60 58-Ce-143 JEF-2 5.9447E+00 7.31 0.91 5.6893E+00 10.36 –1.55 3.8712E+00 4.89 –2.09 58-Ce-143 JENDL-3 5.9388E+00 0.00 1.01 5.6886E+00 0.00 –1.54 3.8061E+00 0.00 –0.38 58-Ce-143 CENDL/FY 5.7861E+00 4.28 3.55 5.5847E+00 1.74 0.31 3.8820E+00 3.16 –2.38 59-Pr-141 THIS WORK 5.9929E+00 0.94 0 5.6184E+00 3.07 0 4.5600E+00 10.96 0 59-Pr-141 ENDF/B-VI 5.8470E+00 1.00 2.43 5.9491E+00 1.40 –5.89 4.4855E+00 4.00 1.63 59-Pr-141 JEF-2 5.8527E+00 6.96 2.34 5.6784E+00 8.13 –1.07 4.4280E+00 7.25 2.89 59-Pr-141 JENDL-3 5.7967E+00 0.00 3.27 5.9536E+00 0.00 –5.97 4.3742E+00 0.00 4.07 59-Pr-141 CENDL/FY 5.4907E+00 5.37 8.38 5.9747E+00 4.91 –6.34 4.6537E+00 92.35 –2.05 59-Pr-144 THIS WORK 5.5523E+00 0.70 0 5.1470E+00 2.52 0 59-Pr-144 ENDF/B-VI 5.4996E+00 0.50 0.95 5.2686E+00 1.00 –2.36 59-Pr-144 JEF-2 5.4629E+00 2.89 1.61 4.8849E+00 4.29 5.09 59-Pr-144 JENDL-3 5.4725E+00 0.00 1.44 5.2580E+00 0.00 –2.16 59-Pr-144 CENDL/FY 6.0148E+00 80.71 –8.33 5.3180E+00 99.71 –3.32 60-Nd-143 THIS WORK 5.9603E+00 0.70 0 5.6920E+00 0.86 0 60-Nd-143 ENDF/B-VI 5.9558E+00 0.35 0.08 5.7312E+00 0.50 –0.69 60-Nd-143 JEF-2 5.9447E+00 0.94 0.26 5.6893E+00 1.03 0.05 60-Nd-143 JENDL-3 5.9388E+00 0.00 0.36 5.6887E+00 0.00 0.06 60-Nd-143 CENDL/FY 5.9643E+00 0.97 –0.07 5.6870E+00 0.81 0.09 60-Nd-144 THIS WORK 5.4571E+00 0.47 0 5.1929E+00 0.97 0 60-Nd-144 ENDF/B-VI 5.4996E+00 0.35 –0.78 5.2687E+00 0.70 –1.46 60-Nd-144 JEF-2 5.4630E+00 0.70 –0.11 4.8850E+00 2.04 5.93 60-Nd-144 JENDL-3 5.4725E+00 0.00 –0.28 5.2580E+00 0.00 –1.25 60-Nd-144 CENDL/FY 5.4904E+00 4.78 –0.61 5.1500E+00 1.86 0.83 60-Nd-145 THIS WORK 3.9403E+00 0.72 0 3.7641E+00 1.04 0 65
TABLE 3.2.4. COMPARISON OF RECOMMENDED YIELDS FROM 235 U FISSION WITH THOSE FROM OTHER LIBRARIES (cont.) 66 Thermal spectrum <strong>Fission</strong> spectrum 14 MeV YIELD Y UNCERT (%) DIFF (%) YIELD Y UNCERT (%) DIFF (%) YIELD Y UNCERT (%) DIFF (%) Nuclide Library 60-Nd-145 ENDF/B-VI 3.9334E+00 0.35 0.18 3.7757E+00 0.50 –0.31 60-Nd-145 JEF-2 3.9318E+00 0.79 0.22 3.8044E+00 2.66 –1.07 60-Nd-145 JENDL-3 3.9175E+00 0.00 0.58 3.7429E+00 0.00 0.56 60-Nd-145 CENDL/FY 3.9495E+00 4.90 –0.23 3.7434E+00 0.40 0.55 60-Nd-146 THIS WORK 2.9654E+00 0.38 0 2.9102E+00 0.63 0 60-Nd-146 ENDF/B-VI 2.9969E+00 0.35 –1.06 2.9213E+00 0.50 –0.38 60-Nd-146 JEF-2 2.9816E+00 0.79 –0.55 2.9268E+00 2.67 –0.57 60-Nd-146 JENDL-3 2.9755E+00 0.00 –0.34 2.9027E+00 0.00 0.26 60-Nd-146 CENDL/FY 2.9939E+00 4.52 –0.96 2.9020E+00 0.39 0.28 60-Nd-148 THIS WORK 1.6747E+00 0.67 0 1.6980E+00 0.66 0 60-Nd-148 ENDF/B-VI 1.6735E+00 0.35 0.07 1.6834E+00 0.50 0.86 60-Nd-148 JEF-2 1.6746E+00 1.03 0.01 1.6979E+00 1.93 0.01 60-Nd-148 JENDL-3 1.6695E+00 0.00 0.31 1.6716E+00 0.00 1.55 60-Nd-148 CENDL/FY 1.6765E+00 1.80 –0.11 1.6709E+00 1.06 1.60 61-Pm-147 THIS WORK 2.2440E+00 0.81 0 2.1807E+00 3.76 0 2.0220E+00 6.00 0 61-Pm-147 ENDF/B-VI 2.2467E+00 1.00 –0.12 2.1389E+00 1.00 1.92 1.6232E+00 2.80 19.72 61-Pm-147 JEF-2 2.2665E+00 8.36 –1.00 2.1367E+00 13.88 2.02 1.6392E+00 9.62 18.93 61-Pm-147 JENDL-3 2.2534E+00 0.00 –0.42 2.0961E+00 0.00 3.88 1.6266E+00 0.00 19.56 61-Pm-147 CENDL/FY 2.3606E+00 5.99 –5.20 1.9044E+00 111.88 12.67 1.6302E+00 100.34 19.38 61-Pm-149 THIS WORK 1.0000E+00 1.68 0 1.0280E+00 3.33 0 61-Pm-149 ENDF/B-VI 1.0816E+00 2.00 –8.16 1.0370E+00 1.40 –0.87 61-Pm-149 JEF-2 1.0478E+00 3.58 –4.78 1.0660E+00 5.77 –3.70 61-Pm-149 JENDL-3 1.0663E+00 0.00 –6.63 1.0259E+00 0.00 0.20 61-Pm-149 CENDL/FY 1.0402E+00 5.19 –4.02 1.0464E+00 16.58 –1.79 61-Pm-151 THIS WORK 4.0693E–01 1.12 0 4.0077E–01 3.96 0 2.6400E–01 1.52 0 61-Pm-151 ENDF/B-VI 4.1877E–01 2.00 –2.91 4.1199E–01 0.70 –2.80 3.5748E–01 16.00 –35.41 61-Pm-151 JEF-2 4.1594E–01 1.59 –2.21 4.3284E–01 4.58 –8.00 4.7362E–01 30.87 –79.40 61-Pm-151 JENDL-3 4.1838E–01 0.00 –2.81 4.0761E–01 0.00 –1.71 3.5361E–01 0.00 –33.94
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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
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
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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:
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
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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