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

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Äystö et al. (1998) [II.9] E p = 20.0 MeV Pre-neutron emission E p = 60.0 MeV Pre-neutron emission Mass A Yield (%) Uncertainty Mass A Yield (%) Uncertainty 7.4000E+01 1.3213E–02 3.0000E–03 7.6000E+01 4.3213E–02 4.8000E–03 7.8000E+01 1.1321E–01 9.0000E–03 8.0000E+01 2.6321E–01 1.8000E–02 8.2000E+01 3.7720E–01 2.5200E–02 8.4000E+01 8.5018E–01 5.4000E–02 8.6000E+01 1.3005E+00 4.0500E–02 8.8000E+01 1.8684E+00 5.7000E–02 9.0000E+01 2.5026E+00 7.5000E–02 9.2000E+01 3.0692E+00 9.0900E–02 9.4000E+01 3.5568E+00 1.0500E–01 9.6000E+01 3.9114E+00 1.1490E–01 9.8000E+01 4.0863E+00 4.0000E–02 1.0000E+02 4.0584E+00 1.1940E–01 1.0200E+02 3.8858E+00 1.1490E–01 1.0400E+02 3.6153E+00 1.0740E–01 1.0600E+02 3.2262E+00 9.6600E–02 1.0800E+02 2.8163E+00 8.4900E–02 1.1000E+02 2.4921E+00 7.5600E–02 1.1200E+02 2.1642E+00 6.6000E–02 1.1400E+02 1.9428E+00 5.9400E–02 1.1600E+02 1.7945E+00 5.4900E–02 1.1800E+02 1.7675E+00 5.4000E–02 1.2000E+02 1.7681E+00 5.4000E–02 1.2200E+02 1.7855E+00 5.4600E–02 1.2400E+02 1.9128E+00 5.8500E–02 1.2600E+02 2.1431E+00 6.5400E–02 1.2800E+02 2.3986E+00 7.2900E–02 1.3000E+02 2.7831E+00 8.4000E–02 1.3200E+02 3.1944E+00 9.5700E–02 1.3400E+02 3.5841E+00 1.0650E–01 1.3600E+02 3.8545E+00 1.1400E–01 1.3800E+02 4.0264E+00 1.1850E–01 1.4000E+02 4.0841E+00 4.0000E–02 1.4200E+02 3.9308E+00 1.1550E–01 1.4400E+02 3.6108E+00 1.0650E–01 1.4600E+02 3.1379E+00 9.3000E–02 1.4800E+02 2.5541E+00 7.6500E–02 1.5000E+02 1.9560E+00 5.9400E–02 1.5200E+02 1.3805E+00 4.2600E–02 1.5400E+02 8.9311E–01 5.6400E–02 1.5600E+02 5.3157E–01 3.4800E–02 1.5800E+02 2.8157E–01 1.9800E–02 1.6000E+02 1.3157E–01 1.0800E–02 1.6200E+02 5.1569E–02 6.0000E–03 7.4000E+01 3.8586E–02 6.0000E–03 7.6000E+01 6.8586E–02 7.8000E–03 7.8000E+01 1.5859E–01 1.3200E–02 8.0000E+01 3.3859E–01 2.4000E–02 8.2000E+01 5.5845E–01 3.7200E–02 8.4000E+01 9.4303E–01 3.0000E–02 8.6000E+01 1.3767E+00 4.2600E–02 8.8000E+01 1.8655E+00 5.6400E–02 9.0000E+01 2.3591E+00 7.0200E–02 9.2000E+01 2.8059E+00 8.2500E–02 9.4000E+01 3.1470E+00 9.2100E–02 9.6000E+01 3.3615E+00 9.8400E–02 9.8000E+01 3.4681E+00 1.0200E–01 1.0000E+02 3.4790E+00 1.0290E–01 1.0200E+02 3.4418E+00 1.0230E–01 1.0400E+02 3.3978E+00 1.0140E–01 1.0600E+02 3.2833E+00 9.8400E–02 1.0800E+02 3.1902E+00 9.6000E–02 1.1000E+02 3.0813E+00 9.3000E–02 1.1200E+02 3.0302E+00 9.1500E–02 1.1400E+02 3.0167E+00 9.0900E–02 1.1600E+02 3.0332E+00 9.1200E–02 1.1800E+02 3.0345E+00 9.1200E–02 1.2000E+02 3.0193E+00 9.0900E–02 1.2200E+02 3.0221E+00 9.1200E–02 1.2400E+02 3.0398E+00 9.1800E–02 1.2600E+02 3.1670E+00 9.5400E–02 1.2800E+02 3.2177E+00 9.6600E–02 1.3000E+02 3.3614E+00 1.0050E–01 1.3200E+02 3.4156E+00 1.0170E–01 1.3400E+02 3.4622E+00 1.0260E–01 1.3600E+02 3.4617E+00 1.0200E–01 1.3800E+02 3.4187E+00 1.0020E–01 1.4000E+02 3.2488E+00 9.5100E–02 1.4200E+02 2.9121E+00 8.5500E–02 1.4400E+02 2.5314E+00 7.5000E–02 1.4600E+02 2.0499E+00 6.1500E–02 1.4800E+02 1.5674E+00 4.8000E–02 1.5000E+02 1.1270E+00 3.5400E–02 1.5200E+02 7.2412E–01 4.6800E–02 1.5400E+02 4.4995E–01 3.0000E–02 1.5600E+02 2.5472E–01 1.8000E–02 1.5800E+02 1.3472E–01 1.0800E–02 1.6000E+02 5.4722E–02 6.0000E–03 1.6200E+02 4.7218E–03 3.0000E–03 315
Vivès et al. (2000) [II.8] 316 Annex 2 to Appendix II ADJUSTED DATA WITH ADJUSTED UNCERTAINTY E n = 1.60 MeV Pre-neutron emission E n = 5.5 MeV Pre-neutron emission Mass A Yield (%) Uncertainty Mass A Yield (%) Uncertainty 75.000 –4.3656E–03 2.8176E–03 78.000 2.7388E–03 6.4378E–03 79.000 8.0673E–03 9.5373E–03 80.000 1.3395E–02 1.2637E–02 81.000 2.8005E–02 2.4160E–02 82.000 3.8401E–02 4.7866E–02 83.000 9.8707E–02 9.6615E–02 84.000 3.5164E–01 1.5110E–01 85.000 4.2392E–01 2.0549E–01 86.000 6.4248E–01 2.6242E–01 87.000 8.7907E–01 3.2172E–01 88.000 1.3097E+00 3.7598E–01 89.000 1.6787E+00 4.3974E–01 90.000 2.1215E+00 4.9996E–01 91.000 2.5971E+00 5.2460E–01 92.000 3.2447E+00 5.2547E–01 93.000 3.7560E+00 4.9028E–01 94.000 4.3424E+00 4.0316E–01 95.000 4.4360E+00 3.4669E–01 96.000 4.6361E+00 3.2422E–01 97.000 4.9172E+00 3.4553E–01 98.000 5.0394E+00 3.7463E–01 99.000 5.5539E+00 4.0886E–01 100.000 6.1263E+00 4.1947E–01 101.000 6.3753E+00 3.7575E–01 102.000 6.4716E+00 2.8362E–01 103.000 6.6572E+00 2.5881E–01 104.000 7.0271E+00 4.5861E–01 105.000 6.3598E+00 7.4180E–01 106.000 5.2813E+00 9.6442E–01 107.000 3.9937E+00 1.0722E+00 108.000 2.6459E+00 1.0319E+00 109.000 1.5191E+00 8.3792E–01 110.000 7.4444E–01 5.9326E–01 111.000 3.9131E–01 3.5047E–01 112.000 2.6189E–01 2.0773E–01 113.000 8.7609E–02 1.1291E–01 114.000 5.8556E–02 5.3899E–02 67.000 2.7711E–04 1.8881E–04 68.000 2.7711E–04 3.9204E–04 69.000 9.6940E–04 6.0592E–04 70.000 2.3540E–03 8.3330E–04 71.000 3.2430E–03 9.3584E–04 72.000 4.2099E–03 9.6907E–04 73.000 4.1060E–03 1.0853E–03 74.000 5.3387E–03 1.5877E–03 75.000 6.0832E–03 2.7429E–03 76.000 7.8019E–03 5.5764E–03 77.000 1.1983E–02 1.0235E–02 78.000 2.9070E–02 1.8139E–02 79.000 3.5724E–02 3.0553E–02 80.000 8.9406E–02 4.7665E–02 81.000 1.3484E–01 6.7734E–02 82.000 2.1427E–01 9.2463E–02 83.000 3.0298E–01 1.2096E–01 84.000 4.4530E–01 1.5611E–01 85.000 5.7356E–01 1.9856E–01 86.000 8.1798E–01 2.4900E–01 87.000 1.0490E+00 2.9564E–01 88.000 1.4099E+00 3.4797E–01 89.000 1.7439E+00 4.0598E–01 90.000 2.2224E+00 4.7023E–01 91.000 2.5176E+00 5.2122E–01 92.000 3.0491E+00 5.4232E–01 93.000 3.8910E+00 5.2344E–01 94.000 4.4983E+00 4.3647E–01 95.000 4.6434E+00 3.7329E–01 96.000 4.7660E+00 3.3354E–01 97.000 4.9223E+00 3.3390E–01 98.000 5.2338E+00 3.3729E–01 99.000 5.8253E+00 3.3562E–01 100.000 6.0551E+00 3.0549E–01 101.000 6.1702E+00 2.6205E–01 102.000 5.9899E+00 2.3069E–01 103.000 5.9916E+00 2.9124E–01 104.000 6.1456E+00 4.4976E–01 105.000 5.6174E+00 6.4812E–01 106.000 4.7795E+00 8.0488E–01 107.000 3.6097E+00 9.0297E–01 108.000 2.5537E+00 8.5961E–01 109.000 1.6316E+00 7.1911E–01 110.000 1.0536E+00 5.2990E–01 111.000 7.3045E–01 3.7068E–01 112.000 4.0852E–01 2.4651E–01 113.000 2.5812E–01 1.5444E–01 114.000 1.5572E–01 8.6253E–02
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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
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3.1.2. Statistical model At least t
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J Â K=-J 2 2 2 ^ sym Krot ( U, J)
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nuclei with N > 144. However, for h
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neutron number. The observed fissio
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FIG. 3.1.6. 235 U(n,f) fission cros
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FIG. 3.1.10. 237 Np(n,f) fission cr
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from higher fission chances [3.1.43
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[3.1.48] DUSHIN, V.N., et al., Stat
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where Y S is our new standard, and
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TABLE 3.2.2. EVALUATED REFERENCE FI
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TABLE 3.2.2. EVALUATED REFERENCE FI
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TABLE 3.2.3. EVALUATED REFERENCE YI
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TABLE 3.2.3. EVALUATED REFERENCE YI
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The comparisons of our evaluated da
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TABLE 3.2.4. COMPARISON OF RECOMMEN
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TABLE 3.2.8. COMPARISON OF THE UNCE
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REFERENCES TO SECTION 3.2 [3.2.1] I
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where N C , N U are the modified an
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activities were recorded with a pro
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3.3.4. Results and discussion The r
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FIG. 3.3.10. Li Ze et al. data: com
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96 Annex 3.3.1 EVALUATED EXPERIMENT
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Li Ze et al. [3.3.8] Thierens et al
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100 Annex 3.3.3 EVALUATED DATA SET
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The range of target nuclides availa
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condensation of cross-sections by t
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(h) REFERENCE (C,80KIEV,171,1980) i
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uncertainties of the calculation. T
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4. SYSTEMATICS AND MODELS FOR THE P
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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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262 Wahl uncert. margins Wahl uncer
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Page 289 and 290: 278 REFERENCES TO SECTION 6 [6.1] B
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Page 295 and 296: after prompt-neutron emission, and
Page 297 and 298: 286 Zöller (1995) 89-110 MeV, post
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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 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
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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
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