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

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all product nuclides. The data tables were processed to generate the data in the required format. I.3.2.12. Laurec et al. [I.14] Measurement type 2: The cumulative yields from 233,235,238 U and 239 Pu fission induced by fission spectrum and 14.7 MeV neutrons were measured by the radiochemical method. The g ray spectra were measured with a Ge(Li) detector and the number of fissions was determined with a plane ionization chamber. The data for 239 Pu fission at 14.9 MeV were used. Although the measured yields are cumulative, the differences between these values and the chain yields are all within the experimental uncertainties. So all data were used except for 136 Xe, whose yield is small and possibly incorrect. I.3.2.13. Winkelmann et al. [I.15] Measurement type 2: The cumulative yields from 242 Pu fission induced by 15.1 MeV neutrons were measured for 65 fission products from 85 Kr to 151 Pm. The fission product activities were measured by direct g ray spectrometry with a Ge(Li) detector, as well as chemical separation of the fission product elements Pd, Ag, Cd, Sn, Sb and Ce, followed by b counting or g ray spectrometry. The chain yields of 43 mass chains were obtained by dividing the measured cumulative yields by an adjustment factor, which is the ratio of the cumulative yield of the measured product nuclide to the corresponding chain yield. The data were used after the following procedures had been applied: (a) Some chain yields were obtained from two or more cumulative yields — the recommended chain yield was taken as their weighted average. (b) Two fission yields were not used: that of 126g Sb because the value is an independent yield, and that of 111m Pm because the datum is only a partial isomeric yield. (c) The data of product nuclides 130g Sb, 131 Sb and 131m Te were also discarded. The chain yields deduced from the cumulative yields of these nuclides are too small. The fractions of the measured cumulative yields to the corresponding chain yields are too small, which could introduce large uncertainties into the resulting chain yields. In addition, there are large differences for the adjustment factors of these nuclides between the values given in the paper and those calculated with the data from ENDF/B-VI. I.4. RESULTS, RECOMMENDATIONS AND DISCUSSION Based on the data selected from the available experimental data, and after their evaluation and processing as described above, the recommended mass distribution data for 238 U, 239,242 Pu fission are listed in Table I.1. All recommended data are given in the annex to this section, and plotted in Figs I.1–I.16. As mentioned above, there are two types of measurements for mass distributions: (a) Data are obtained by recording prompt fission fragments (data type 1 in Table I.1) with a double Frisch gridded ionization chamber, silicon PIN diode detector arrays, etc., as described by Vivès et al., Zöller and Äystö et al. (b) Data are obtained by recording the radioactivity of fission product nuclides (data type 2 in Table I.1) by means of g ray spectrometry with a Ge(Li) or HPGe detector, either directly from the fission sample or after radiochemical separation, as undertaken by Nagy et al., Chapman, Li Ze et al., Liu Conggui et al., Daroczy et al., Liu Yonghui et al., Gindler et al., Ford, Laurec et al. and Winkelmann et al. From the comparisons in Figs I.17–I.19, the data measured by different laboratories but obtained with the same type of method (data type 1 or 2) are generally found to be in good agreement within the experimental uncertainty. But there is a systematic difference between the two types of data. The reason lies (a) in the physical nature of the measured yield and (b) in differences in the measurement techniques. The essential difference between the two types of method is that for type 2 there is some delay time (days, hours seconds, etc.) between fragment formation and measurement, during which the radioactive products decay (although this effect can be accounted for), whereas for data type 1 the measurement is ‘prompt’. Nevertheless, even in the type 1 method the fragments are generally measured 283
after prompt-neutron emission, and are labelled as post-neutron emissions. Fragment data before prompt emission, (pre-neutron emission data) are obtained after adjustment, as described by Vivès et al. 284 TABLE I.1. RECOMMENDED MASS DISTRIBUTION DATA Fissile nuclide Energy (MeV) Author (energy (MeV)) Reference Data type 238 U 239 Pu En around 1.5 Vivès (1.6) Nagy (1.5) En = 5.5 Vivès Nagy En around 8.2 Li Ze (8.3) Chapman (8.1) En around 11.3 Li Ze (11.3) Zöller (11.5–14.5) En around 14.5 Liu Conggui (14.9) Daroczy (14.5) Zöller (11.5–14.5) En around 22.0 Liu Yonghui (22) Zöller (18–22) I.1 I.4 I.1 I.4 I.6 I.5 I.7 I.3 I.8 I.9 I.3 I.10 I.3 En around 27.5 Zöller (22–33) I.3 1 En around 50.0 Zöller (45–55) I.3 1 En around 100 Zöller (89–110) I.3 1 En around 160 Zöller (145–175) I.3 1 Ep = 20.0 Äystö I.11 1 Ep = 60.0 Äystö I.11 1 En = 0.17 Gindler I.12 2 En = 7.9 Gindler I.12 2 En around 14.5 Ford (14.0) I.13 2 Laurec (14.7) I.14 2 242 Pu En = 15.1 Winkelmann I.15 2 Vivès et al. (2000) 1.6 MeV [I.1] Nagy et al. (1978) 1.5 MeV [I.4] FIG. I.1. Mass distribution from 238 U fission at E n of around 1.5 MeV. 1 2 1 2 2 2 2 1 2 2 1 2 1 Nagy et al. (1978) [I.4] Vivès et al. (2000) [I.1] FIG. I.2. Mass distribution from 238 U fission at E n = 5.5 MeV. and Zöller [I.1, I.3]. So in the data file (figures and annex), ‘post’ and ‘pre’ refer to the prompt neutrons for type 1. However, all type 2 data are not only postneutron emission, but also after delayed neutron emission.
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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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Page 246 and 247: TABLE 4.6.5. ACCURACIES OBTAINED FR
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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
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Page 267 and 268: 256 Valley heights and peak-to-vall
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Page 271 and 272: 260 Wahl uncert. margins Wahl uncer
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Page 277 and 278: Wahl (1.6-160 MeV): Distributions a
Page 279 and 280: TABLE 6.2.2. 238 U PRE-NEUTRON EMIS
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Page 283 and 284: FIG. 6.2.14. Benchmark exercise, pa
Page 289 and 290: 278 REFERENCES TO SECTION 6 [6.1] B
Page 291 and 292: As mentioned above, the mass distri
Page 293: I.3.2.6. Liu Conggui et al. [I.8] M
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
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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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