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

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FOREWORD A report issued by an international study group for the transmutation of nuclear waste using accelerator driven systems has highlighted the need for specific sets of nuclear data. These authoritative requirements include fission product yields at an intermediate incident neutron energy of up to 150 MeV. Before the start of the present CRP on fission product yield data for the transmutation of nuclear waste, only four types of evaluated fission yield data sets existed, namely for spontaneous fission, and for fission induced by thermal, fast (or fission) spectrum, and by ‘high energy’ (14–15 MeV) neutrons. A new type of evaluation for energy dependent neutron induced fission yields was required for this project. In view of the scarcity of experimental data, such an evaluation has to be based on systematics and theoretical model calculations. Unlike fission cross-sections, where nuclear models are being used successfully for the calculation of unmeasured cross-section ranges, such models or theories existed only for low energy fission yields. Hence the CRP participants entered a completely new field of research for which the progress and outcome were unpredictable. Clearly the ultimate goal of such an effort, namely an evaluation of energy dependent fission yields, could not be realized within the perceived lifetime of a CRP. The main emphasis of the CRP was on the development of adequate systematics and models for the calculation of energy dependent fission yields up to 150 MeV incident neutron energy. Several problems had to be solved, such as the correct choice of model parameters and multiplicity distributions of emitted neutrons, and the effect of multi-chance fission. Models and systematics have been tested for lower energy yields, but they failed to reproduce recent experimental data, particularly at higher energies, and the parameters had to be modified. Other models have been developed from the analysis of experimental data in order to derive systematic dependences and they were adapted in the course of the CRP to predict fission product yields. The valuable role of the CRP in such work became evident during the meetings, at which the discussions formed a fruitful basis for improvements to the models. The benchmark exercise revealed the true worth and predictive capabilities of the systematics and theoretical models developed during the course of the CRP. Necessary improvements and the direction of future studies were also revealed. These models have the potential to give reliable predictions after implementation of the improvements suggested in this report. A brief introduction and the various studies undertaken by individual participants are given at the beginning of this publication, followed by a detailed description of the resulting overall achievements, conclusions and recommendations of the CRP and a summary of the benchmark exercise and results. Additional material is included on the enclosed CD-ROM, including compilations of the fission product yields, unedited papers and all details of the benchmark exercise. The IAEA wishes to thank all CRP participants for their contributions to the project. The IAEA responsible officers were M. Lammer and A.L. Nichols of the Division of Physical and Chemical Sciences.
CONTRIBUTING AUTHORS Denschlag, J.-O. Johannes-Gutenberg-Universität Mainz, Germany Duijvestijn, M.C. Nuclear Research and Consultancy Group, Netherlands Ethvignot, Th. Service de Physique Nucléaire, Commissariat à l’Énergie Atomique, France Hambsch, F.-J. EC Joint Research Centre, Institute for Reference Materials and Measurements, Belgium Katakura, J. Japan Atomic Energy Agency, Japan Kibkalo, Yu.V. SC Institute for Nuclear Research, Ukraine Lammer, M. International Atomic Energy Agency Tingjin, Liu China Institute of Atomic Energy, China Maslov, V.M. Belarus Academy of Sciences, Belarus Mills, R.W. Nexia Solutions, British Nuclear Fuels plc, United Kingdom Wahl, A.C. Los Alamos National Laboratory, United States of America Zhdanov, S.V. National Nuclear Centre, Kazakhstan TECHNICAL ASSISTANCE Nichols, A.L. International Atomic Energy Agency EDITORIAL NOTE The use of particular designations of countries or territories does not imply any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries. The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA.
Page 1 and 2: Fission Product Yield Data for the
Page 3 and 4: AFGHANISTAN ALBANIA ALGERIA ANGOLA
Page 5: COPYRIGHT NOTICE All IAEA scientifi
Page 9 and 10: 3.2.1. Introduction . . . . . . . .
Page 11 and 12: 6. BENCHMARK EXERCISE . . . . . . .
Page 13 and 14: However, this CRP entered an entire
Page 15 and 16: ‘Provisional masses’ are determ
Page 17 and 18: Three scientists were invited to pa
Page 19 and 20: 8 (d) Prompt or delayed neutron emi
Page 21 and 22: [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
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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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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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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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This publication reports on a coord
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