JENDL Actinoid File 2008

Journal of Nuclear Science and Technology

Volumn 46, Issue 5, 2009, Pages 510-528

  Iwamoto, Osamu ^a   Nakagawa, Tsuneo ^a   Otuka, Naohiko ^a,c   Chib, Satoshia ^a   Okumura, Keisuke ^a   Chiba, Go ^a   Ohsawa, Takaaki ^b   Furutaka, Kazuyoshi ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b KINKI UNIVERSITY   (Japan)

^c INTERNATIONAL ATOMIC ENERGY AGENCY   (Austria)

Author keywords

Actinoid; Cross section; Energy spectrum; Evaluation; JENDL; Neutron; Nuclear data

Indexed keywords

ACTINOID; CROSS SECTION; ENERGY SPECTRUM; EVALUATION; JENDL; NUCLEAR DATA;

ISOTOPES; NEUTRON EMISSION; SPECTRUM ANALYSIS;

EMISSION SPECTROSCOPY;

EID: 67649216637     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.3327/jnst.46.510     Document Type: Article

References (81)

1. K. Shibata, T. Kawano, T. Nakagawa et al., "Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3," J. Nucl. Sci. Technol., 39, 1125 (2002).
2. K. Okumura, S. Ohki, M. Yamamoto et al, Study on the Prediction Accuracy of Nuclide Generation and Depletion with JENDL, JAERI-Research 2004-025 (2004).
3. O. Iwamoto, "Development of a comprehensive code for nuclear data evaluation, CCONE, and validation using neutron-induced cross sections for uranium isotopes," J. Nucl. Sci. Technol., 44, 687 (2007).
4. W. P. Poenitz, "Data interpretation, objective evaluation procedures and mathematical techniques for the evaluation of energy-dependent ratio, shape and cross section data," Proc. Conf. Nuclear Data Evaluation Methods and Procedures, Upton, USA, Sep. 22-25, 1980, BNL-NCS-51363, vol. I, 249-289 (1981).
5. S. Chiba, D. L. Smith, A Suggested Procedure for Resolving an Anomaly in Least-Squares Data Analysis Known as "Peele 's Pertinent Puzzle" and the General Implications for Nuclear Data Evaluation, ANL/NDM-121 (1991).
6. M. Herman (Ed.), ENDF-6 Formats Manual, Data Formats and Procedures for the Evaluated Nuclear Data File ENDF/B-VI and ENDF/B-VII, ENDF-102, Reoprt BNL-NCS-44945-05-Rev, revised June 2005 (1990).
7. JENDL Actinoid File 2008, http://wwwndc.jaea.go.jp/ftpnd/jendl/jendl-ac- 2008.html.
8. K. Okumura, G. Chiba, to be published.
9. N. M. Larson, Updated Users' Guide for SAMMY: Multilevel R-Matrix Fits to Neutron Data Using Bays' Equation, ORNL/TM-9179/R7 (2006).
10. 232Th resonance parameters in the energy range 0 to 4000 eV," Proc. ANS Topical Meeting on Reactor Physics (PHYSOR-2006), Vancouver, Canada, Sep. 10-14, 2006, B071 (2006).
11. 233U in the Neutron Energy Range from Thermal to 600 eV, ORNL/TM-2000/372 (2001).
12. 238U resonance parameters from 0 to 20keV," Proc. Int. Conf. Nuclear Data for Science and Technology (ND2004), Santa Fe, USA, Sep. 26-Oct. 1, 2004, vol. 1, 276-281 (2004).
13. 239Pu neutron resonance parameters revisited and covariance matrix in the neutron energy range from thermal to 2.5 keV," Proc. Int. Conf. Nuclear Data for Science and Technology, Nice, France, Apr. 22-27, 2007, 667-670 (2007).
14. 241Pu resonance parameters in the energy range thermal to 20eV," Nucl. Sci. Eng., 150, 109 (2005).
15. V. M. Maslov, E. S. Sukhovitskij, Y. V. Porodzinskij et al., Evaluation of Neutron Data for Americium-242g, INDC(BLR)-008 (1997).
16. Y. Kikuchi, STAT, A Code for Analysis of Statistical Properties of Averaged Resonance Cross Sections, JAERI-M 6248 (1975), [in Japanese].
17. 254gEs," Nucl. Sci. Eng., 90, 298 (1985).
18. Y. Kikuchi, T. Nakagawa, Y. Nakajima, ASREP: A Computer Program for Automatic Search of Unresolved Resonance Parameters, JAERI-Data/Code 99-025 (1999), [in Japanese].
19. O. Schwerer, V. McLane, H. Henriksson, S. Maev, "Nuclear Reaction Data Centre Network: A success story," Proc. Int. Conf. Nucl. Data for Science and Technology, Santa Fe, USA, Sep. 26-Oct. 4, 2004 (AIP-769), 83-86 (2005).
20. S. Chiba, D. Smith, "Impacts of data transformations on least-squares solutions and their significance in data analysis and evaluation," J. Nucl. Sci. Technol., 31, 770 (1994).
21. 241Pu, JAERI-Research 2000-004 (2000).
22. T. Kawano, H. Matsunobu, T. Murata et al., "Simultaneous evaluation of fission cross sections of uranium and plutonium isotopes for JENDL-3.3," J. Nucl. Sci. Technol., 37, 327 (2000).
23. I. ALkhazov, L. Drapchinsky, V. Kalinin et al., "New results of absolute cross-section measurements for the heavy nuclide fission induced by fast neutrons," Proc. Int. Conf. Nuclear Data for Science and Technology, Mito, Japan, May 30-Jun. 3, 1988, 145-148 (1988).
24. T. Iwasaki, F. Manabe, M. Baba et al., "Measurement of fast neutron induced fission cross section ratios of Pu-240 and Pu-242 relative to U-235," J. Nucl. Sci. Technol., 27, 885 (1990).
25. 235U around 14 MeV, Tech. Rep. Faculty of Engineering, Tohoku Univ., 52, 97 (1988).
26. 232Th up to 200MeV," Phys. Rev., C72, 024604 (2005).
27. S. Kunieda, S. Chiba, K. Shibata et al., "Coupled-channels optical model analyses of nucleon-induced reactions for medium and heavy nuclei in the energy region from 1 keV to 200MeV," J. Nucl. Sci. Technol, 44, 838 (2007).
28. T. Ohsawa, "Empirical formulas for estimation of fission prompt neutron multiplicity for actinide nuclides," J. Nucl. Radiochem. Sci., 9, 19 (2008).
29. R. J. Howerton, "v Revisited," Nucl. Sci. Eng., 62, 438 (1977).
30. 237Np," Phys. At. Nuclei, 61, 530 (2000).
31. J. F. Conant, P. F. Palmedo, "Measurement of the delayed-neutron fractions for thermal fission of uranium-235, plutoni-um-239, and uranium-233," Nucl. Sci. Eng., 44, 173 (1971).
32. G. R. Keepin, T. F. Wimett, R. K. Zeigler, "Delayed neutrons from fissionable isotopes of uranium, plutonium, and thorium," Phys. Rev., 107, 1044 (1957).
33. M. S. Krick, A. E. Evans, "The measurement of total delayed-neutron yields as a function of the energy of the neutron inducing fission," Nucl. Sci. Eng., 47, 311 (1972).
34. A. E. Evans, M. M. Thorpe, "Revised delayed-neutron yield data," Nucl. Sci. Eng., 50, 80 (1973).
35. C. F. Masters, M. M. Thorpe, D. B. Smith, "The measurement of absolute delayed-neutron yields from 3.1- and 14.9-MeV fission," Nucl. Sci. Eng., 36, 202 (1969).
36. R. J. Turtle, "Delayed-neutron yields in nuclear fission," Proc. Consultants' Meeting Delayed Neutron Properties, Vienna, Austria, Mar. 26-30, 1979, INDC(NDS)-107/G+Special, 29-67 (1979).
37. R. W. Waldo, R. A. Karam, R. A. Meyer, "Delayed neutron yields: Time dependent measurements and predictive model," Phys. Rev., C23, 1113 (1981).
38. G. Benedetti, A. Cesana, V. Sangiust et al., "Delayed neutron yields from fission of uranium-233, neptunim-237, plutonium-238, -240, -241, and americium-241," Nucl. Sci. Eng., 80, 379 (1982).
39. D. G. Madland, J. R. Nix, "New calculation of prompt fission neutron spectra and average prompt neutron multiplicities," Nucl. Sci. Eng., 81, 213 (1982).
40. O. Iwamoto, "Systematics of prompt fission neutron spectra," J. Nucl. Sci. Technol., 45[9], 910-919 (2008).
41. U. Brosa, S. Grossmann, A. Müller, "Nuclear scission," Phys. Reports, 197[4], 167 (1990).
42. 237Np(n, f)," Nucl. Phys., A653, 17 (1999).
43. th, f)," Nucl. Phys., A665, 3 (2000).
44. 238Np," Nucl. Phys., A594, 45 (1995).
45. F.-C. Wang, J.-M. Hu, "A study of the multimode fission model," J. Phys., G15, 829 (1989).
46. T. Tachibana, M. Uno, M. Yamada, S. Yamada, "Empirical mass formula with proton-neutron interaction," Atomic Data and Nuclear Data Tables, 39, 251 (1988).
47. F. D. Becchetti, Jr., G. W. Greenlees, "Nucleon-nucleus optical-model parameters, A > 40, E > 50MeV," Phys. Rev., 182, 1190 (1969).
48. A. V. Ignatyuk, "The role of collective effects in the systematics of nuclear level densities," Sov. J. Nucl. Phys., 29, 450 (1979).
49. L. V. Drapchinsky (Project Manager), Measurements of the Fission Neutron Spectra of Minor Actinides. Spontaneous Fission of Pu-240, 242 and Thermal Neutron Induced Fission of Cm-243, 245, ISTC 183B-96 (1999).
50. The International Criticality Safety Benchmark Evaluation Project, http://icsbep.inel.gov/.
51. V. M. Piksaykin et al., Pribory i Tekhnika Eksperimenta, 6, 29 (2006), [data were taken from EXFOR].
52. 235U neutron transmission and cross-section measurements in the 0- to 2.25-keV energy range," Nucl. Sci. Eng., 131, 230 (1999).
53. N. Otuka, T. Nakagawa, K. Shibata, "Uranium-235 neutron capture cross section at keV energies," J. Nucl. Sci. Technol, 44, 815 (2008).
54. 235U(n, 2n) cross section between threshold and 13 MeV," Nucl. Sci. Eng., 74, 29 (1980).
55. J. Frehaut, A. Bertin, R. Bois et al., "Status of (n, 2n) cross section measurements at Bruyeres-le-Chatel," Proc. Symposium Neutron Cross Sections from 10-50 MeV, Upton, USA, May 12-14, 1980 (1980).
56. ENSDF, Evaluated Nuclear Structure Data File (2006).
57. p measurements between 1.5 and 15 MeV," Contributions to the EANDC Topical Conference, Saclay, France, Nov. 29, 1972, EANDC(E)-154, 67-90 (1973).
58. J. Frehaut, G. Mosinski, M. Soleilhac (1980), private communication (EXFOR 20490).
59. S. Igarashi, T. Fukahori, Program CASTHY, -Statistical Model Calculation for Neutron Cross Sections and Gamma Ray Spectrum-, JAERI 1321, NEANDC(J)-156/U, INDC(JPN)-143/L (1991).
60. G. V. Vals̀kiy, E. A. Gromova, V. V. Danichev et al., "Np-236 neutron fission cross-section in the energy range up to 10keV," Proc. Int. Conf. on Neutron Physics, Kiev, USSR, Sep. 14-18, 1987, vol. 3, 99 (1987).
61. 236Np," Nucl. Sci. Eng., 124, 482-491 (1996).
62. 236Np," Series: Nuclear Constants, Issue No. 1, 27, (2001);
63. Translated from Russian by the IAEA, INDC(CCP)-432, 35-42 (2002).
64. 238Np," Series: Nuclear Constants, Issue No. 1, 19, (1999);
65. Translated from Russian by the IAEA, INDC(CCP)-424, 19-25 (2000).
66. M. B. Chadwick, P. Obložinský, M. Herman et al., "ENDF/B-VII.O: Next generation evaluated nuclear data library for nuclear science and technology," Nucl. Data Sheet, 107[12], 2931 (2006).
67. N. M. Larson, "Updated Users' Guide for SAMMY: Multilevel R-Matrix Fits to Neutron Data Using Bayes Equations," Sep. 2006, corrected Sep. 2007, ORNL/TM-9179/R7, ENDF-364/R1.
68. A. H. Jaffey, J. L. Lerner, "Number of neutrons per fission," Argonne National Laboratory Report series No. 6600, 124 (1961).
69. M. Lindner, D. W. Seegmiller, "Reactor neutron fission characteristics of the long-lived isomer of neptunium 236," Radio-chimica Acta, 49, 1-12 (1990).
70. 238Np," Trans. Am. Nucl. Soc, 12, 284 (1969).
71. S. N. Abramovich, M. F. Andreev, Y. M. Bolshakov et al., Proc. XIII Meeting on Physics of Nuclear Fission in the Memory of Prof. G. N. Smirenkin, Obninsk, Oct. 3-6, 303 (1995).
72. 238Np near the thermal point," Proc. Int. Conf. Nucl. Data for Sci. and Technol., Trieste, Italy, May 19-24, 1997, Vol. 2, 1353-1355 (1997).
73. 238Np for thermal neutrons," J. Nucl. Sci. Technol, 41, 1-6 (2004).
74. L. W. Weston, J. H. Todd, "Neutron capture cross section of plutonium-240," Nucl Sci. Eng., 63, 143 (1977).
75. L. W. Weston, J. H. Todd, "Neutron capture and fission cross sections of plutonium-241," Nucl. Sci. Eng., 65, 454 (1978).
76. V. F. Gerasimov et al., JINR-E3-97-213, 384 (1997), [data were taken from EXFOR].
77. 241Am, LA-TR-71-74 (1971).
78. M. Ohta, S. Nakamura, H. Harada et al., "Measurement of effective capture cross section of americium-243 for thermal neutrons," J. Nucl. Sci. Technol, 43, 1441 (2006).
79. 231Pa using LINAC-driven lead slowing-down spectrometer," Nucl. Sci. Eng., 139, 273 (2001).
80. 250Cm from 0.1 eV to 80keV," Nucl. Sci. Eng., 109, 341 (1991).
81. 250,251Cf," Sov. At. Energy, 74, 69 (1993).