ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

Nuclear Data Sheets

Volumn 107, Issue 12, 2006, Pages 2931-3060

  Chadwick, M B ^a   Oblozinsky P ^b   Herman, M ^b   Greene, N M ^f   McKnight, R D ^c   Smith, D L ^c   Young, P G ^a   MacFarlane, R E ^a   Hale, G M ^a   Frankle, S C ^a   Kahler, A C ^a,l   Kawano, T ^a   Little, R C ^a   Madland, D G ^a   Moller, P ^a   Mosteller, R D ^a   Page, P R ^a   Talou, P ^a   Trellue, H ^a   White, M C ^a   Wilson, W B ^a   Arcilla, R ^b   Dunford, C L ^b   Mughabghab, S F ^b   Pritychenko, B ^b   Rochman, D ^b   Sonzogni, A A ^b   Lubitz, C R ^d   Trumbull, T H ^d   Weinman, J P ^d   Brown, D A ^e   Cullen, D E ^e   Heinrichs, D P ^e   McNabb, D P ^e   Derrien, H ^f   Dunn, M E ^f   Larson, N M ^f   Leal, L C ^f   Carlson, A D ^g   Block, R C ^h   Briggs, J B ⁱ   Cheng, E T ^j   Huria, H C ^k   Zerkle, M L ^l   Kozier, K S ^m   Courcelle, A ⁿ   Pronyaev, V ^o   van der Marck, S C ^p   more..

^a LOS ALAMOS NATIONAL LABORATORY   (United States)

^b BROOKHAVEN NATIONAL LABORATORY   (United States)

^c ARGONNE NATIONAL LABORATORY   (United States)

^d Knolls Atomic Power Laboratory   (United States)

^e LAWRENCE LIVERMORE NATIONAL LABORATORY   (United States)

^f OAK RIDGE NATIONAL LABORATORY   (United States)

^g NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY   (United States)

^h RENSSELAER POLYTECHNIC INSTITUTE   (United States)

ⁱ IDAHO NATIONAL LABORATORY   (United States)

^j TSI Research Inc   (United States)

^k WESTINGHOUSE ELECTRIC COMPANY   (United States)

^l BETTIS ATOMIC POWER LABORATORY   (United States)

^m ATOMIC ENERGY OF CANADA LIMITED   (Canada)

ⁿ Centre d'Études Nucléaires de Cadarache   (France)

^o INSTITUTE OF PHYSICS AND POWER ENGINEERING   (Russian Federation)

^p NUCLEAR RESEARCH AND CONSULTANCY GROUP NRG   (Netherlands)

more..

Author keywords

[No Author keywords available]

Indexed keywords

BENCHMARKING; CRITICALITY (NUCLEAR FISSION); FISSION PRODUCTS; GROUP THEORY; LIBRARIES; NEUTRON SCATTERING; NEUTRONS; PHOTONS; URANIUM; WAVE FUNCTIONS;

CRITICAL ASSEMBLY; ENDF/B-VI; ENDF/B-VII.0; EVALUATED NUCLEAR DATA FILE; NEUTRON REACTIONS; NUCLEAR DATA LIBRARY; NUCLEAR SCIENCE AND TECHNOLOGY; TECHNOLOGY APPLICATION; THERMAL; WORKING PARTIES;

ISOTOPES;

EID: 33947156628     PISSN: 00903752     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nds.2006.11.001     Document Type: Article

References (297)

1. C. Dunford, "A CSEWG retrospective: 35th anniversary, Cross Section Evaluation Working Group," Tech. Rep. BNL-52675, Brookhaven National Lab, November 2001
2. CSEWG-Collaboration. Evaluated Nuclear Data File ENDF/B-VI.8. www.nndc.bnl.gov/endf released in October 2001
3. C. Dunford, "Some CSEWG recollections," Tech. Rep. In Report BNL-52675 [1], p.29, Brookhaven National Lab, November 2001
4. M. Herman (editor), "ENDF-6 Formats Manual: Data Formats and Procedures for the Evaluated Nuclear Data File ENDF/B-VI and ENDF/B-VII," Tech. Rep. BNL-NCS-44945-05-Rev, Document ENDF-102, Brookhaven National Lab, June 2005
5. M. Chadwick, P. Obložinský, A. Blokhin, T. Fukahori, Y. Han, Y.-O. Lee, M. Martins, S. Mughabghab, V. Varlamov, B. Yu, and J. Zhang, "Handbook on Photonuclear Data for Applications: Cross-sections and Spectra," Tech. Rep. IAEA-TECDOC-1178, International Atomic Energy Agency, October 2000
6. x in ENDF-6 format and as ACE library for MCNP(X) codes," report INDC(NDS)-0470, IAEA, April 2005
7. V.G. Pronyaev, S.A. Badikov, A.D. Carlson, Z. Chen, E.V. Gai, G.M. Hale, F.-J. Hambsch, H.M. Hofmann, N.M. Larson, D.L. Smith, S.-Y. Oh, S. Tagesen, and H. Vonach, "An international evaluation of the neutron cross section standards," tech. rep., International Atomic Energy Agency, 2006. to be published as an IAEA Technical Report
8. "SCALE: A modular code system for performing standardized computer analysis for licensing evaluation." NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/R6), Vols. I, II, and III, May 2000. Available from the Radiation Safety Information Computational Center at Oak Ridge National Lab as CCC-545, 2000
9. R.E. MacFarlane and D.W. Muir, "The NJOY nuclear data processing system, version 91," Tech. Rep. LA-12740-M, Los Alamos National Lab, NM, 1994
10. R. MacFarlane, "NJOY nuclear data processing code, version 2006." Nuclear Data Sheets, to be published
11. RSICC. Webpage, Radiation Safety Information Computational Center (2006). www-rsicc.ornl.gov
12. NEA. Webpage, Nuclear Energy Agency Data Bank (2006). www.nea.fr/html/databank/
13. LANL, "Webpage, T-2 Information Service, Los Alamos National Lab." t2.lanl.gov, 2006
14. K. Kosako, "Covariance Data Processing Code: ERRORJ," in the Specialists' Meeting of Reactor Group Constants (J. Katakura, ed.), JAERI, Tokai, Japan, February 22-23, 2001. JAERI-Conf 2001-009
15. D. Wiarda and M. Dunn, "PUFF-IV: Code System to Generate Multigroup Covariance Matrices from ENDF/B-VI Uncertainty Files." Oak Ridge National Lab, Radiation Safety Information Computational Center (RSICC) Code Package PSR-534, 2006
16. M. Dunn and N. Greene, "AMPX-2002: A Cross Section Processing System for Generating Nuclear Data for Criticality Safety Applications," Tech. Rep. Trans. Am. Nucl. Soc., ORNL, 2002
17. Dunford C. ENDF Utility Codes, version 7.02 (2005). www.nndc.bnl.gov/nndcscr/endf/endf-util-7.02/
18. X5-MCNP-Team, "MCNP - A General Monte Carlo N-Particle Transport Code, Version 5, Volume I: Overview and Theory," Tech. Rep. LA-UR-03-1987, Los Alamos National Lab, April 2003
19. J. Briesmeister et al., "MCNP - A general Monte Carlo N-particle transport code, version 4C," Tech. Rep. LA-13709-M, Los Alamos National Lab, 2000
20. MCNPX Transport Code for Charged Particles (2006). mcnpx.lanl.gov
21. Pritychenko B., et al. Nuclear reaction and structure data services of the National Nuclear Data Center. Ann. Nucl. Energy 33 (2006) 390
22. P.G. Young, E.D. Arthur, and M.B. Chadwick, "Comprehensive nuclear model calculations: Introduction to the theory and use of the GNASH code," Tech. Rep. LA-12343-MS, Los Alamos National Lab, Los Alamos, 1992
23. P.G. Young and E.D. Arthur, "GNASH: A preequilibrium statistical nuclear model code for calculations of cross sections and esmission spectra," Tech. Rep. LA-6947, Los Alamos National Lab, Los Alamos, 1977
24. Young P.G., Arthur E.D., and Chadwick M.B. Comprehensive nuclear model calculations: Theory and use of the GNASH code. In: Gandini A., and Reffo G. (Eds). Proc. of the IAEA Workshop on Nuclear Reaction Data and Nuclear Reactors - Physics, Design, and Safety. (Singapore), Trieste, Italy, April 15 - May 17, 1996 (1998), World Scientific Publishing, Ltd. 227-404
25. Herman M., Obložinský P., Capote R., Sin M., Trkov A., Ventura A., and Zerkin V. Recent developments of the nuclear reaction model code EMPIRE. In: Haight R., Chadwick M., Kawano T., and Talou P. (Eds). Proc. of the Inter. Conf. on Nuclear Data for Science and Technology. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 1184
26. Herman M. Recent extensions and use of the statistical model code EMPIRE-II - version: 2.17 Millesimo. In: Herman M., Paver N., and Stanculescu A. (Eds). Accelerator Driven Systems for Energy Production and Waste Incineration: Physics, Design and Related Nuclear Data. ICTP Lecture Notes vol. 12 (2002), ICTP, Trieste 271-326
27. Herman M. EMPIRE-II statistical model code for nuclear reaction calculations. In: Paver N., Herman M., and Gandini A. (Eds). Nuclear Reaction Data and Nuclear Reactors. ICTP Lecture Notes vol. 5 (2001), ICTP, Trieste 137-230
28. Herman M., Capote R., Carlson B., Obložinský P., Sin M., Trkov A., and Zerkin V. EMPIRE nuclear reaction model code, version 2.19 (Lodi) (March 2005). www.nndc.bnl.gov/empire219/
29. J. Raynal, Notes on ECIS. CEA-N-2772, Commissariat à l'Energie Atomique, 1994
30. G.M. Hale, "Use of R-matrix methods for light element evaluations," in Proc. of the Conference on Nuclear Data Evaluation Methods and Procedures (B. Magurno and S. Pearlstein, eds.), pp. 509-531, Brookhaven National Lab, Upton, NY, BNL-NCS-51363, 1981
31. N.M. Larson, "Updated users' guide for SAMMY: Multilevel R-matrix fits to neutron data using Bayes' equations," Tech. Rep. ORNL/TM-9179/R7, Document ENDF-364, Oak Ridge National Lab, TN, 2006.
32. S. Oh, J. Chang, and S.F. Mughabghab, "Neutron cross section evaluations of fission products below the fast neutron region," Tech. Rep. BNL-NCS-67469, Brookhaven National Lab., 2000
33. Mughabghab S.F. Atlas of Neutron Resonances: Thermal Cross Sections and Resonance Parameters (2006), Elsevier, Amsterdam
34. Hofmann H.M. Models and methods in few-body physics. In: Ferreira L.S., et al. (Ed). Models and Methods in Few-Body Physics. Lecture Notes in Physics vol. 273 (1987), Springer, Heidelberg
35. 4He system. Nuclear Physics A 613 (January 1997) 69-106
36. A. Ignatyuk, P. Obložinský, M. Chadwick, T. Fukahori, S. Kailas, G. Molnar, G. Reffo, Z. Su, M. Uhl, and P. Young, "Handbook for calculations of nuclear reaction data: Reference Input Parameter Library," Technical report IAEA-TECDOC-1034, International Atomic Energy Agency, Vienna, Austria, 1998
37. P. Young, M. Herman, P. Obložinský, T. Belgya, O. Bersillon, R. Capote, T. Fukahori, G. Zhigang, S. Goriely, A. Ignatyuk, S. Kailas, A. Koning, and V. Plujko, "Handbook for calculations of nuclear reaction data, RIPL-2," TECDOC-1506, IAEA, Vienna, 2006
38. N. Larson and K. Volev, "Validation of multiple-scattering corrections in the analysis code SAMMY," in Inter. Conf. on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing (Physor 2002), p. A0203, Seoul, South Korea, 2002
39. N. Larson, "On the efficient treatment of data covariance matrices," in 71st Annual Meeting of the Southeastern Section of the APS, Oak Ridge, TN, November 11 - 13, 2004, Amer. Inst. of Physics
40. Larson N. Treatment of data uncertainties. In: Haight R., Chadwick M., Kawano T., and Talou P. (Eds). Proc. of the Inter. Conf. on Nuclear Data for Science and Technology. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 374
41. F. Fröhner, B. Goel, and U. Fischer, "FITACS computer code," Tech. Rep. Report ANL-83-4, p.116, Kernforschungszentrum Karslruhe, 1982. Note: Presented at Specialists' Meeting on Fast Neutron Capture Cross Sections, ANL
42. Mughabghab S.F., Divadeenam M., and Holden N.E. Neutron Cross Sections: Z = 1-60, vol. 1A (1981), Academic Press, New York
43. Mughabghab S.F. Neutron Cross Sections: Z = 61-100, vol. 1B (1984), Academic Press, New York
44. M. Herman et al., "Neutron reaction evaluation methodology at the NNDC," under preparation
45. 64Zn + n. Phys. Rev. C 23 (1981) 671
46. 238U. Phys. Rev. 171 (1968) 1293
47. S.T. Perkins and G.E. Gyulassy, "An Integrated System for Production of Neutronics and Photonics Calculational Constants," Tech. Rep. UCRL-50400, Vol. 12, Univ. of California, 1972
48. Porter C.E., and Thomas R.G. Fluctuations of Nuclear Reaction Widths. Phys. Rev. 104 (Oct 1956) 483-491
49. Axel P. Electric dipole ground state transition width strength function and 7 MeV photon interaction. Phys. Rev. 126 (1962) 671
50. D.M. Brink, Unpublished. D. Phil. thesis, Oxford University, 1955
51. Kopecky J., and Uhl M. Test of gamma-ray strength functions in nuclear-reaction model-calculations. Phys. Rev. C 41 (1990) 1941-1955
52. Mughabghab S.F., and Dunford C.L. A dipole-quadrupole interaction term in E1 photon transitions. Phys. Lett. B 487 (2000) 155
53. V. Plujko and M. Herman, Handbook for calculations of nuclear reaction data, RIPL-2, ch. Chapter 7: Gamma-ray strength functions, p. 120. No. in press, IAEA, Vienna, 2006
54. Moldauer P.A. Evaluation of the fluctuation enhancement factor. Phys. Rev. C 14 (Aug 1976) 764-766
55. Hofmann H.M., Richert J., Tepel J.W., and Weidenmüller H.A. Direct reactions and Hauser-Feshbach theory. Ann. Phys. 90 (1975) 403
56. Nishioka H., Verbaarschot J.J.M., Weidenmüller H.A., and Yoshida S. Statistical theory of precompound reactions: The multistep compound process. Ann. Phys. 172 (1986) 67
57. C. Dunford, "Compound nuclear analysis programs COMNUC and CASCADE," Tech. Rep. T1-707-130-013, Atomics International, 1971
58. Hofmann H.M., Mertelmeier T., Herman M., and Tepel J.W. Calculation in the Presence of Weakly Absorbing Channels with Special Reference to the Elastic Enhancement Factor and Factorization Assumption. Z. Physik A 297 (1980) 153
59. Gadioli E., and Hodgson P.E. Pre-Equilibrium Nuclear Reactions (1992), Oxford University Press, Oxford, UK
60. Kalbach C. Systematics of continuum angular distributions: Extensions to higher energies. Phys. Rev. C 37 (1988) 2350-2370
61. Feshbach H., Kerman A., and Koonin S. The statistical theory of multi-step compound and direct reactions. Ann. Phys. (N.Y.) 125 (1980) 429-476
62. E. Běták and P. Obložinský, "Code PEGAS: Preequilibrium exciton model with spin conservation and gamma emission," Tech. Rep. INDC(SLK)-001, IAEA/Slovak Academy of Sciences, 1993. Note: DEGAS is an extended version of the code PEGAS using two-parameteric p-h level densities
63. Blann M. New precompound decay model. Phys. Rev. C 54 (1996) 1341
64. Blann M., and Chadwick M.B. New precompound model: Angular distributions. Phys. Rev. C 57 (1998) 233
65. Blann M., and Chadwick M.B. Precompound Monte-Carlo model for cluster induced reactions. Phys. Rev. C 6203 (2000) 4604
66. Chadwick M.B., Young P.G., George D.C., and Watanabe Y. Multiple preequilibrium emission in Feshbach-Kerman-Koonin analyses. Phys. Rev. C 50 (Aug 1994) 996
67. Tamura T., Udagawa T., and Lenske H. Multistep direct reaction analysis of continuum spectra in reactions induced by light ions. Phys. Rev. C26 (1982) 379
68. Herman M., Reffo G., and Weidenmüller H.A. Multistep-compound contribution to precompound reaction cross section. Nucl. Phys. A536 (1992) 124
69. Kalbach C., and Mann F.M. Phenomenology of continuum angular distributions. I. Systematics and parametrization. Phys. Rev. C 23 (Jan 1981) 112-123
70. Iwamoto A., and Harada K. Mechanism of cluster emission in nucleon-induced preequilibrium reactions. Phys. Rev. C 26 (Nov 1982) 1821-1834
71. Sato K., Iwamoto A., and Harada K. Pre-equilibrium emission of light composite particles in the framework of the exciton model. Phys. Rev. C 28 (Oct 1983) 1527-1537
72. J.S. Zhang and X.G. Shi et al., "The Formulation of UNIFY Code for the Calculation of Fast Neutron Data for Structural Materials," Report INDC(CPR)-014, IAEA, Vienna, 1989
73. J.S. Zhang et al., "Formation and Emission of Light Particles in Fast Neutron-induced Reaction - A Unified Compound Pre-equilibrium Model," Report INDC(NDS)-193, IAEA, Vienna, 1988. p. 21
74. Madland D.G., and Nix J.R. New calculation of prompt fission neutron-spectra and average prompt neutron multiplicities. Nucl. Sci. and Eng. 81 (1982) 213-271
75. NRDC-Network. CSISRS/EXFOR library of experimental cross sections (2006). www.nndc.bnl.gov/exfor
76. 235U to increase epithermal alpha and k1," in Proc. of the Inter. Conf. on Nuclear Data for Science and Technology, Gatlinburg, USA, 1994
77. H. Weigmann, J. Hambsch, W. Mannhart, Mamoru Baba, Liu Tingjin, N. Kornilov, D. Madland, and P. Staples, "Fission neutron spectra of uranium-235," Report NEA/WPEC-9, OECD, 2003
78. Boykov G., et al. Sov. J. Nucl. Phys. 53 (1991) 392
79. 225U(n, 2n) Cross Section: Preliminary Calculations," Tech. Rep. UCRL-ID-137718, Lawrence Livermore National Lab, CA, 1999
80. 235U," in PHYSOR Conference, Chicago, Illinois, April 25-29, 2004
81. 238U," in Proc. of the Inter. Conf. on Nuclear Data for Science and Technology, (Mito, Japan), JAERI, 1988
82. 235U from Transmission Measurements in the Energy Range 2 keV to 300 keV and Statistical Model Analysis of the Data," tech. rep., Oak Ridge National Lab, 2000
83. 239Pu. Nucl. Sci. Eng. 88 (1984) 567
84. 235U at keV Neutron Energies. Nucl. Sci. Eng. 20 (1964) 80
85. López Jiménez M., Morillon B., and Romain P. Overview of Recent Bruyères-le-Châtel Actinide Evaluations. In: Haight R., Chadwick M., Kawano T., and Talou P. (Eds). Proc. of the Inter. Conf. on Nuclear Data for Science and Technology. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 314-316
86. 239Pu," Tech. Rep. JEFDOC-17, NEA, JEFF project, 2000
87. Baba M., Wakabayashi H., Ito N., Maeda K., and Hirakawa N. Measurement of double-differential neutron emission spectra from uranium-238. J. Nucl. Sci. Tech. 27 (1990) 601-616
88. G. Lovchikova et al. XIV international Workshop on Nuclear Fission Physics, 2000
89. Ethvignot T., et al. Phys. Lett. B 575 (2003) 221
90. 238U capture and related cross sections," Tech. Rep. WPEC/SG4, NEA Paris
91. J.B. Briggs et al., "International handbook of evaluated criticality safety benchmark experiments," Tech. Rep. NEA/NSC/DOC(95)04/I, Nuclear Energy Agency, Paris, France, 2004. The 2006 Edition of the ICSBEP Handbook is available on DVD media and can be requested from a link on the http://icsbep.inl.gov/handbook.shtml website
92. 238U," Tech. Rep. NEANDC-313U, OECD Nuclear Energy Agency, Paris, 1994
93. Courcelle A. First conclusions of the WPEC Subgroup-22. In: Haight R., Chadwick M., Kawano T., and Talou P. (Eds). Proc. of the Inter. Conf. on Nuclear Data for Science and Technology. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 462-467
94. 238U Resonance Parameters from 0 to 20 keV. In: Haight R., Chadwick M., Kawano T., and Talou P. (Eds). Proc. of the Inter. Conf. on Nuclear Data for Science and Technology. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 276-281
95. de Saussure G. Measurement of the Uranium-238 Capture Cross Section for Incident Neutron Energies up to 100 keV. Nucl. Sci. Eng. 5 (1973) 385
96. Olsen D.K., de Saussure G., Perez R.B., Silver E.G., Difilippo F., Ingle R.W., and Weaver H. Precise Measurement and Analysis of Neutron Transmission Through Uranium-238. Nucl. Sci. Eng. 62 (1977) 479
97. Olsen D.K. Measurement and resonance analysis of neutron transmission through Uranium-238. Nucl. Sci. Eng. 479 (1979) 202-222
98. 238U Neutron Capture Yield in the Energy Region Between 1 and 100 keV," in Proc. of the Inter. Conf. on Nuclear Data for Science and Technology, (Mito, Japan), JAERI, 1988
99. 239Np decay. Nucl. Sci. Eng. 150 (2005) 336-348
100. 238U. Nucl. Sci. Eng. 103 (1988) 119-128
101. Staples P., et al. Nucl. Phys. A 591 (1995) 41-60
102. 241Am (n,2n) cross section measurements near 14 MeV," Tech. Rep. UCRL-ID-145592, Lawrence Livermore National Lab, CA, 2001
103. 239Pu(n, 2n) cross section," Tech. Rep. Memorandum T-16-MBC00/10, Los Alamos National Lab, Los Alamos (2000), October 2, 2000
104. Bernstein L.A., Becker J.A., Garrett P.E., Younes W., McNabb D.P., Archer D.E., McGrath C.A., Chen H., Ormand W.E., Stoyer M.A., Nelson R.O., Chadwick M.B., Johns G.D., Wilburn W.S., Devlin M., Drake D.M., and Young P.G. Phys. Rev. C6502 (2002) 1601
105. 233U in the Neutron Energy Range from Thermal to 600 eV," Tech. Rep. ORNL/TM-2000, ENDF-365, Oak Ridge National Lab, Oak Ridge, TN, 2001
106. 233U from 600 eV to 40 keV. Trs. Am. Nucl. Sci. 92 (2005)
107. 233U Using a Cooled Sample at the Temperature T = 11°K. Nucl. Sci. Eng. 139 (2001) 111-117
108. 233U in the Energy Region 0.4 to 2000 eV. Nucl. Sci. Eng. 34 (1968) 1-12
109. 239Pu. Nucl. Sci. Eng. 12 (1962) 169-177
110. Younes W., and Britt H.C. Neutron-induced fission cross sections simulated from (t,pf) results. Phys. Rev. C 67 2 (2003) 024610
111. Plettner C., Ai H., Beausang C.W., Bernstein L.A., Ahle L., Amro H., Babilon M., Burke J.T., Caggiano J.A., Casten R.F., Church J.A., Cooper J.R., Crider B., Gurdal G., Heinz A., McCutchan E.A., Moody K., Punyon J.A., Qian J., Ressler J.J., Schiller A., Williams E., and Younes W. Estimation of (n,f) cross sections by measuring reaction probability ratios. Phys. Rev. C 71 5 (2005) 051602
112. 241Pu neutron cross-sections in the thermal to 300-ev energy range. Nuc. Sci. Eng. 106 (1990) 415-433
113. 241Pu. In: Qaim S. (Ed). Proc. Nuclear Data for Science and Technology. Jülich, Germany, May 13-17, 1991 (1992), Springer-Verlag
114. 241Pu Reich-Moore resonance parameters by comparison with recent fission cross-section measurements," tech. rep., JAERI, 1994
115. C. Chabert, A. Santamarina, and P. Bioux, "Trends in nuclear data derived from integral experiments in thermal and epithermal reactors," in Proc. of the Inter. Conf. on Nuclear Data for Science and Technology, Tsukuba, 2002
116. 241Pu resonance parameters in the energy range thermal to 20 eV. Nuc. Sci. Eng. 150 (2005) 109-114
117. Rochman D., Herman M., and Obložinský P. Modeling and fission cross sections for Americium. Nucl. Sci. Eng. 154 (2006) 280
118. P. Talou, T. Kawano, P. Young, M. Chadwick, and R. MacFarlane, "Improved evaluations of neutron-induced reactions on Americium isotopes," accepted for publication in Nucl. Sci. Eng., 2006
119. 240,241,242,242m,243,244,244mAm isotopes," Livermore Report UCRL-TR-201913, LLNL, 2004
120. S. Ohki, K. Yokoyama, K. Numata, and T. Jin, "Target accuracy of Am nuclear data and progress in validation by post irradiation experiments with the fast reactor JOYO," in Proc. of the 2003 Symposium on Nuclear Data, p. 40, 2004. Nov. 27-28, 2003, JAERI, Tokai, Japan
121. 241Am(n,2n) reaction cross sections using the activation method. Phys. Rev. C 73 (2006) 067601
122. Bjornholm S., and Lynn J.E. The double-humped fission barrier. Rev. Mod. Phys. 52 (1980) 725
123. A. Trkov, "2nd IAEA Research Co-ordination Meeting on Evaluated Nuclear Data for Thorium-Uranium Fuel Cycle," Technical report INDC(NDS)-447, IAEA, Vienna, 2003
124. A. Trkov, "Evaluated Nuclear Data for Th-U Fuel Cycle Summary Report of the Third Research Coordination Meeting," Technical report INDC(NDS)-494, IAEA, Vienna, 2006
125. 232Th in the energy range 0 to 4 keV," technical report, Oak Ridge National Lab, 2006. In preparation
126. 232Th from 8 MeV to 4 keV," Report ORNL/TM-7661(ENDF-307), Oak Ridge National Lab, 1981
127. G. Morogovskij and L.A. Bakhanovich, "Evaluation of the resolved resonance region for Pa-233," Series: Nuclear Constants, no. 1-2, 2003. Translated in INDC(CCP)-440, International Atomic Energy Agency, Vienna September 2004
128. 232Th: Evaluation of the average resonance parameters and their covariances in the unresolved resonance region from 4 to 100 keV." Private Communication, September 2006
129. 231Pa," Technical report INDC(BLR)-19, IAEA, Vienna, 2004
130. 233Pa," Tech. Rep. INDC(BLR)-20, IAEA, Vienna, 2004
131. 231,233Pa up to 60 MeV." to be published
132. Sin M., Capote R., Herman M., Obložinský P., Ventura A., and Trkov A. Improvement of the fission channel in the EMPIRE code. In: Haight R., Chadwick M., Kawano T., and Talou P. (Eds). Proc. of the Inter. Conf. on Nuclear Data for Science and Technology. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 1249
133. 232Th up to 200 MeV. Phys. Rev. C 72 (2005) 024604
134. Hauser W., and Feshbach H. The inelastic scattering of neutrons. Phys. Rev. 87 (1952) 366-373
135. 231Pa(n,f) reactions. Phys. Rev. C 74 1 (2006) 014608
136. 232Th measured at the n-TOF facility at CERN in the unresolved resonance region up to 1 MeV. Phys. Rev. C 73 (2006) 054610
137. 232Th cross sections for the energy range up to 150 MeV." Provided to the IAEA CRP on Th-U cycle, 2006
138. 232Th evaluated nuclear data through benchmark experiments," in Proc. of the Inter. Conf. on Nuclear Energy for New Europe 2006, Portorož, Slovenia, September 18-21, 2006, to be published
139. 239Pu. Nucl. Phys. A772 (2006) 113
140. ICRU-Report-63, in Nuclear Data for Neutron and Proton Radiotherapy and for Radiation Protection, Bethesda, MD: International Commission on Radiation Units and Measurements, 2000
141. D. Muir, "Gamma rays, Q-values and kerma factors," Tech. Rep. LA-6258-MS, Los Alamos National Lab, Los Alamos, 1976
142. J. Rowlands, "The incident neutron energy dependence of the prompt energy yield in fission," SERCO document CCU0516 SA/NST/17729/W001, Issue 2, August 2006
143. G. Rudstam, P. Fink, A. Filip, A. D'Angelo, and R. McKnight, "Delayed neutron data for the major actinides," Tech. Rep. NEA/WPEC-6, Paris, 2002
144. Kratz K.-L., and Herrmann G. Systematics of neutron emission probabilities from delayed neutron precursors. Z. Physik 363 (1973) 435-442
145. Mann F., Dunn C., and Schenter R. Beta decay properties using a statistical model. Phys. Rev. C25 (1982) 524-526
146. M. Brady, "Evaluation and application of delayed neutron precursor data," Tech. Rep. LA-11534-T, Los Alamos National laboratory, Los Alamos, 1989
147. 239Pu(n, xn) excitation function," Tech. Rep. LA-UR-94-3106 ENDF-349, Los Alamos National laboratory, Los Alamos, 1993
148. Wilson W., and England T. Delayed neutron study using ENDF/B-VI basic nuclear data. Prog. Nucl. Energy 41 (2002) 71-107
149. Pfeiffer B., Kratz K.-L., and Moller P. Status of delayed-neutron data: half-lives and neutron emission probabilities. Prog. Nucl. Energy 41 (2002) 39-69
150. Audi G., Bersillon O., Blachot J., and Wapstra A. The NUBASE evaluation of nuclear and decay properties. Nucl. Phys. A729 (2003) 3
151. Moller P., Pfeiffer B., and Kratz K.-L. New calculations of gross beta decay properties for astrophysical applications: Speeding up the classical r-process. Phys. Rev. C67 (2003) 055802
152. Moller P., Nix J.R., Myers W.D., and Swiatecki W.J. Nuclear ground-state masses and deformations. Atomic Data Nucl. Data Tables 59 (1995) 185-381
153. Moller P., Nix J., and Kratz K.-L. Nuclear properties for astrophysical and radioactive-ion-beam applications. At. Data Nucl. Data Tables 66 (1997) 131
154. Brady M., and England T. Delayed neutron data and group parameters for 43 fissioning systems. Nucl. Sci. Eng. 103 (1989) 129-149
155. Keepin G.R. Physics of Neutron Kinetics (1965), Addison-Wesley, New York
156. Conant J., and Palmedo P. Delayed neutron data. Nuc. Sci. Eng. 44 (1971) 173
157. Tuttle R. Delayed neutron data. Nuc. Sci. Eng. 56 (1975) 37
158. Ohsawa T., and Oyama T. Possible fluctuations in delayed neutron yields in the resonance region of U-235. In: Katakura J. (Ed). Proc. of the Specialists' Meeting on Delayed Neutron Nuclear Data. (Tokai-mura, Nagakun, Ibaraki-ken, Japan), JAERI (1999), Amer. Inst. of Physics 43
159. 239Pu. Nuc. Sci. Eng. 148 (2004) 50
160. Nakajima K. Re-evaluation of the effective delayed neutron fraction measured by the substitution technique for a light water moderated low-enriched uranium core. J. Nucl. Sci. Techn. 38 (2001) 1120-1125
161. Sakurai T., and Okajima S. Adjustment of delayed neutron yields in jendl-3.2. J. Nuc. Sci. Tech. 39 (2002) 19-30
162. Analyzed β-effective in the JAERI Tank Critical Assembly (TCA, 2.6% enriched) and recommended 0.01586 ± 1.8%, the value adopted for JENDL-3.3
163. S. van der Marck, "Benchmarking ENDF/B-VII beta1." CSEWG 2005 meeting report, www.nndc.bnl.gov/csewg/, 2005. Analyzed TCA, IPEN/MB-01, Stacy, Winco, and Proteus thermal β-effective measurements and found JENDL-3.3 to be superior to ENDF/B-VI.8
164. Y. Chao. Westinghouse, Private Communication, 2006
165. M. Brady. PNNL, Private Communication, 2006
166. Pruet J., Descalle M.-A., Hall J., Pohl B., and Prussin S. Neutron and photon transport in sea-going cargo containers. J. Appl. Phys. 97 (2005) 094908
167. Pruet J., Hall J., Descalle M.-A., and Prussin S. Monte Carlo models for the production of β-delayed gamma-rays following fission of special nuclear materials. Nuclear Instruments and Methods B 222 (2004) 403
168. D. Brown, J. Pruet, G. Hedstrom, J. Hall, and M.-A. Descalle, "Proposal for ENDF formats that describe emission of post-fission β-delayed photons," Report UCRL-TR-206607, Lawrence Livermore National Lab, 2004
169. 239Pu into ENDF format," Tech. Rep. UCRL-TR-223148, Lawrence Livermore National Lab, 2006
170. R.Q. Wright and R.E. MacFarlane, "Review of ENDF/B-VI fission-product cross sections," Tech. Rep. ORNL/TM-13723, Oak Ridge National Lab, Oak Ridge, TN, 2000
171. Obložinský P., et al. WPEC Subgroup 23: Creation of neutron cross section library for fission products (2006). www.nndc.bnl.gov/sg23
172. M.D. DeHart, "Sensitivity and parametric evaluations of significant aspects of burnup credit for PWR spent fuel packages," Tech. Rep. ORNL/TM-12973, Oak Ridge National Lab, 1995
173. Y.D. Lee, J. Chang, and P. Obložinský, "Neutron cross section evaluations of fission products in the fast energy region," in Proc. of the Inter. Conf. on Nuclear Data for Science and Technology, p. 168, Tsukuba, 2002
174. Lee Y.D., and Chang J.H. Fission product evaluations for the selected nuclei. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 378
175. H.-I. Kim, Y.-O. Lee, M. Herman, S.F. Mughabghab, P. Obložinský, and D. Rochman, "New ENDF/B-VII.0 Evaluation of Neutron Cross Sections on 32 Fission Products," Tech. Rep. under preparation, Brookhaven National Lab
176. 99Tc neutroninduced cross sections for the ENDF/B-VII.0 library," Tech. Rep. BNL-75892-2006-JA-R1, Brookhaven National Lab, 2006
177. Iwamoto O., Herman M., Mughabghab S., and Obložinský P. Neutron cross-section evaluations for 70,72,73,74,76-Ge. In: Haight R., Chadwick M., Kawano T., and Talou P. (Eds). Proc. of the Inter. Conf. on Nuclear Data for Science and Technology. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 434
178. D. Rochman et al., "Evaluation of neutron induced reactions on 8 isotopes of Gd for ENDF/B-VII.0," Tech. Rep. under preparation, Brookhaven National Lab
179. D. Rochman, M. Herman, P. Obložinský, S. Mughabghab, T. Kawano, and L. Leal, "Evaluation of covariance data for Gd isotopes." under preparation
180. G. Leinweber et al., "Neutron capture and transmission measurements and resonance parameter analysis of gadolinium," Nucl. Sci. Eng., November 2006. See also Report LM-05K107, June 2005
181. 103Rh, Private communication, 2006
182. Capote R., Soukhovitskii E.S., Quesada J.M., and Chiba S. Is a global coupled-channel dispersive optical model potential for actinides feasible?. Phys. Rev. C 72 6 (2005) 064610
183. 232Th up to 200 MeV. Phys. Rev. C 72 2 (2005) 024604
184. Obložinský P., et al. WPEC Subgroup 21: Assessment of neutron cross section evaluations for fission products (2005). www.nndc.bnl.gov/sg21
185. P. Obložinský, M. Herman, S. Mughabghab, I. Sirakov, J. Chang, T. Nakagawa, K. Shibata, M. Kawai, A. Ignatyuk, V. Pronyaev, V. Zerkin, S. Qingbiao, and Z. Youxiang, "Assessment of neutron cross-section evaluations for the bulk of fission products," Tech. Rep. NEA/WPEC-21, OECD Nuclear Energy Agency, Paris, 2005
186. Chadwick M.B., Young P.G., Chiba S., Frankle S., Hale G.M., Hughes H.G., Koning A.J., Little R.C., MacFarlane R.E., Prael R.E., and Waters L.S. Cross section evaluations to 150 MeV for accelerator-driven systems and implementation in MCNPX. Nucl. Sci. Eng. 131 (1999) 293-328
187. Cokinos D., and Melkonian E. Measurement of the 2200 m/sec neutron-proton capture cross section. Phys. Rev. C15 (1977) 1636
188. Schoen K., et al. Precision neutron interferometric measurements and updated evaluations of the n-p and n-d coherent neutron scattering lengths. Phys. Rev. C 67 (2003) 044005
189. Houk T.L. Neutron-proton scattering cross section at a few electron Volts and charge independence. Phys. Rev. C3 (1971) 1886
190. Dilg W. Measurement of the neutron-proton total cross section at 132 eV. Phys. Rev. C11 (1975) 103
191. n = 10 MeV. Phys. Rev. C65 (2002) 014004
192. Buerkle W., and Mertens G. Measurement of the neutron-proton differential cross section at 14.1 MeV. Few Body Systems 22 (1997) 11
193. 3He scattering. Phys. Rev. C42 (1990) 438
194. 51V(n, np+pn) and (n, t) cross sections for the ENDF/B-VII library. Fusion Engineering and Design 81 (August 2006) 2109-2113
195. 93Nb. Phys. Rev. C 17 (1978) 508
196. Kokoo O., Murata I., and Takahashi A. Measurements of double-differential cross sections of charged-particle emission reactions for several structural elements of fusion power reactors by 14.1-MeV incident neutrons. Nuclear Science and Engineering 132 (1999) 16
197. Woelfle R., et al. Radiochimica Acta 50 (1990) 5
198. 193Ir and influence of spin distribution in the preequilibrium process. Nucl. Instr. Meth. 562 (2006) 774
199. Koning A.J., and Delaroche J.P. Local and global nucleon optical models from 1 keV to 200 MeV. Nucl. Phys. A713 (2003) 231
200. Koning A., Hilaire S., and Duijvestijn M. TALYS: Comprehensive nuclear reaction modeling. In: Haight R., Chadwick M., Kawano T., and Talou P. (Eds). Proc. of the Inter. Conf. on Nuclear Data for Science and Technology. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 1154-1159
201. Smith D.L. Probability, Statistics, and Data Uncertainties in Nuclear Science and Technology (1991), American Nuclear Society
202. rd Edition, ENDF/B-V Library
203. B. Magurno, R. Kinsey, and F. Scheffel, "Guidebook for the ENDF/B-V Nuclear Data Files," Tech. Rep. EPRI NP-2510, BNL-NCS-31451, ENDF-328, Brookhaven National Lab and Electric Power Research Institute, July 1982
204. Ishikawa M. Recent Application of Nuclear Data to Fast Reactor Core Analysis and Design in Japan. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 1405
205. Ishikawa M., Sugino K., Sato W., and Numata K. Development of a Unified Cross-section Set ADJ2000 Based on Adjustment Technique for Fast Reactor Analysis. J. Nucl. Sci. Technol. 1073 Suppl. 2 (2002)
206. P.F. Rose (editor), "ENDF-201: ENDF/B-VI Summary Documentation," Tech. Rep. BNL-NCS-17541, National Nuclear Data Center, BNL, October 1991. Note: For ENDF/B-VI.8 see www.nndc.bnl.gov/endf
207. K. Kosako and N. Yanano, "Preparation of a covariance processing system for the evaluated nuclear data file, JENDL," Tech. Rep. JNC TJ-9440, 99-003, JAERI, 1999. (in Japanese)
208. T. Kawano, T. Ohsawa, K. Shibata, and H. Nakashima, "Evaluation of Covariance for Fission Neutron Spectra," Tech. Rep. 99-009, JAERI, 1999. (in Japanese)
209. M. Williams, "Generation of Approximate Covariance Data." ORNL memo, August 2004
210. Wisshak K., Voss F., Käppeler F., Guber K., Kazakov L., Kornilov N., Uhl M., and Reffo G. Stellar neutron capture cross sections of the Gd isotopes. Phys. Rev. C 52 (Nov 1995) 2762-2779
211. 232Th Neutron Resonance Parameters in the Energy Range 0 to 4 keV," Tech. Rep. ORNL/TM-2006/53, Oak Ridge National Lab, 2006
212. D. Smith, "Covariance matrices for nuclear cross sections derived from nuclear model calculations," report ANL/NDM-159 November, Argonne National Lab, 2004
213. A. Trkov, "Summary report of the IAEA technical meeting," INDC(NDS)-471, IAEA, Vienna, 2005
214. R.E. MacFarlane, "New thermal neutron scattering files for ENDF/B-VI release 2," Tech. Rep. LA-12639-MS (1994), Los Alamos National Lab, Los Alamos, 1994
215. J. Koppel and D. Houston, "Reference manual for ENDF thermal neutron scattering data," report GA-8774 revised and reissued as ENDF-269 by the National Nuclear Data Center, General Atomic, July 1978
216. Keinert J., and Sax J. Investigation of neutron scattering dynamics in liquid hydrogen and deuterium for cold neutron sources. Kerntechnik 51 (1987) 19
217. Young J.A., and Koppel J.U. Slow neutron scattering by molecular hydrogen and deuterium. Phys. Rev. 135 (Aug 1964) A603-A611
218. Vineyard G.H. Frequency factors and isotope effects in solid state rate processes. J. of Physics and Chemistry of Solids 3 1-2 (1957) 121-127
219. Stedman R., Almqvist L., and Nilsson G. Phonon-frequency distributions and heat capacities of Aluminum and Lead. Phys. Rev. 162 (Oct 1967) 549-557
220. Brockhouse B.N., Abou-Helal H.E., and Hallman E.D. Lattice vibrations in iron at 296°K. Solid State Commun. 5 (1967) 211
221. W.P. Poenitz and S.E. Aumeier, "The simultaneous evaluation of the standards and other cross sections of importance for technology," Tech. Rep. ANL/NDM-139, Argonne National Lab, Argonne, IL, 1997
222. Hambsch F.-J., Carlson A.D., and Vonach H. Status of the neutron cross section standards database. In: Haight R., Chadwick M., Kawano T., and Talou P. (Eds). Proc. of the Inter. Conf. on Nuclear Data for Science and Technology. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 826-829
223. 252Cf. Nucl. Sci. Eng. 87 (1984) 381-404
224. 235U. Phys. Rev. A 35 (1987) 2810
225. n = 10 MeV. Phys. Rev. C 65 (2002) 014004
226. A.D. Carlson, G.M. Hale, and V. Pronyaev, "Summary report of the first research coordination meeting on improvement of the standard cross sections for light elements," Tech. Rep. INDC(NDS)-438, International Atomic Energy Agency, Vienna, 2003
227. W.P. Poenitz, "Data interpretation, objective, evaluation procedures and mathematical technique for the evaluation of energy-dependent ratio, shape and cross section data," in Proc. of the Conference on Nuclear Data Evaluation Methods and Procedures (B. Magurno and S. Pearlstein, eds.), pp. 249-289, Brookhaven National Lab, Upton, NY, BNL-NCS-51363, 1981
228. S. Chiba and D.L. Smith, "A suggested procedure for resolving an anomaly in least-squares data analysis known as Peelle's pertinent puzzle and the general implications for nuclear data evaluation," Tech. Rep. ANL/NDM-121, Argonne National Lab, Argonne, Illinois, 1991
229. A.D. Carlson, W.P. Poenitz, G.M. Hale, R.W. Peelle, D.C. Dodder, and C.Y. Fu, "The ENDF/B-VI neutron cross section measurement standards," Tech. Rep. ENDF-351, Brookhaven National Lab, National Nuclear Data Center, Upton, NY, 1993
230. 17O system. Atomic Energy Science and Technology 29 4 (1995) 366-371
231. Tagesen S., and Hetrick D.M. Enhancements to the generalized least-squares cross-section evaluation code GLUCS. In: Dickens J.K. (Ed). Proc. of the Inter. Conf. on Nuclear Data for Science and Technology. (La Grange Park, IL), Gatlinburg, TN, 1994 (1994), American Nuclear Society 589-591
232. 241Pu," Tech. Rep. JAERI-Research-2000-004, Japan Atomic Energy Research Institute, Tokai, Japan, 2000
233. Badikov S.A., Gai E.V., Guseynov M.A., and Rabotnov N.S. Nuclear data processing, analysis, transformation and storage with Pade-approximants. In: Qaim S. (Ed). Proc. Nuclear Data for Science and Technology. (New York, NY), Jülich, Germany, May 13-17, 1991 (1992), Springer-Verlag 182-187
234. 252Cf," Tech. Rep. CBNM (IRMM) Report GE/PH/01/86, IRMM, Geel, 1986
235. Maslov V.M. Uranium symmetric/asymmetric nucleon-induced fission up to 200 MeV. Eur. Phys. J. A 21 (2004) 281-286
236. J. Hardy. Private Communication, Memo dated 18 June, 1985
237. Dietrich S.S., and Berman B.L. Atlas of photonuetron cross sections obtained with monoenergetic photons. Atomic Data and Nuclear Data Tables 38 (1988) 199-338
238. E.G. Fuller and H. Gerstenberg, "Photonuclear data - abstract sheets 1955-1982," Tech. Rep. Reports of the US National Bureau of Standards, NBSIR 83-2742, vol. I-XV (1983-1986), National Institute for Standards and Technology, Gaithersburg, MD, 1983-1986
239. A.V. Varlamov, V.V. Varlamov, D.S. Rudenko, and M.E. Stepanov, "Atlas of giant dipole resonance paramaters and graphs of photonuclear reaction cross sections," Tech. Rep. INDC (NDS)-394 (1999), International Atomic Energy Agency, Vienna, Austria, 1999
240. Berman B.L., Pywell R.E., Dietrich S.S., Thompson M.N., McNeill K.G., and Jury J.W. Absolute photoneutron cross-sections for Zr, I, Pr, Au, and Pb. Phys. Rev. 36 (1987) 1286-1292
241. Wolynec E., Martinez A.R.V., Gouffon P., Miyao Y., Serrao V.A., and Martins M.N. Comment on photoneutron cross-sections. Phys. Rev. C 29 (1984) 1137-1139
242. 14N for Gamma Resonance Technology." Unpublished BNL report, December 2002
243. Ajzenberg-Selove F. Energy Levels of Light Nuclei A = 13-15. Nucl. Phys. A253 (1991) 1-196
244. Chadwick M.B., Young P.G., MacFarlane R.E., White M.C., and Little R.C. Photonuclear physics in radiation transport: I. Cross sections and spectra photonuclear cross section evaluations to 150 MeV. Nucl. Sci. Eng. 144 (2003) 157-173
245. Giacri M.L., Chadwick M.B., Ridikas D., Young P.G., and Wilson W.B. Photonuclear physics in radiation transport: III. Photofission cross sections. Nucl. Sci. Eng. 153 (2006) 33-40
246. White M., Little R., Chadwick M., Young P., and MacFarlane R. Photonuclear physics in radiation transport-II: Implementation. Nucl. Sci. Eng. 144 (2003) 174-189
247. 232Th. Phys. Rev. C 21 (Apr 1980) 1215-1231
248. P. Young and M.B. Chadwick to be published, 2007
249. Barber W.C., and George W.D. Neutron Yields from Targets Bombarded by Electrons. Phys. Rev. 116 (1959) 1551-1559
250. M. White, R. Little, M. Chadwick, P. Moller, W. Wilson, M. Nieto, M. Giacri, C. Moss, H. Trellue, G. McKinney, and D. Mashnik, "Photofission delayed neutron detection of HEU for nonproliferation," Tech. Rep. LA-UR-03-7724, Los Alamos National Lab, NM, 2003
251. Hale G.M., and Talley T.L. Cross sections and spectra for charged-particle induced reactions. In: Dickens J.K. (Ed). Proc. of the Inter. Conf. on Nuclear Data for Science and Technology. (La Grange Park, IL), Gatlinburg, TN, 1994 (1994), American Nuclear Society 403
252. Lohr J., and Haeberli W. Elastic Scattering of 9-13 MeV Vector Polarized Deuterons. Nucl. Phys. A 232 (1974) 381
253. McFadden L., and Satchler G.R. Optical model analyses of the scattering of 24.7 MeV alpha particles. Nucl. Phys. 84 (1966) 177-200
254. Becchetti F.D., and Greenlees G.W. Polarization Phenomena in Nuclear Reactions. In: Barschall H., and Haeberli W. (Eds). Proc. of the Conference on Polarization Phenomena in Nuclear Reactions. (University of Wisconsin) (1971), University of Wisconsin Press, 223 682
255. D.G. Madland, "Recent results in the development of a global medium-energy nucleon-nucleus optical model potential," in Proc. of a Specialists Meeting on Preequilibrium Reactions in Semmering, Austria (B. Strohmaier, ed.), no. NEANDC-245, pp. 103-116, OECD Nuclear Energy Agency, Paris, 1988
256. A.J. Koning, J.J. van Wijk, and J.-P. Delaroche, "ECISVIEW: An interactive toolbox for optical model development," in Proc. of a Specialists Meeting on the Nucleon-Nucleus Optical Model up to 200 MeV, (Paris, France), pp. 111-120, Bruyeres-le-Chatel France, 13-15 November, OECD Nuclear Energy Agency, 1996
257. Ignatyuk A.V., Smirenkin G.N., and Tishin A. Phenomenological description of the energy dependence of the level density parameter. Sov. J. Nucl. Phys. 21 (1975) 255-257
258. Cook J.L., Ferguson H., and Musgrove A.R. Nuclear level densities for intermediate and heavy nuclei. Aus. J. Phys. 20 (1967) 477-487
259. Kalbach C. The Griffin Model, complex particles and direct nuclear reactions. Z. Physik A283 (1977) 401-411
260. C. Kalbach, "PRECO-D2: Program for calculating preequilibrium and direct reaction double differential cross sections," report LA-10248-MS, Los Alamos National Lab, 1985
261. H. Trellue and M. Chadwick, "Modifications to High-Energy Neutron and Proton Sublibraries (LA150)," Tech. Rep. LA-UR-06-3091, Los Alamos National Lab, 2005
262. t = 12.5 to 117 keV. Phys. Rev. C 29 (Jun 1984) 2031-2046
263. Poppe C.H., Holbrow C.H., and Borchers R.R. Neutrons from D + T and D + H. Phys. Rev. 129 (Jan 1963) 733-739
264. 4He reaction for deuteron energies between 3 and 7 MeV. Zeitschrift für Physik A, Hadrons and Nuclei 300 (Dec 1981) 315-317
265. Holm D.M., and Argo H.V. t-t elastic scattering from 1.6 to 2.0 MeV. Phys. Rev. 101 (1956) 1772
266. Wong C., Anderson J.D., and McClure J.W. Neutron spectrum from the t+t reaction. Nucl. Phys. 71 (1965) 106
267. 3 + t Reactions. Phys. Rev. 129 (1963) 785
268. Barshay S., and Temmer G.M. Geometric test of the isospin multiplet nature of nuclear analog states. Phys. Rev. Lett. 12 (Jun 1964) 728-730
269. NSDD-Network. ENSDF, Evaluated Nuclear Structure Data File (2006). www.nndc.bnl.gov/ensdf
270. Tuli J. Nuclear Wallet Cards. Electronic version (2005). www.nndc.bnl.gov/wallet
271. Greenwood R., Helmer R., Putnam M., and Watts K. Measurement of β- decay intensity distributions of several fission-product isotopes using a total absorption γ-ray spectrometer. Nucl. Instrum. Methods Phys. Res. A390 (1997) 95
272. N. Hagura, T. Yoshida, and T. Tachibana, "Reconsideration of the theoretical supplementation of decay data in fission-product decay heat summation calculations," J. of Nucl. Science and Tech. (to be published), 2006
273. Yoshida T., et al. Validation of Fission Product Decay Data for Decay Heat Calculations. WPEC Subgroup-25 (2006). www.nea.fr/html/science/projects/SG25
274. Band I., Trzhaskovskaya M., Nestor Jr. C., Tikkanen P., and Raman S. Dirac-Fock internal conversion coefficients. At. Data Nucl. Data Tables 81 (2002) 1
275. P. Cassette, "SPEBETA programme de calcul du spectre en energie des electros emis par des radionucleides emetterus beta," Tech. Rep. CEA Technical Note LPRI/92/307/J, CEA Saclay, 1992
276. A. Tobias and R. Mills. (private communication), 1989
277. T. England and B. Rider, "Evaluation and compilation of fission product yields," Tech. Rep. ENDF-349, Los Alamos National Lab, 1992
278. D.E. Cullen, J.H. Hubbell, and L. Kissel, "EPDL97: The Evaluated Photon Data Library, '97 Version," Tech. Rep. UCRL-50400, Vol.6, Rev.5, Lawrence Livermore National Lab, September 1997
279. S.T. Perkins, D.E. Cullen, and S.M. Seltzer, "Tables and Graphs of Atomic Subshell and Relaxation Data Derived from the LLNL Evaluated Electron Data Library (EEDL), Z = 1-100," Tech. Rep. UCRL-50400, Vol.30, Lawrence Livermore National Lab, October 1991
280. S.T. Perkins, D.E. Cullen, and S.M. Seltzer, "Tables and Graphs of Electron Interaction Cross Sections from 10 eV to 100 GeV Data Derived from the LLNL Evaluated Electron Data Library (EEDL), Z = 1-100," Tech. Rep. UCRL-50400, Vol.31, Lawrence Livermore National Lab, October 1991
281. D.E. Cullen, "ENDF/B-VI Coupled Photon-Electron Data for Use in Radiation Shielding Applications," Tech. Rep. UCRL-JC-148180, Lawrence Livermore National Lab, 2002
282. T. Sutton et al., "The physical models and statistical procedures used in the RACER Monte Carlo code," Tech. Rep. KAPL-4840 (DOE/TIC-4500-R75), Knolls Atomic Power Lab, 1999
283. Brown F. Vectorization of 3-D General Geometry Monte Carlo. Trans. Am. Nucl. Soc. 53 (1986) 283
284. L. Ondis, L. Tyburski, and B. Moskowitz, "RCP01 - a Monte Carlo program for solving neutron and photon transport problems in three-dimensinal geometry with detailed energy desription and depletion capability," Tech. Rep. B-TM-1638, Bechtel Bettis, 2000
285. R. Blomquist, "VIM continous energy Monte Carlo transport code," in Proc. Inter. Conf. on Mathematics, Computations, Reactor Physics and Environmental Analysis, (Portland, OR), April 30 - May 4 1995
286. S.C. van der Marck, "Benchmarking ENDF/B-VII.0." Nuclear Data Sheets, the present issue
287. J. Both et al., "TRIPOLI-4 Monte Carlo method particle transport computer code," Tech. Rep. CEA-R-6044, CEA Saclay, 2003
288. A. dos Dantos, R. Diniz, L. Fanaro, R. Jerez, G. de Andrade e Silva, and M. Yamaguchi, "The experimental determination of the effective delayed neutron parameters of the IPEN/MB-01 reactor," (Chicago), PHYSOR-2004
289. Okajima S., Sakurai T., Lebrat J., and Averlant V. Summary on international benchmark experiments for effective delayed neutron fraction. Progress in Nuclear Energy 41 (2002) 285301
290. Klein Meulekamp R., and van der Marck S. Reevaluation of the effective delayed neutron fraction measured by the substitution technique for a light water moderated low-enriched uranium core. Nucl. Sci. Eng. 152 (2006) 142-148
291. van der Marck S., Klein Meulekamp R., Hogenbirk A., and Koning A. Benchmark results for delayed neutron data. (New York, USA), Santa Fe, Sept 26 - Oct 1, 2004 (2005), Amer. Inst. of Physics 531-534
292. W. Webster et al., "Measurements of the neutron emission spectra from spheres of N, O, W, U-235, U-238, and Pu-239, pulsed by 14 MeV neutrons," Tech. Rep. UCID-17332, 1976
293. C. Wong et al., "Livermore pulsed sphere program: Program summary through July 1971," Tech. Rep. UCRL-51144, Rev I, and Addendum (1973), Lawrence Livermore National Lab, Livermore, 1972
294. A. Marchetti and G. Hedstrom, "New Monte Carlo simulations of the LLNL pulsed-sphere experiments," Tech. Rep. UCRL-ID-131461, Lawrence Livermore National Lab, Livermore, 1998
295. S. Frankle, "LLNL pulsed-sphere measurements and detector response functions," Tech. Rep. X-5:SCF-04-004 and LA-UR-05-5878, Los Alamos National Lab, Los Alamos, 2004
296. S. Frankle, "Possible impact of additional collimators on the LLNL pulsed-sphere experiments," Tech. Rep. X-5:SCF-04-001 and LA-UR-05-5877, Los Alamos National Lab, Los Alamos, 2004
297. Bucholz J., and Frankle S. Improving the LLNL pulsed-sphere experiments database and MCNP models. Trans. Am. Nucl. Soc. (2002) 433-435