JENDL-4.0: A New Library for Nuclear Science and Engineering
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Chiba G., J. Nucl. Sci. Technol.
Igarasi S., 1991, Program CASTHY—Statistical Model Calculation for Neutron Cross Sections and Gamma Ray Spectrum—
Nakagawa T., 1999, PEGASUS: A Preequilibrium and Multi-Step Evaporation Code for Neutron Cross Section Calculation
Young P. G., 1992, Comprehensive Nuclear Model Calculations: Introduction to the Theory and Use of the GNASH Code
Ichihara A., 2007, Program POD; A Computer Code to Calculate Cross Sections for Neutron-Induced Nuclear Reactions
Iwamoto O., 2003, Program CCOM, −Coupled-Channels Optical Model Calculation with Automatic Parameter Search—
Kalbach C., 1986, Phys. Rev., 33, 818
Kopecky J., 1990, Phys. Rev., 41, 1941
Kopecky J., 1993, Phys. Rev., 47, 312
Belgya T., 2006, Handbook for Calculations of Nuclear Reaction Data, RIPL-2
Kalbach C., 1988, Phys. Rev., 37, 2350
Becchetti , F. D. Jr. and Greenlees , G. W. 1971.Polarization Phenomena in Nuclear ReactionsEdited by: Barshall , H. H. and Haeberli , W. 682University of Wisconsin Press.
Lemos O. F., 1972, Diffusion Elastique de Particules Alpha de 21 à 29.6 MeV sur des Noyaux de la Region Ti-Zn
Arthur E. D., 1980, Evaluated Neutron-Induced Cross Sections for 54 56 Fe to 40 MeV, 10.2172/6674307
Sukhovitskii E. Sh., 2005, Programs OPTMAN and SHEMMAN Version 8 (2004)
Tasaka K., 1990, JNDC Nuclear Data Library of Fission Products—SecondVersion—
Rider B. F., 1979, Compilation of Fission Product Yields
England T. R., 1992, Evaluation and Compilation of Fission-Product Yields
Koning A., 2006, The JEFF-3.1 Nuclear Data Library
Santamarina A., 2009, The JEFF-3.1.1 Nuclear Data Library
Mills R. W., 1995, Fission Product Yield Evaluation
Katakura J., 2001, JENDL FP Decay Data File 2000
McLane V., 2000, EXFOR Basics: A Short Guide to the Nuclear Reaction Data Exchange Format
Kawano T., 2000, Evaluation of Fission Cross Sections and Covariances for 233U, 235U, 238U, 239Pu, 240Pu, and 241Pu
Poenitz W. P., 1981, Proc. Conf. Nuclear Data Evaluation Methods and Proce- dures, 249
Chiba S., 1991, A Suggested Procedure for Resolving an Anomaly in Least-Squares Data Analysis Known as “Peel's Pertinent Puzzle” and the General Implications for Nuclear Data Evaluation
Besant C. B., 1977, J. Br. Nucl. Energy Soc., 16, 161
East L. V., 1970, Delayed Neutron Abundances and Half-Lives for 14.7-MeV Fission
Piksaikin , V. M. 1997. private communication
Piksaikin V. M., 1999, Phys. At. Nucl., 62, 1279
Verbinski V. V., 1973, Phys. Rev., 7, 1173
Audi , G. 2009. private communication
Herman M., 2009, ENDF-6 Formats Manual
Leal L. C., 2001, U in Neutron Energy Range from Thermal to 600 eV
Larson N. M., 2006, Updated Users' Guide for SAMMY: Multilevel R-Matrix Fits to Neutron Data Using Bays' Equation
Dridi W., 2006, Proc. ANS Top. Mtg. on Reactor Physics (PHYSOR-2006)
Parker W. E., 1994, Phys. Rev., 49, 672
Kikuchi Y., 1999, ASREP: A Computer Program for Automatic Search of Unresolved Resonance Parameters
Kazakov L. E., 1985, Vop. At. Nauki i Tekhn., Ser. Yadernye Konstanty, 1985, 44
Frehaut J., 1980, Proc. Symp. On Neutron Cross Sections From 10–50 MeV
Chiba G., 2007, Benchmark Test of Evaluated Nuclear Data Files for Fast Reactor Neutronics Application
Piksaykin V. M., 2006, Pribory I Tekhnika Eksperimenta, 6, 29
Tuttle R. J., 1979, Proc. Consultants' Mtg. Delayed Neutron Properties
Waldo R. W., 1981, Phys. Rev., 23, 1113
Esch E.-I., 2008, Phys. Rev., 77, 034309
Derrien H., 2007, Proc. Int. Conf. Nuclear Data for Science and Technology, 667
Gwin R., 1978, Measurements of the Average Number of Prompt Neutrons Emitted per Fission of 239Pu and 235U, 10.2172/7020385
Frehaut J., 1973, Physics+Chemistry of Fission Symp., 2
Jandel M., 2008, Phys. Rev., 78, 034609
Aïche M., 2007, Proc. Int. Conf. Nuclear Data for Science and Technology, 483
Laptev A. B., 2007, Conf. Fission and Properties of Neutron-Rich Nuclei
Dovbenko A. G., 1971, Radiative Capture of Neutrons by 241Am
Kikuchi Y., 1975, STAT: A Code for Analysis of Statistical Properties of Averaged Resonance Cross Sections
Iwamoto O., 2005, Proc. Int. Conf. on Nuclear Data for Science and Technology
2010, Evaluated Nuclear Structure Data File (ENSDF)
Mughabghab S. F., 2006, Atlas of Neutron Resonances, Resonance Parameters and Thermal Cross Sections
Tagliente G., 2008, Phys. Rev., 78, 045804
Ohgama K., 2006, Proc. 12th Int. Conf. on Capture Gamma-Ray Spectroscopy and Related Topics
Igashira , M. 2007. private communication
D'hondt P., 1983, Proc. Int. Conf. on Nuclear Data for Science and Technology, 147, 10.1007/978-94-009-7099-1_29
Okumura , K. 2009. private communication
Smith D. A., 2002, Phys. Rev., 65, 024607
Lowie L. Y., 1997, Phys. Rev., 56, 90
Lowie L. Y., 1999, Phys. Rev., 59, 1119
Iwamoto N., 2009, Proc. 2008 Annu. Symp. on Nuclear Data
Dickens J. K., 1973, Gamma-ray Production due to Neutron Interactions with Tin for Incident Neutron Energies between 0.75 and 20 MeV: Tabulated Differential Cross Sections
Sharapov E. I., 1999, Phys. Rev., 59, 1772
Wisshak K., 1998, Phys. Rev., 57, 3452
Wisshak K., 1997, Stellar Neutron Capture Cross Sections of the Neodymium Isotopes, Kernforschungszentrum Karlsruhe Reports No. 5967
Gledenov Yu. M., 2000, Phys. Rev., 62, 042801
Filatenkov , A. A. Chuvaev , S. V. Aksenov , V. N. 1997.Systematic Measurement of Activation Cross Sections at Neutron Energies from 13.4 to 14.9 MeV, USSR report to the I.N.D.C., No. 402
Yamamoto , T. 2009. private communication
Mughabghab S. F., 1984, Neutron Cross Sections, Volume 1, Part B: Z = 61–100
Kawano , T. 2008. private communication
Leal L. C., 1997, Proc. Int. Conf. on Nuclear Data for Science and Technology
Konno , C. 2010. private communication
Moxon M. C., 1993, Phys. Rev., 48, 553
Leal , L. C. Derrien , H. Guber , K. 2010. private communication
Abfalterer W. P., 2001, Phys. Rev., 63, 044608
Derrien , H. Leal , L. C. and Larson , N. M. 2010. private communication
Kinney W. E., 1976, Proc. Int. Conf. on Interactions of Neutrons with Nuclei, 1319
Perey C. M., 1991, Proc. Int. Conf. on Nuclear Data for Science and Technology, Jülich, Germany, May 13–17
Harvey , J. A. Halperin , J. Hill , N. W. 1976.(n, α), (n, p), (n, γ) and Total Neutron Cross Section Measurements on59Ni, ORNL-5137 2Oak Ridge National Laboratory (ORNL).
Chiba , G. 2008. private communication
Pandey M. S., 1977, Phys. Rev., 15, 600
Nemoto S., 1998, Phys. Rev., 58, 2599
Nemoto S., 1999, Elastic Nucleon-Deuteron Scattering with Δ-isobar Excitation
Oryu , S. 2003. private communication
Shibata K., 1984, Evaluation of Neutron Nuclear Data for 9Be for JENDL-2
Kornilov N. V., 1990, Jadrnye Konstanty, 1, 11
Itagaki , N. 2009. private communication
Itagaki N., 2003, Phys. Rev., 68, 054302
Cserpak F., 1978, Proc. Int. Conf. on Neutron Physics and Nuclear Data for Reactors and Other Applied Purposes, 761
Firestone R. B., 2007, Proc. 2007 Int. Workshop on Compound-Nuclear Reactions and Related Topic—CNR* 2007, 26
Shibata K., 1983, C
Wagemans J., 2000, Phys. Rev., 61, 064601
Moxon , M. C. Endacott , D. A. J. and Jolly , J. E. 1974.Neutron Total Cross Section Measurements, AERE-PR/NP-20 29
Ohkubo , M. 1984. taken from EXFOR21926002
Wisshak K., 2000, Phys. Rev., 61, 065801
Bokhovko , M. V. Kononov , V. N. Rabotnov , N. S. 1996. taken from EXFOR
Qiu J.-Z., 2005, High Energy Phys. Nucl. Phys., 29, 648
Segawa M., 2007, Phys. Rev., 76, 022802
Winters R. R., 1987, Astron. Astrophys., 171, 9
Domingo-Pardo C., 2007, Phys. Rev., 75, 015806
Borella A., 2007, Phys. Rev., 76, 014605
Domingo-Pardo C., 2006, Phys. Rev., 74, 055802
Carlton R. F., 1991, Bull. Am. Phys. Soc., 36, 1394
Harvey , J. A. 1999. private communication in EXFOR
Horen D. J., 1978, Phys. Rev., 18, 722
Foster D. G., 1971, Phys. Rev., 3, 576
Horen D. J., 1979, Phys. Rev., 20, 478
Carlton R. F., 2003, Phys. Rev., 67, 024601
Domingo-Pardo C., 2006, Phys. Rev., 74, 025807
Leal , L. C. 2009. private communication
Kawano T., 1997, Covariance Evaluation System