Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Plompen, A. J. M.*; Cabellos, O.*; De Saint Jean, C.*; Fleming, M.*; Algora, A.*; Angelone, M.*; Archier, P.*; Bauge, E.*; Bersillon, O.*; Blokhin, A.*; et al.
European Physical Journal A, 56(7), p.181_1 - 181_108, 2020/07
Times Cited Count：321 Percentile：99.41(Physics, Nuclear)The Joint Evaluated Fission and Fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides 
U, 
U and 
Pu, on 
Am and 
Na, 
Ni, Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yileds, prompt fission neutron spectra and average number of neutrons per fission. In addition, new data for radioactive decay, thermal neutron scattering, gamma-ray emission, neutron activation, delayed neutrons and displacement damage are presented. JEFF-3.3 was complemented by files from the TENDL project. The libraries for photon, proton, deuteron, triton, helion and alpha-particle induced reactions are from TENDL-2017. The demands for uncertainty quantification in modeling led to many new covariance data. A comparison between results from model calculations using the JEFF-3.3 library and those from benchmark experiments for criticality, delayed neutron yields, shielding and decay heat, reveals that JEFF-3.3 is excellent for a wide range of nuclear technology applications, in particular nuclear energy.
Fukushima, Masahiro; Tsujimoto, Kazufumi; Okajima, Shigeaki
Journal of Nuclear Science and Technology, 54(7), p.795 - 805, 2017/07
Times Cited Count：10 Percentile：69.28(Nuclear Science & Technology)A series of integral experiments was conducted in FCA assemblies with systematically changed neutron spectra covering from the intermediate to fast ones. The experiments provide systematic data of central fission rates for TRU nuclides containing minor actinides, 
Np, Pu, Pu, 
Pu, Am, 
Am, and 
Cm. Latest major nuclear data libraries, JENDL-4.0, ENDF/B-VII.1, and JEFF-3.2, were tested using benchmark models regarding the fission rate ratios relative to Pu. For all the libraries, the benchmark tests by a Monte Carlo calculation code show obvious overestimations particularly for the fission rate ratios of Cm to Pu. Additionally, a large discrepancy about by 20% between the libraries is revealed for the fission rate ratio of Pu to Pu measured in the intermediate neutron spectrum. The cause of discrepancy is furthermore clarified by sensitivity analyses.
Tsujimoto, Kazufumi; Oigawa, Hiroyuki; Shinohara, Nobuo
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2004), 4 Pages, 2004/09
Japan Atomic Energy Research Institute (JAERI) has been developing technologies for partitioning and transmutation of long-lived nuclides in high-level radioactive waste. In the dedicated transmutation systems, reliable neuclear data of minor actinide (MA) are indispensable to obtain a reliable design of a transmutation system. Present status of MA nuclear data is not so satisfactory. To obtain reliable nuclear data of MA, radiochemically analyzed data of the actinide samples irradiated at the Dounreay Prototype Fast Reactor (PFR) were used in this study. The samples were actinide oxides of 21 different isotopes from thorium to curium. The burnup calculations were performed and the calculated results were compared with the experimental data to validate the neutron cross section data of MA in an evaluated nuclear data file JENDL-3.3, ENDF/B-VI, and JEFF-3.0. The results for uraniumu and plutoniumu samples show good agreements with experimental data. On the other hand, in the results for americium and curiumu, relatively large disagreement with experimental data are showed.
Mori, Takamasa; Nagaya, Yasunobu; Okumura, Keisuke; Kaneko, Kunio*
JAERI-Data/Code 2004-011, 119 Pages, 2004/07
JAERI-Data-Code-2004-011.pdf:5.93MB
The 2nd version of code system, LICEM-2, has been developed to produce neutron cross section libraries for the MVP continuous energy Monte Carlo code from an evaluated nuclear data library in the ENDF format. The code system can process nuclear data in the latest ENDF-6 format and produce cross section libraries for MVP's capability of transport calculation at arbitrary temperature. By using the present system, MVP neutron cross section libraries have been prepared from the latest evaluations of JENDL, ENDF/B and JEFF data bases. This report describes the specification of MVP neutron cross section library, the details of each code in the code system, how to use them and MVP neutron cross section libraries produced with the code system.
Konno, Chikara; Fischer, U.*; Perel, R.*
Journal of Nuclear Science and Technology, 39(Suppl.2), p.1045 - 1048, 2002/08
no abstracts in English
Maekawa, Fujio; Kasugai, Yoshimi; Konno, Chikara; Murata, Isao*; Kokooo*; Wada, Masayuki*; Oyama, Yukio; Ikeda, Yujiro; Takahashi, Akito*
Journal of Nuclear Science and Technology, 36(3), p.242 - 249, 1999/03
Times Cited Count：7 Percentile：49.75(Nuclear Science & Technology)no abstracts in English
Konno, Chikara; Maekawa, Fujio; Wada, Masayuki*; Kosako, Kazuaki*
Fusion Technology, 34(3), p.1013 - 1017, 1998/11
no abstracts in English
Kwon, Saerom*; Konno, Chikara; Ota, Masayuki*; Sato, Satoshi*
no journal, ,
Our analyses of JAEA/FNS copper benchmark experiment with ENDF/B-VIII.0 and JEFF-3.3 pointed out that the calculation with ENDF/B-VIII.0 underestimated and that with JEFF-3.3 overestimated the measured reaction rate of the 
Nb(n,2n)
Nb sensitive to neutrons above 10 MeV. As a result of our detailed study, we specified that this issue was due to the (n,np) and (n,n') reaction data above a few MeV, etc.
Konno, Chikara
no journal, ,
We examined the ACE files of the Fusion Evaluated Nuclear Data Library FENDL-3.2b in detail and found that damage production energy cross section data and proton ACE files had problems. It was pointed out that the damage production energy cross section data above 20 MeV of FENDL-3.2b from JENDL-4.0/HE and those above a few MeV of FENDL-3.2b from JEFF-3.1.1 were too small, which was solved by replacing them with JENDL-5 and JEFF-3.2 in the next FENDL, respectively. It was also proposed to reproduce the proton ACE files of FENDL-3.2b from JENDL/HE-2007 for the next FENDL with the nuclear data processing code NJOY2016 modified for JENDL-5, because the Monte Carlo code MCNP6.2 could not treat secondary neutron production data in the proton ACE files of FENDL-3.2b from JENDL/HE-2007 adequately.
