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Tada, Kenichi; Suyama, Kenya
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 4 Pages, 2017/04
JAEA provides the evaluated nuclear data library JENDL. Usually, the integral experiments are used for the validation. Since this validation process takes long time and much effort, the automated system has been desired. To realize the automated system, nuclear data processing, analysis of the integral experiments and editing calculation results are required. With regard to the nuclear data processing, JAEA has started to develop the new nuclear data processing system FRENDY. Using FRENDY, the nuclear data can be automatically processed. Taking advantage of FRENDY, we developed the automatic nuclear data validation system VACANCE. VACANCE has many functions, e.g., searching and modifying the input file, available for the parallel computation and restart calculation, editing the calculation results. Combination of FRENDY and VACANCE enables us to carry out the efficient nuclear data validation cycle. In this presentation, the outline and functions of VACANCE are demonstrated.
Dietze, K.
JNC TN9400 99-089, 20 Pages, 1999/11
The integral experiments performed at the Rossendorf fast-thermal coupled reactor RRR/SEG have been reanalyzed using the JNC route for reactor calculation JENDL3.2/SLAROM / CITATION / JOINT / PERKY. The Rossendorf experiments comprise sample reactivity measurements with pure fission products and structural material in five configurations with different neutron and adjoint spectra. The shapes of the adjoint spectra have been designed to get high sensitivities to neutron capture or the scattering effect. The calculated neutron and adjoint spectra are in good agreement with former results obtained with the European route JEF2.2/ECCO/ERANOS. The C/E-values of the central reactivity worths of samples under investigation are given. Deviations in the results of both routes are due to the different libraries, codes, and self-shielding treatments used in the calculations. Results outside of the error are discussed.
Nakashima, Hiroshi; Takada, Hiroshi; Meigo, Shinichiro; Kasugai, Yoshimi; Ikeda, Yujiro; Oyama, Yukio; Watanabe, Noboru*;
Proc. of 14th Meeting of the Int. Collaboration on Advanced Neutron Sources (ICANS-14), 1, p.457 - 467, 1998/11
no abstracts in English
Takada, Hiroshi
Proc. of JHF Symp. on Neutronics and Radiation Shielding for Spallation Neutron Source, p.205 - 218, 1998/00
no abstracts in English
Yamamoto, Toshihiro; Sakurai, Kiyoshi; Suzaki, Takenori; *; ; Horiki, Oichiro*
Journal of Nuclear Science and Technology, 34(12), p.1178 - 1184, 1997/12
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Sakurai, Kiyoshi; Yamamoto, Toshihiro
Journal of Nuclear Science and Technology, 34(2), p.202 - 210, 1997/02
Times Cited Count：3 Percentile：30.37(Nuclear Science & Technology)no abstracts in English
Takada, Hiroshi; Meigo, Shinichiro; Sasa, Toshinobu; Fukahori, Tokio; Sakamoto, Yukio; Yoshizawa, Nobuaki*; Furihata, Shiori*; V.I.Belyakov-Bodin*; G.I.Krupny*
Proc. of 3rd Workshop on Simulating Accelerator Radiation Environments (SARE3), p.255 - 263, 1997/00
no abstracts in English
Takada, Hiroshi; Meigo, Shinichiro; Sasa, Toshinobu; Tsujimoto, Kazufumi; Fukahori, Tokio; Yasuda, Hideshi
Proc. of 3rd Workshop on Simulating Accelerator Radiation Environments (SARE3), p.284 - 292, 1997/00
no abstracts in English
Takizuka, Takakazu; ; Sasa, Toshinobu; Takada, Hiroshi; Meigo, Shinichiro; Mizumoto, Motoharu;
Global 1995,Int. Conf. of Evaluation of Emerging Nuclear Fuel Cycle Systems, 0, p.489 - 496, 1995/00
no abstracts in English
Nakamura, Tomoo; Oyama, Yukio; Ikeda, Yujiro; Konno, Chikara; Maekawa, Hiroshi; Kosako, Kazuaki*; M.Z.Youssef*; M.A.Abdou*
Fusion Technology, 19(3), p.1873 - 1878, 1991/05
no abstracts in English
;
JAERI-M 83-188, 61 Pages, 1983/11
no abstracts in English
JAERI-M 9999, 358 Pages, 1982/03
no abstracts in English
Tada, Kenichi
no journal, ,
Validation of the nuclear data using the criticality experiments and nuclear reactor experiments, i.e., integral experiments, is one of the most important process. The analyses of the integral experiments become more important along with the accuracy improvement of the library. This validation procedure is mainly carried out by the specialists of the reactor physics because it is complicated for the nuclear data evaluators. Furthermore, it takes a long time and much effort even if the specialists carry it out. To realize the efficient nuclear data validation cycle for the next version of JENDL, the automatic nuclear data validation system VACANCE (Validation Environment for Comprehensive and Automatic Neutronics Calculation Execution) is developed. In this presentation, the outline and functions of VACANCE are demonstrated in detail and examples of the new nuclear data evaluation and subsequent integral experiment analyses will be shown.
Fukushima, Masahiro; Goda, J.*; Bounds, J.*; Cutler, T.*; Grove, T.*; Hutchinson, J.*; James, M.*; McKenzie, G.*; Sanchez, R.*; Oizumi, Akito; et al.
no journal, ,
no abstracts in English
Yokoyama, Kenji
no journal, ,
no abstracts in English
Tokashiki, Mikio*; Ikehara, Tadashi*; Tada, Kenichi; Egawa, Toru*; Yokoyama, Kenji; Iwamoto, Osamu
no journal, ,
The bias factor methods have been widely used for applications to reduce uncertainties of the predicted value in the reactor physics characteristics. In the present study, an attempt has been made to apply the extended bias factor method to qualifying the reliability of measured data by assuming the uncertainty of the numerical model being negligible and the covariance of cross section being reliable. In this presentation, comparison results will be shown between actual measured value and the predicted value of a benchmark case sampled from the benchmark suite. Furthermore, it will be shown that the comparison and their uncertainty enable us to qualify the degree of reliability of the actual measured value.
