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Kashima, Takao; Suyama, Kenya; Takada, Tomoyuki*
JAEA-Data/Code 2014-028, 152 Pages, 2015/03
JAEA-Data-Code-2014-028.pdf:13.39MB
There have been two versions of SWAT depending on details of its development history: the revised SWAT that uses the deterministic calculation code SRAC as a neutron transportation solver, and the SWAT3.1 that uses the continuous energy Monte Carlo code MVP or MCNP5 for the same purpose. It takes several hours, however, to execute one calculation by the continuous energy Monte Carlo code even on the super computer of the Japan Atomic Energy Agency. Moreover, two-dimensional burnup calculation is not practical using the revised SWAT because it has problems on production of effective cross section data and applying them to arbitrary fuel geometry when a calculation model has multiple burnup zones. Therefore, SWAT4.0 has been developed by adding, to SWAT3.1, a function to utilize the deterministic code SARC2006, which has shorter calculation time, as an outer module of neutron transportation solver for burnup calculation. SWAT4.0 has been enabled to execute two-dimensional burnup calculation by providing an input data template of SRAC2006 to SWAT4.0 input data, and updating atomic number densities of burnup zones in each burnup step. This report describes outline, input data instruction, and examples of calculations of SWAT4.0.
Nojiri, Naoki; Handa, Yuichi*; Shimakawa, Satoshi; Goto, Minoru; Kaneko, Yoshihiko*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 5(3), p.241 - 250, 2006/09
It was shown from the annular core experiment of the HTTR that the discrepancy of excess reactivity between experiment and analysis reached about 3 % Dk/k at maximum. Sensitivity analysis for the annular core of the HTTR was performed to improve the discrepancy. The SRAC code system was used for the core analysis. As the results of the analysis, it was found clearly that the multiplication factor of the annular core is affected by (1) mesh interval in the core diffusion calculation, (2) mesh structure of graphite region in fuel lattice cell and (3) the Benoist's anisotropic diffusion coefficients. The significantly large discrepancy previously reported was reduced down to about 1 % Dk/k by the revised annular core model.
Yamane, Tsuyoshi; *
JAERI-Data/Code 99-011, 46 Pages, 1999/03
JAERI-Data-Code-99-011.pdf:1.33MB
no abstracts in English
U captures to 
U fission in low-enriched UO
tight latticesNakajima, Ken; ; Yamamoto, Toshihiro; ; Suzaki, Takenori
Journal of Nuclear Science and Technology, 31(11), p.1160 - 1170, 1994/11
Times Cited Count：7 Percentile：56.56(Nuclear Science & Technology)no abstracts in English
Nakano, Yoshihiro; Ichikawa, Hiroki; Nakajima, Teruo
Proc. of the 16th Int. Meeting on Reduced Enrichment for Research and Test Reactors, 0, p.313 - 320, 1994/03
no abstracts in English
Obu, Makoto; ; Sakurai, Takeshi; Iijima, Susumu; *; Osugi, Toshitaka
JAERI-M 90-052, 52 Pages, 1990/03
no abstracts in English
*; ; ; *
JAERI-M 90-007, 126 Pages, 1990/02
no abstracts in English
JAERI-M 87-063, 133 Pages, 1987/04
no abstracts in English
; Kawamura, Hiroshi; ;
JAERI-M 87-036, 51 Pages, 1987/03
no abstracts in English
; ; ; ;
JAERI-M 85-047, 81 Pages, 1985/04
no abstracts in English
