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; ; Sanda, Toshio*
PNC TJ9124 93-009, 334 Pages, 1993/03
To commertialize LMFBR, they are important subjects of research and development to improve the accuracy in neutronic design of large LMFBR cores and to make be able to design highly efficient core more rationaoy. The adjusted library has been made by being reflected the result of critical experiment of the JUPITER, etc. effectively as much as possible by using the cross-sections adjustment method based on the probabilistic theory. And the distinct improvement of the accuracy in neutronic design of large LMFBR cores has been achieved. In the design of large LMFBR cores, however, it is important to accurately estimate not only neutronic characteristics, for example, reaction rate distribution and control rod worth but also burnup characteristics, for example, burnup reactivity loss, breeding ratio and so on. Therefore the objective of the work is to improve the prediction accuracy for burnup characteristics using many burnup data of "Joyo" effectively. For the objective computer codes for analyzing sensitivity coefficients of burnup characteristics were prepared and cross-sections adjustment using burnup data of "Joyo" was done and the effect for the improvement of the accuracy for burnup characteristics was estimated. The results are as follows: (1)The computer codes which could analyze sensitivity coefficients of burnup characteristics of LMFBR taking into consideration plural cycles and refueling were prepared and their adequacy was made sure by comparing with direct calculations. (2)It was clarified that it is possible to improve the accuracy of burnup characteristics without affecting statically neutronic characteristics so much by applying the burnup characteristics to cross-sections adjustment.
; ; Miyakawa, Shunichi
PNC TN9410 87-009, 95 Pages, 1987/01
The Coordinated Research Programme (CRP) on Intercomparison of LMFBR Core Mechanics Codes was agreeded by the Consultants' Meeting of the IAEA international Working Group on Fast Reactors (IWGFR) in Vienna June, 1985. This report presents the results to all the problems set for the stage in which the LMFBR Core Mechanics Codes should be verified on the basis of comparison of computational results. The example problems have been solved with the three dimensinal structural analysis code for bowing history of fast breeder reactor cores, "HIBEACON".
Watari, Yoshio*; ;
PNC TJ902 84-05, 168 Pages, 1984/08
The Analysis on the Gamma heating of the 0'th cycle of "Joyo" MK-II Core has been performed. In advance of this analysis, the followings have been performed. (1)The Cross Sections for the Gamma heating analysis have been prepared based on JENDL-IIB-70 and the second Gamma production data which was made from ENDF-B/IV. These Cross Sections include the Neutron Cross Section, the second Gamma production Cross Section and the Gamma transport cross section. The number of the energy groups is 7 for the Neutron, and 20 for the Gamma ray. (2)The analysis on the experiment of the Gamma heating in the FCA X-2. This FCA X-2 is the mock-up of the "Joyo" MK-II core. The analysis has been performed based on the RZ-geometry and the XY-geometry. The Gamma source was calculated with the Neutron Diffusion theory and the Gamma transport calculation was performed with SN-Code(P
S
).
