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Ohtaki, Akira; ; ; *; *;
JNC TN9410 2000-006, 74 Pages, 2000/04
JNC-TN9410-2000-006.pdf:3.01MB
To evaluate materials balance in nuclear fuel cycle quickly and quantitatively the fuel cycle requirement code "FAMILY" was improved. And an accumulated TRU&LLFP quantity analysis code was developed. The contents are as follows: (1)A calculation ability of minor actinide production and expenditure was added to the "FAMILY" code. (2)An output program for the "FAMILY" calculation results was developed. (3)A simple version of "FAMILY" code was developed. (4)An analysis code for accumulated TRU&LLFP quantity in nuclear fuel cycle was developed.
Fukaya, Yuji; Goto, Minoru; Ueta, Shohei; Okamoto, Koji*
no journal, ,
To confirm the feasibility of plutonium burner HTGR, we investigate introduction scenario, and evaluate mass balance of proposed fuel cycle based on the scenario. Finally we confirmed the usefulness of the proposed cycle quantitatively.
Nishihara, Kenji
no journal, ,
In order to discuss the technological development and human resource development necessary for the future nuclear fuel cycle at the research committee on "Feasibility of Nuclear Fuel Cycle," various quantitative analyzes were conducted assuming a wide range of future scenarios. In the evaluation of quantities, the future power generation of LWR and fast reactor, the amount of spent fuel reprocessing, etc. were assumed, and the amount of uranium demand, the accumulation of spent fuel, plutonium, vitrified waste etc. were estimated.
Nishihara, Kenji; Abe, Takumi
no journal, ,
In order to study the future nuclear power generation and nuclear fuel cycle including geological disposal in Japan, various quantity evaluation codes are used to calculate the time variation of the quantities. The NMB code published by Tokyo Institute of Technology and JAEA was used to evaluate various quantities using the example of the Ikata Nuclear Power Plant, and the code was validated. Simple future projections were also made.
Takeshita, Kenji*; Matsumura, Tatsuro
no journal, ,
no abstracts in English
Nishihara, Kenji; Takeshita, Kenji*; Shimada, Takashi*; Nakase, Masahiko*
no journal, ,
Many codes have been developed in the world to quantify future nuclear scenarios for the purpose of developing nuclear energy utilization strategies and R&D goals. However, quality assurance and verification of the accuracy of the codes are not yet fully implemented, with only simple benchmark intercomparisons by the OECD/NEA. In the various evaluation codes, many models are used for each process of the nuclear fuel cycle and nuclear reactors, and there are differences in the definitions of inputs and outputs and databases, so a general verification method has not been established. Therefore, we developed a verification and validation (V&V) method for quantity evaluation codes to contribute to quality assurance and accuracy verification in the future.