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Abe, Takumi; Oizumi, Akito; Nishihara, Kenji; Nakase, Masahiko*; Asano, Hidekazu*; Takeshita, Kenji*
Progress in Nuclear Science and Technology (Internet), 7, p.299 - 304, 2025/03
Currently, much research continues on stable energy sources that do not emit CO
in order to achieve a carbon-neutral and sustainable society. Nuclear energy is one of the such sources, and various new reactors and reprocessing technologies are being developed. In order to implement the nuclear fuel cycle with these technologies, a nuclear fuel cycle simulator is required to quantitatively evaluate various quantities, such as the distribution of nuclear fuel materials and the scale of waste loading. For this purpose, NMB4.0 was developed in collaboration with Tokyo Institute of Technology and Japan Atomic Energy Agency. This code calculates the material balance of 179 nuclides including actinides and fission products (FPs) from the front-end to the back-end and simulates the nuclear fuel cycle in an integrated manner. Unlike other nuclear fuel cycle simulators, the code is capable of performing precise back-end analyses such as the number of radioactive wastes and the scale of the geological repository considering heat generation of waste package under diverse nuclear energy scenario, and is an open source code that runs on Microsoft Excel. By these features, it is possible to quantitatively study nuclear energy utilization strategies with various stakeholders. The presentation will detail the numerical model used in NMB4.0.
Nishihara, Kenji
JAEA-Data/Code 2020-005, 48 Pages, 2020/07
JAEA-Data-Code-2020-005.pdf:2.95MB
JAEA-Data-Code-2020-005-appendix(CD-ROM).zip:3.62MB
In order to discuss the technological development and human resource development necessary for the future nuclear fuel cycle, various quantitative analyzes were conducted assuming a wide range of future nuclear power generation 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.
Nakajima, Hayato; Ikenoya, Kazuhiko*; Onuki, Kaoru; Shimizu, Saburo
Kagaku Kogaku Rombunshu, 24(2), p.352 - 355, 1998/00
Times Cited Count：55 Percentile：87.64(Engineering, Chemical)no abstracts in English
JAERI-M 8063, 60 Pages, 1979/01
no abstracts in English
Tateno, Haruka; Sato, Takumi; Tsubata, Yasuhiro; Hayashi, Hirokazu
no journal, ,
Japan Atomic Energy Agency has been pursuing research and development on partitioning and transmutation of minor actinides (MAs) by accelerator-driven system (ADS) using uranium-free nitride fuel. The target transmutation ratio of 99% MAs can be achieved if 99.9% of MAs in the spent fuel are recovered in reprocessing. From the point of view of neutronics design, the weight ratio of rare-earths against MAs in the refabricated fuel should be 5.0% or less. In this study, we calculated the material balance in the pyro-reprocessing of nitride fuel to evaluate the processing conditions to meet the above-mentioned requirements.
