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Abe, Takumi; Suzuki, Taiga*; Okamura, Tomohiro*; Nakase, Masahiko*
Annals of Nuclear Energy, 232, p.112224_1 - 112224_7, 2026/07
Times Cited Count：0 Percentile：0.00Abe, 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.
Takeshita, Kenji*; Matsumura, Tatsuro
no journal, ,
no abstracts in English
Ono, Koki*; Okamura, Tomohiro*; Abe, Takumi; Nishihara, Takahiro*; Nakase, Masahiko*; Nishihara, Kenji; Suzuki, Taiga*
no journal, ,
no abstracts in English
Dwijayanto, A. P.*; Nishihara, Kenji; Okamura, Tomohiro*; Nakase, Masahiko*
no journal, ,
NMB4 is a nuclear fuel cycle simulator capable of modelling various nuclear fuel cycle scenarios from front-end to back-end. However, its capability to simulate a Molten Chloride Fast Reactor (MCFR), a subset of Molten Salt Reactor (MSR), had yet to be tested. Verifying NMB4 capability to model MCFR fuel cycle in a nuclear energy system is crucial for determining the limit of applicability and future development of the NMB4 simulator. A mass balance comparison between the NMB4 nuclear fuel cycle simulator and the Monte Carlo code Serpent-2 was then performed. A long-lived marine-based MCFR core with minimal reprocessing was modeled in a Monte-Carlo code as the closest scheme with the depletion capability supported by NMB4. From the results, NMB4 was found to generate an acceptable mass balance compared to Serpent-2, and a simple case study using a marine-based MCFR was subsequently simulated to analyse the mass balance and the disposal area required in a once-through cycle. Several discrepancies in code verification have been discussed, and future developments are suggested.
