| Issue |
EPJ Nuclear Sci. Technol.
Volume 11, 2025
Status and advances of Monte Carlo codes for particle transport simulation
|
|
|---|---|---|
| Article Number | 1 | |
| Number of page(s) | 7 | |
| DOI | https://doi.org/10.1051/epjn/2024020 | |
| Published online | 08 January 2025 | |
https://doi.org/10.1051/epjn/2024020
Regular Article
Review of JAEA’s Monte Carlo codes for nuclear reactor core analysis
Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki, 319-1195, Japan
* e-mail: nagaya.yasunobu@jaea.go.jp
Received:
12
August
2024
Received in final form:
7
October
2024
Accepted:
16
October
2024
Published online: 8 January 2025
Japan Atomic Energy Agency (JAEA) has been developing a general-purpose continuous-energy Monte Carlo code MVP for nuclear reactor core analysis. Recently improvements to MVP have been focused on the development of an advanced neutronics/thermal-hydraulics coupling code. JAEA has also developed a new Monte Carlo solver Solomon for criticality safety analysis. Solomon aims to calculate the criticality of fuel debris. This paper provides an overview of the capabilities and reviews recent applications of MVP and Solomon.
© Y. Nagaya, Published by EDP Sciences, 2025
This is an Open Access article distributed under the terms of the Creative Commons Attribution License (https://creativecommons.org/licenses/by/4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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