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Bachmann, A. M.*; Richards, S.*; Feng, B.*; Nishihara, Kenji; Abe, Takumi
Proceedings of International Conference on Nuclear Fuel Cycle (GLOBAL2024) (Internet), 4 Pages, 2024/10
This work demonstrates the value of code verification as an initial step in utilizing fuel cycle simulation. Cyclus and NMB are open-source fuel cycle simulators that provide computational modeling of nuclear fuel cycle alternatives and were chosen by Argonne National Laboratory and Japan Atomic Energy Agency (JAEA), respectively, for a multi-year collaboration on fuel cycle benchmarks. Both are relatively new and can be improved after conducting a rigorous code-to-code comparison. Initial verification of these simulators was performed using a set of hypothetical scenarios for once-through and multi-recycle fuel cycles. The results of this work identify how differences in scenario definitions and the modeling methodologies of the two simulators lead to differences in results in material inventories, mass flows, and other important metrics for fuel cycle assessments.
Nishihara, Kenji; Takeshita, Kenji*; Shimada, Takashi*; Aizawa, Naoto*; Nakase, Masahiko*; Wada, Satoshi*; Wakasaki, Shingo*; Matsui, Minefumi*; Yasunaga, Yoshiaki*; Okamura, Tomohiro*; et al.
no journal, ,
Nuclear fuel cycle simulators (NFCSs) are widely used but suffer from uncertainties and a lack of benchmarking for large, complex scenarios. To address this, the Atomic Energy Society of Japan established a committee to develop standard reactor libraries and benchmarking scenarios. Multiple Japanese NFCSs will analyze these scenarios, and the results will be published to improve NFCS reliability.
Nishihara, Kenji; Takeshita, Kenji*; Shimada, Takashi*; Aizawa, Naoto*; Nakase, Masahiko*; Wada, Satoshi*; Wakasaki, Shingo*; Matsui, Minefumi*; Yasunaga, Yoshiaki*; Okamura, Tomohiro*; et al.
no journal, ,
This study presents benchmark activities conducted by a research committee of the Atomic Energy Society of Japan to enhance the reliability of nuclear fuel cycle simulators. Standard reactor libraries and phased benchmark scenarios were developed and applied to stepwise validation exercises. The results clarify consistency of simulators on burnup calculation and impact of human error. The results for 11 large-scale scenarios are also provided for future activity.