Initial Benchmark Comparison of the Open-Source Cyclus and NMB Fuel Cycle Simulators

Verification exercises between fuel cycle simulators are important for understanding how the methodology and capability differences between the simulators affect the results.This work performs an initial verification exercise with the Cyclus and NMB fuel cycle simulators.The exercise compares the results of the two codes in three simple fuel cycle scenarios: a once-through scenario with a pressurized water reactor, a limited recycle scenario with a pressurized water reactor, and a continuous recycle scenario with a pressurized water reactor and a sodium fast reactor.The results of this exercise highlight the differences in the codes' methodologies to determine when fresh fuel is fabricated and to model fuel depletion.These differences affect where material is located in a scenario but do not greatly affect the total amount of material in a scenario.

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Publication Details

Journal
Progress in Nuclear Science and Technology
Published
2025-09-30
DOI
https://doi.org/10.15669/pnst.8.11
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
0.00

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article

Initial Benchmark Comparison of the Open-Source Cyclus and NMB Fuel Cycle Simulators

Scott Richards, Kenji Nishihara, Amanda M. Bachmann, Takumi Abe et al.
Progress in Nuclear Science and Technology
Nuclear reactor physics and engineering
article

Initial Benchmark Comparison of the Open-Source Cyclus and NMB Fuel Cycle Simulators

Scott Richards, Kenji Nishihara, Amanda M. Bachmann, Takumi Abe, Bo Feng
article en

Abstract

Verification exercises between fuel cycle simulators are important for understanding how the methodology and capability differences between the simulators affect the results.This work performs an initial verification exercise with the Cyclus and NMB fuel cycle simulators.The exercise compares the results of the two codes in three simple fuel cycle scenarios: a once-through scenario with a pressurized water reactor, a limited recycle scenario with a pressurized water reactor, and a continuous recycle scenario with a pressurized water reactor and a sodium fast reactor.The results of this exercise highlight the differences in the codes' methodologies to determine when fresh fuel is fabricated and to model fuel depletion.These differences affect where material is located in a scenario but do not greatly affect the total amount of material in a scenario.

Progress in Nuclear Science and TechnologyVol. 8(0)
Japan Atomic Energy Agency (JP), Argonne National Laboratory (US)
U.S. Department of Energy, National Nuclear Security Administration, Argonne National Laboratory
Openalex Percentile: Top 59%
Nuclear reactor physics and engineering
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