Contribution to the validation of the MORET 5 code using the CROCUS reactor physics benchmark
| Autor: | B. Cochet, Nicolas Leclaire |
|---|---|
| Přispěvatelé: | PSN-RES/SNC/LN, Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Commissariat à l'Energie Atomique (CEA) |
| Jazyk: | angličtina |
| Rok vydání: | 2021 |
| Předmět: |
Data processing
020209 energy Nuclear engineering Nuclear data 02 engineering and technology 01 natural sciences 010305 fluids & plasmas [SPI]Engineering Sciences [physics] Nuclear Energy and Engineering Criticality 0103 physical sciences 0202 electrical engineering electronic engineering information engineering Benchmark (computing) Code (cryptography) Sensitivity (control systems) Energy (signal processing) Physical quantity |
| Zdroj: | Annals of Nuclear Energy Annals of Nuclear Energy, Elsevier Masson, 2021, 155, pp.1-12. ⟨10.1016/j.anucene.2021.108164⟩ |
| ISSN: | 0306-4549 |
| DOI: | 10.1016/j.anucene.2021.108164⟩ |
| Popis: | The present paper focuses on the modeling of the CROCUS reactor with the French MORET 5 continuous energy code and compares keff, anti-reactivity effects (variation of keff normalized to keff due to the insertion of an absorber), sensitivity coefficients and kinetics parameters with those provided by other reference codes. The aim is mainly to extend the experimental validation/verification database of the MORET 5 code to use reactor physics applications. A suite of about 1400 benchmarks is already available for criticality but only a few are dedicated to reactor physics applications. The CROCUS reactor configurations therefore constitute an opportunity to test and improve the implementation of kinetics parameters and sensitivity coefficients in the code and make a verification of these physical quantities through the comparison with other codes such as MCNP. Moreover, it offers the opportunity to quantify the effect of nuclear data processing through the use of two different data processing codes. |
| Databáze: | OpenAIRE |
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