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Definition of the neutronics benchmark of the NuScale-like core

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This paper defines a 3D full core neutronics benchmark which is based on the NuScale small modular reactor (SMR) concept. The paper provides a detailed description of the NuScale-like core, a list of expected outputs, and a reference solution to the benchmark exercises obtained with the Monte Carlo code Serpent. The benchmark was developed in the framework of the Euratom McSAFER project and can be used for verification of computational chains dedicated to 3D full-core neutronics simulations of water cooled SMRs. The paper is supplemented with a digital data set to ease the modeling process

Abstract

This paper defines a 3D full core neutronics benchmark which is based on the NuScale small modular reactor (SMR) concept. The paper provides a detailed description of the NuScale-like core, a list of expected outputs, and a reference solution to the benchmark exercises obtained with the Monte Carlo code Serpent. The benchmark was developed in the framework of the Euratom McSAFER project and can be used for verification of computational chains dedicated to 3D full-core neutronics simulations of water cooled SMRs. The paper is supplemented with a digital data set to ease the modeling process

참고문헌 (9)

  1. B. Chanaron, "Overview of the NURESAFE European Project", Nuclear Engineering and Design, 321, pp.1~7 (2017), Elsevier BV[DOI]
  2. Christophe Demazière, "Advanced numerical simulation and modelling for reactor safety − contributions from the CORTEX, HPMC, McSAFE and NURESAFE projects", EPJ Nuclear Sciences & Technologies, 6, pp.42~ (2020), EDP Sciences[DOI]
  3. V. H. Sanchez-Espinoza, "THE McSAFE PROJECT - HIGH-PERFORMANCE MONTE CARLO BASED METHODS FOR SAFETY DEMONSTRATION: FROM PROOF OF CONCEPT TO INDUSTRY APPLICATIONS", EPJ Web of Conferences, 247, pp.06004~ (2021), EDP Sciences
  4. NRC to Issue Rule Certifying NuScale Small Modular Reactor, "US NRC", US NRC, Office of Public Affairs, ~ (2022)
  5. (2022)[URL]
  6. L.L.C. NuScale Power, "NuScale Standard Plant Design Certification Application, Chapter Four, Reactor", ~ (2020)
  7. Benchmark for Evaluation and Validation of Reactor Simulations (BEAVRS), "N. Horelik", Massachusetts Institute of Technology, ~ (2013)
  8. Ulrich Rohde, "The reactor dynamics code DYN3D – models, validation and applications", Progress in Nuclear Energy, 89, pp.170~190 (2016), Elsevier BV[DOI]
  9. V. Sahlberg, "Development and first results of a new rectangular nodal diffusion solver of Ants", PHYSOR 2018 (2018)

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