Coupling of Neutronics and Thermal-Hydraulic Codes for Simulation of the MNSR Reactor-Reference-Cited by-同舟云学术

Coupling of Neutronics and Thermal-Hydraulic Codes for Simulation of the MNSR Reactor

Published:2019-06-17 Issue:11 Volume:193 Page:1276-1289
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Al Zain Jamal¹²^ORCID,El Hajjaji O.¹,El Bardouni T.¹,Boulaich Y.³

Affiliation:

1. Abdelmalek Essaâdi University, Faculty of Sciences, Radiations and Nuclear Systems Laboratory, Tetouan, Morocco

2. Sana’a University, Physics Department, Sana’a, Yemen

3. National Centre of Sciences, Energy and Nuclear Techniques (CNESTEN/CENM), Nuclear Installation Directorate, Rabat, Morocco

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2019.1622927

Reference36 articles.

1. M. ARAI and T. TSUMURA, “Thermal-Hydraulic Conceptual Design of the New Multipurpose Research Reactor Succeeding toJRR-3,” p. 10 (Dec. 2017); http://www.igorr.com/Documents/2017-SYDNEY/Sharefile_full-papers_IGORR%202017/52%20full%20paper%20for%20IGORR18%20conference_arai.pdf.

2. Neutronics and thermal hydraulics analysis of a small modular reactor

3. A Kinetics and Thermal-Hydraulics Capability for the Analysis of Research Reactors

4. Simulation of loss-of-flow transients in research reactors

5. Calculation of temperature coefficients of reactivity for EBR-II kinetic analyses

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