Conceptualization of the Micro Research Reactor Cooled by Heat Pipes (MRR-HP), Part-I: neutronics analyses-Reference-Cited by-同舟云学术

Conceptualization of the Micro Research Reactor Cooled by Heat Pipes (MRR-HP), Part-I: neutronics analyses

Published:2022-08-21 Issue:3 Volume:60 Page:299-319
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Allaf Mohammad¹^ORCID,Okamoto Koji²,Erkan Nejdet³^ORCID

Affiliation:

1. Nuclear Engineering and Management Department, The University of Tokyo, Tokyo, Japan

2. Nuclear Professional School, The University of Tokyo, Shirane, Ibaraki, Japan

3. Fusion Technology Facility, United Kingdom Atomic Energy Authority (UKAEA), Rotherham, UK

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2022.2098197

Reference47 articles.

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3. IAEA. In: Use of neutron beams for low and medium flux research reactors: R&D programmes in material science. IAEA-TECDOC-836. Vienna: International Atomic Energy Agency; 1993.

4. IAEA. In: Use of neutron beams for low and medium flux research reactors: radiography and materials characterization. IAEA-TECDOC-837. Vienna: International Atomic Energy Agency. 1993.

5. IAEA. History, development and future of triga research reactors. History, development and future of triga research reactors Technical Report Series No.482. Vienna: International Atomic Energy Agency; 2016.

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1. Concept design and neutronics analysis of a heat pipe cooled nuclear reactor with CERMET fuel;Annals of Nuclear Energy;2023-11

2. Conceptualization of the micro research reactor cooled by heat pipes (MRR-HP), part-II: safety analyses;Journal of Nuclear Science and Technology;2023-01-10