Neutronic study of an ASTRID-like fast reactor core with thorium-based fuel-Reference-Cited by-同舟云学术

Neutronic study of an ASTRID-like fast reactor core with thorium-based fuel

Published:2018-12 Issue: Volume:339 Page:159-170
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Escorcia-Ortiz Daniel,François Juan-Luis

Funder

CONACYT

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference15 articles.

1. Bortot, S., et al., 2015. European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficients. In: Proceedings of ICAPP 2015, Nice (France), May 03-06, 2015, 15, pp. 668-676.

2. CEA, 2012. CEA Report – Nuclear Energy Division, 4th Generation Sodium-Cooled Fast Reactors – The ASTRID Technological Demonstrator.

3. ENDF/B-VII. 0: next generation evaluated nuclear data library for nuclear science and technology;Chadwick;Nucl. Data Sheets,2006

4. Status of the ASTRID core at the end of the preconceptual design phase 1;Chenaud;Nucl. Eng. Technol.,2013

5. Commissariat à l’énergie atomique, 2012. The ASTRID Technological Demonstrator, Saclay, France.

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1. Comparative analysis of fuel burnup calculations of fourth-generation European fast reactors;Kerntechnik;2023-08-14

2. Neutronic performance of a thorium based mixed oxide fuel in a burner sodium-cooled fast reactor;Energy;2020-12

3. Comparative study of the neutronic performance of thorium-based metallic fuel and MOX fuel in an ASTRID-like fast reactor core;Nuclear Engineering and Design;2019-06

4. Analysis of the use of thorium in the GFR2400 gas-cooled fast reactor;Nuclear Engineering and Design;2019-03