Comparative analysis of fuel burnup calculations of fourth-generation European fast reactors-Reference-Cited by-同舟云学术

Comparative analysis of fuel burnup calculations of fourth-generation European fast reactors

Published:2023-08-14 Issue:5 Volume:88 Page:593-603
ISSN:0932-3902
Container-title:Kerntechnik
language:en
Short-container-title:

Author:

Ibrahim Amr¹^ORCID

Affiliation:

1. High Institute for Engineering and Technology at Al-Obour , Cairo , Egypt

Abstract

Abstract The sustainability of nuclear energy implies the continuous research and development of fast reactor technology. This work represents a comparative analysis of fuel burnup calculations of three commercial-level fast spectrum concepts which are under research and development in Europe. The investigated designs are the European Sodium-cooled Fast Reactor, the European Lead-cooled Fast Reactor, and the European Gas-cooled Fast Reactor. MCNPX transport code was used to design three representative fuel assemblies of these fourth-generation concepts to analyze and compare their neutronic and safety parameters. The neutronic and safety analysis in this work includes the evolution of infinite multiplication factor and fissile inventory, neutron yield, the average energy of neutrons causing fission, neutron energy spectrum, neutron generation time, Doppler reactivity effect, effective delayed neutron fraction, and coolant void reactivity coefficient. The fuel burnup results showed that the ESFR is superior regarding the reactivity swing and breeding of fissile 239Pu. On the other hand, analysis of safety parameters results showed that they depend mainly on fuel composition rather than on other design specifications.

Publisher

Walter de Gruyter GmbH

Subject

Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation

Link

https://www.degruyter.com/document/doi/10.1515/kern-2023-0019/pdf

Reference34 articles.

1. Artioli, C., Grasso, G., and Petrovich, C. (2010). A new paradigm for core design aimed at the sustainability of nuclear energy: the solution of the extended equilibrium state. Ann. Nucl. Energy 37: 915–922, https://doi.org/10.1016/j.anucene.2010.03.016.

2. Escorcia-Ortiz and François, J.L. (2018). Neutronic study of an ASTRID-like fast reactor core with thorium-based fuel. Nucl. Eng. Des. 339: 159–170, https://doi.org/10.1016/j.nucengdes.2018.09.007.

3. Fazzolare, R. (1977). Gas-cooled fast breeder reactor designs with advanced fuel and cladding. Nucl. Eng. Des. 40: 191–201, https://doi.org/10.1016/0029-5493(77)90160-1.

4. Fiorini, G.L. and Vasile, A. (2011). European commission – 7th framework programme, the collaborative project on European sodium fast reactor (CP ESFR). Nucl. Eng. Des. 241: 3461–3469, https://doi.org/10.1016/j.nucengdes.2011.01.052.

5. Galahom, A.A. and Ibrahim, A. (2022). Integrated analysis to investigate the viability of using Thorium-based fuel instead of traditional fuel in CANDU reactor. Nucl. Eng. Des. 398: 111969, https://doi.org/10.1016/j.nucengdes.2022.111969.