Critical configuration of a SMR based on CAREM 25 using the SERPENT code

Author:

Antonio C. Lima Marco,Henrice Edson,Palma Daniel A.P.,Zacarias Mesquita Amir

Funder

Conselho Nacional de Desenvolvimento Científico e Tecnológico

Brazilian Nuclear Energy Commission

Publisher

Elsevier BV

Reference11 articles.

1. Performance evaluation of nuclear fuel in a reactor based on the CAREM 25;Afonso;Nuclear Engineering and Design,2023

2. CAREM project status;Boado Magan;Sci. Technol. Nucl. Install.,2011

3. Edenius, M., 1976,Studies of the reactivity temperature coefficient in light water reactors(No. INIS-MF--3230). Chalmers Tekniska Hoegskola.

4. Neutronic study of a new generation of small modular pressurized water reactor using Monte-Carlo simulation;Erfaninia;Prog. Nucl. Energy,2016

5. Dynamic simulation of the CEFR control rod drop experiments with the Monte Carlo code serpent;Fridman;Ann. Nucl. Energy,2020

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