Neutronics simulation of China Experimental Fast Reactor start-up tests using FARCOB and ERANOS 2.1 code systems

The neutronics analysis of selected start-up tests conducted from 2010 to 2011 in China Experimental Fast Reactor (CEFR) is carried out using in-house FARCOB and European ERANOS-2.1 code systems as a part of IAEA coordinated research project (CRP) on "Neutronics Benchmark of CEFR Start-Up Tests...

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Bibliographic Details
Published in:Nuclear engineering and design 2022-12, Vol.399, p.112038, Article 112038
Main Authors: Bachchan, Abhitab, Devan, K., Riyas, A.
Format: Article
Language:English
Subjects:
Benchmarks
Control rods
Cores
Diffusion theory
Error analysis
Experimental methods
Fast nuclear reactors
Reactivity
Reactor cores
Reactors
Research projects
Simulation
Sodium
Sodium cooled reactors
Stainless steel
Stainless steels
Uranium
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Summary:The neutronics analysis of selected start-up tests conducted from 2010 to 2011 in China Experimental Fast Reactor (CEFR) is carried out using in-house FARCOB and European ERANOS-2.1 code systems as a part of IAEA coordinated research project (CRP) on "Neutronics Benchmark of CEFR Start-Up Tests". This exercise has the main objective of validation and verification of physical models, neutronics simulation methodology including cross-section libraries that is used for fast reactor core simulations. It is challenging to simulate such a small compact core of enriched uranium with high neutron leakage having stainless steel radial reflector by using 3-D diffusion theory codes. This benchmark analysis used a new simplified approach such as a 3-step method and experimental method for simulating temperature and sodium void reactivity coefficients. Net criticality, control rod worth, temperature and sodium void reactivity coefficients and swap reactivity could be predicted well within their measured error values. This exercise provided an additional validation of the FARCOB system against small sodium-cooled fast reactor (SFR) cores, and it can be confidently used for the design and analysis of small experimental reactor cores.
ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2022.112038