Modeling of sodium-cooled fast reactor core – A sensitivity study on number of core channels and axial meshes-Reference-Cited by-同舟云学术

Modeling of sodium-cooled fast reactor core – A sensitivity study on number of core channels and axial meshes

Published:2023-03 Issue: Volume:403 Page:112136
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Vikram G.,Riyas A.,Bachchan Abhitab,Rajendrakumar M.,Devan K.,Natesan K.

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

Reference13 articles.

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2. An Assessment of Corewide Coherency Effects in the Multichannel Modeling of the Initiating Phase of a Severe Accident in a Sodium Fast Reactor;Guyot;Nucl. Technol.,2014

3. NEWPERT - Perturbation Code for Two Dimensional Diffusion Equation;John,1984

4. BNAB-93 Group Data Library Part 1: Nuclear Data for the Calculation of Neutron and Photon Radiation Fields;Manturov,1997

5. Manturov, G.N. et al. 1998. Description of the CONSYST2 Code System for Applying the ABBN-93 Nuclear Data Set to Different Applications. Report obtained from IPPE under the contract on “Co-operation in Reactor Physics” between IGCAR and IPPE.

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