Thermo-mechanical behavior of all the metallic fuel rods in a sodium-cooled fast reactor-Reference-Cited by-同舟云学术

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Thermo-mechanical behavior of all the metallic fuel rods in a sodium-cooled fast reactor

Published:2018-12 Issue: Volume:339 Page:126-136
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Choi Sun Rock,Lim Jae-Yong,Won Jong Hyuck,Kim June-Hyung,Cheon Jin-Sik

Funder

NRF

MSIP

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

Reference19 articles.

1. User's Guide for TWODANT: A Code Package for Two-dimensional, Diffusion-Accelerated, Neutron Transport, LA-10049-M;Alcouffe,1990

2. Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants;ANS,1983

3. General Safety Design Criteria for a Liquid Metal Reactor Nuclear Power Plant;ANS,1989

4. Design Report of Core T/H Design, SFR-120-DR-462-001;Choi,2017

5. CRBRP Core Assemblies Hot Channel Factors Preliminary Analysis, CRBRP-ARP-0050;Friedland,1980

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