Development and validation of the lead-bismuth cooled reactor system code based on a fully implicit homogeneous flow model-Reference-Cited by-同舟云学术

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Development and validation of the lead-bismuth cooled reactor system code based on a fully implicit homogeneous flow model

Published:2023-11 Issue: Volume: Page:
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Li Ge,Jingxin Wang,Kun Fan,Jie Zhang,Jianqiang Shan

Funder

China National Nuclear Corporation

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference26 articles.

1. Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis;Ma;Nucl. Eng. Des.,2006

2. Overview of the Use of ATHENA for Thermal-Hydraulic Analysis of Systems with Lead-Bismuth Coolant;Davis,2000

3. Status of the SAS4A/SASSYS-1 safety analysis code[R];Fanning,2017

4. SIMMER-III and SIMMER-IV Safety Code Development for Reactors with Transmutation Capability;Maschek,2005

5. Applicability Development and Application of System Safety Analysis Program in Supercritical Water-Cooled Reactor and Sodium-Cooled Fast Reactor [D];Zhou,2013

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