A study on the impact of using a subchannel resolution for modeling of large break loss of coolant accidents-Reference-Cited by-同舟云学术

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A study on the impact of using a subchannel resolution for modeling of large break loss of coolant accidents

Published:2024-11 Issue: Volume:207 Page:110716
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Salko Robert^ORCID,Wysocki Aaron,Hizoum Belgacem,Capps Nathan

Publisher

Elsevier BV

Reference22 articles.

1. A Preliminary Study of Droplet Breakup at PWR Spacer Grids;Adams,1983

2. Development, validation, and assessment of the TRACE thermal-hydraulics systems code;Bajorek,2015

3. Rod bundle heat transfer thermal-hydraulic program;Bajorek;Nucl. Technol.,2019

4. TRACE V5.0 Assessment Manual: Main Report;Bajorek,2012

5. TRACE V5.0 Developmental Assessment, Addendum 7A: V5.0 Patch 7;Bajorek,2022

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Assessment of the CTF subchannel code for modeling a large-break loss-of-coolant accident reflood transient;Annals of Nuclear Energy;2025-01

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