TRISO SiC Failure Probability for Reactivity Initiated Accidents in High-Temperature Gas-Cooled Reactors-Reference-Cited by-同舟云学术

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TRISO SiC Failure Probability for Reactivity Initiated Accidents in High-Temperature Gas-Cooled Reactors

Published:2022-08-11 Issue:11 Volume:196 Page:1361-1382
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Ghezzi Carlotta G.¹,Kile Robert F.¹,Brown Nicholas R.¹^ORCID

Affiliation:

1. University of Tennessee – Knoxville, Knoxville, Tennessee 37902

Funder

U.S. Department of Energy Integrated Research Project

Office of Nuclear Energy of the U.S. Department of Energy

Nuclear Science User Facilities

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2022.2097466

Reference43 articles.

1. A review of in-pile fuel safety tests of TRISO fuel forms and future testing opportunities in non-HTGR applications

2. “RELAP5-3D Code Manuals, Volumes I-IV and Appendix A,” INL/MIS-15-36723- V2, Idaho National Laboratory (2015).

3. BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms

4. Behavior of Coated Fuel Particle of High-Temperature Gas-Cooled Reactor under Reactivity-Initiated Accident Conditions

5. Modeling reactivity insertion experiments of TRISO particles in NSRR using BISON

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1. Sensitivity analysis and fuel performance of a control rod withdrawal in the generic fluoride-salt-cooled high temperature reactor;Nuclear Engineering and Design;2024-11

2. Understanding Ag liquid migration in SiC through ex-situ and in-situ Ag-Pd/SiC interaction studies;Materials & Design;2024-09

3. Equilibrium core modeling of a pebble bed reactor similar to the Xe-100 with SCALE;Progress in Nuclear Energy;2024-06

4. Multiphysics Analysis of PLOFC and DLOFC Accidents in the HTGR-TR;Nuclear Technology;2024-03-11

5. Neutronic and thermal-hydraulic calculations under steady state and transient conditions for a generic pebble bed fluoride salt cooled high-temperature reactor;Nuclear Engineering and Design;2023-12

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