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FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits

  • Published:2021-11 Issue:11 Volume:53 Page:3741-3758
  • ISSN:1738-5733
  • Container-title:Nuclear Engineering and Technology
  • language:en
  • Short-container-title:Nuclear Engineering and Technology

Author:

Khvostov G.,Gorzel A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference32 articles.

1. Pressurized-water reactor control rod ejection and boiling water reactor control rod drop accidents;U.S. NRC Regulatory Guide RG,2020

2. Reactor Core, Fuel Assemblies and Control Rods: Design and Operation Guideline for Swiss Nuclear Installations;ENSI-G20/e,2015

3. Fuel analysis and licensing Code: FALCON MOD01: volume 1: theoretical and numerical bases;EPRI Report 1011307,2004

4. Fuel analysis and licensing Code: FALCON MOD01: volume 2: code user’s guide;EPRI Report 1011308,2004

5. FALCON-PSI Code Management Report;Khvostov,2020

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1. Interpretation of the online measurement data for selected tests of the RISOE-III project;Journal of Nuclear Materials;2024-10

2. Verification of the Coupled Code PARCS/TWOPORFLOW with Rod Ejection Accident Calculations for Small Modular Reactors;Nuclear Science and Engineering;2024-06-13

3. Calibration and Validation of thermal fuel behaviour models based on the first case of the first IAEA CRP FUMEX;Journal of Nuclear Materials;2023-10

4. Insights into fuel behaviour during relatively fast thermal transients based on calculations for two tests of the Halden IFA-507 experiment;Nuclear Engineering and Technology;2023-10

5. Application of algorithm with variable step in time to solve problem of contact interaction of fuel element with account of creep;PROCEEDINGS OF INTERNATIONAL CONFERENCE OF YOUNG SCIENTISTS AND STUDENTS “TOPICAL PROBLEMS OF MECHANICAL ENGINEERING” ToPME 2021: Mechanical Engineering Research Institute of the Russian Academy of Sciences (IMASH RAN);2023
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