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International fuel performance study of fresh fuel experiments for PCMI effects during RIA experiments

Journal Article · · Nuclear Engineering and Design
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  1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
  2. Nuclear and Industrial Engineering (NINE) (Italy)
  3. ALVEL (Czech Republic)
  4. Alternative Energies and Atomic Energy Commission (CEA) (France)
  5. Ecole Polytechnique Federale Lausanne (EPFL) (Switzerland)
  6. HUN-REN Centre for Energy Research (HUN-REN EK-CER) (Hungary)
  7. Research Centre for Energy, Environment and Technology (CIEMAT) (Spain)
  8. Paul Scherrer Inst. (PSI) (Switzerland)
  9. Bhabha Atomic Research Centre (BARC) (India)
  10. Atomic Energy Regulatory Board (AERB) (India)
  11. Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA) (Italy)
  12. Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH (GRS) (Germany)
  13. Technical Research Centre of Finland (VTT) (Finland)
  14. Inst. for Radiological Protection and Nuclear Safety (IRSN) (France)
  15. Japan Atomic Energy Agency (JAEA) (Japan)
  16. North Carolina State University, Raleigh, NC (United States)
  17. US Nuclear Regulatory Commission (NRC), Washington, DC (United States)
  18. TRACTEBEL (Belgium)
  19. UJV (Czech Republic)
  20. Czech Technical Univ. (Czech Republic)
  21. Texas A & M Univ., TX (United States)
+ Show Author Affiliations
This paper presents the results of High-burnup Experiments for Reactivity-initiated Accident (HERA) Modeling & Simulation (M&S) exercise. The HERA project under the Nuclear Energy Agency (NEA) Second Framework for Irradiation Experiments (FIDES-II) program is focused on studying Light Water Reactor (LWR) fuel behavior during Reactivity-Initiated Accident (RIA) conditions. The Part I M&S cases are based on a series of tests in the Transient Reactor Test (TREAT) facility in the United States and the Nuclear Safety Research Reactor (NSRR) in Japan. The purpose of this work is to evaluate the test design to accomplish its goals in establishing clearer understanding of the effects of power pulse width during RIA conditions. Further, the blind predictions using various computational tools have been performed and compared amongst to interpret the behaviors of high burnup fuels during RIA. While many international participants evaluate the thermal–mechanical behavior of fuel rod under different conditions, a considerable scatter of outputs comes out for the cases due to the disparity between codes in predicting mechanical behaviors. In general, however, the results of thermal–mechanical analysis elaborate that nominal design conditions the shorter pulse width tests in NSRR should cause cladding failures while the TREAT tests appear to have more split prediction of failure or not. Furthermore, the sensitivity analysis varying key testing parameters reveals the considerable effect of power pulse width and total energy deposition on prediction of fuel rod failure.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
2503480
Alternate ID(s):
OSTI ID: 2475845
Report Number(s):
INL/JOU--24-77472-Rev000
Journal Information:
Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: - Vol. 430; ISSN 0029-5493
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (15)

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Multidimensional multiphysics simulation of nuclear fuel behavior journal April 2012
Fuel cladding behavior under rapid loading conditions journal February 2016
Threshold stress intensity factor of delayed hydride cracking in irradiated and unirradiated zircaloy-4 cladding journal January 2021
Effect of temperature and hydrogen concentration on the threshold stress intensity factor of radial delayed hydride cracking in fuel cladding journal July 2022
Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes journal December 2023
On the effect of temperature on the threshold stress intensity factor of delayed hydride cracking in light water reactor fuel cladding journal June 2017
Simulation of the fracture behavior of Zircaloy-4 cladding under reactivity-initiated accident conditions with a damage mechanics model combined with fuel performance codes FEMAXI-7 and RANNS journal November 2013
Influence of Cladding-Peripheral Hydride on Mechanical Fuel Failure under Reactivity-Initiated Accident Conditions journal May 2007
Pellet-Cladding Mechanical Interaction Failure Threshold for Reactivity Initiated Accidents for Pressurized Water Reactors and Boiling Water Reactors report June 2013
High-burnup Experiments in Reactivity Initiated Accidents (HERA) report June 2022

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
High burnup fuel
Reactivity initiated accident