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Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 3: Thermal hydraulic evaluation of large break LOCA under high-burnup conditions

Journal Article · · Annals of Nuclear Energy
 [1];  [2];  [1];  [1]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  2. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)
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Increasing the peak rod average burnup of pressurized water reactor (PWR) fuel beyond 62 GWd/tU may increase fuel fragmentation, relocation, and dispersal (FFRD) susceptibility during a large break loss of coolant accident (LBLOCA). TRACE thermal hydraulic (TH) LBLOCA analyses were performed for a realistic 24-month high-burnup PWR equilibrium cycle, to inform subsequent transient BISON high-burnup FFRD susceptibility evaluations. Realistic LBLOCA systems behavior was first established by configuring to and comparing with the BEMUSE OECD LBLOCA benchmark. Fuel and operating conditions were then applied from high-burnup VERA depletion calculations. LBLOCA simulations were performed for 281 selected high-burnup rods, for which transient TH boundary conditions were collected for later use in BISON. The TRACE results indicated that rod linear heat rate (rather than burnup) is the main predictor of peak cladding temperature (PCT) during the event. PCT typically occurred at a local burnup lower than the rod-average burnup, especially for twice-burned fuel.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE). Advanced Fuels Campaign (AFC)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1997778
Journal Information:
Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Journal Issue: N/A Vol. 192; ISSN 0306-4549
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (13)

Application of code scaling applicability and uncertainty methodology to the large break loss of coolant journal November 1998
AP1000® Large-Break LOCA BEPU analysis with TRACE code journal November 2015
Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 1: Overview and code coupling strategies journal October 2023
LBLOCA analysis for the Maanshan PWR nuclear power plant using TRACE journal January 2012
The Virtual Environment for Reactor Applications (VERA): Design and architecture journal December 2016
AREVA's realistic large break LOCA analysis methodology journal July 2005
Validating the BISON fuel performance code to integral LWR experiments journal May 2016
Estimation of coping time in pressurized water reactors for near term accident tolerant fuel claddings journal October 2018
Assessment of coated cladding impact on large-break LOCA with TRACE-DAKOTA journal April 2021
Full core LOCA safety analysis for a PWR containing high burnup fuel journal August 2021
CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pressurized water reactors journal October 2022
Bootstrapped-ensemble-based Sensitivity Analysis of a trace thermal-hydraulic model based on a limited number of PWR large break loca simulations journal September 2016
BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms journal March 2021

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
FRD
LOCA
high-burnup
reactor safety
thermal hydraulics