DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Modeling reactivity insertion experiments of TRISO particles in NSRR using BISON

Journal Article · · Journal of Nuclear Materials

This research presents BISON simulations of stress, temperature, and failure probability of tristructural isotropic (TRISO) fuel particles subjected to transient power pulse conditions in the Nuclear Safety Research Reactor (NSRR). We report that by modifying the default elastic properties of the PyC and the UO2 coefficient of thermal expansion correlation, BISON was found to produce suitable agreement with the observed and independently simulated results when appropriate shape and scale Weibull parameters for SiC failure were chosen. The Weibull parameter effects were also explored within the range of SiC failure and were applied using experimental data from hemispherical crush testing.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1606788
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 530; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (32)

libMesh : a C++ library for parallel adaptive mesh refinement/coarsening simulations journal November 2006
Thermal behavior of the HTR-10 under combined PLOFC and ATWS condition initiated by unscrammed control rod withdrawal journal July 2018
The thermal expansion of solid UO2 and (U, Pu) mixed oxides — a review and recommendations journal May 1988
The early history of high-temperature helium gas-cooled nuclear power reactors journal January 1991
Thermophysical properties of uranium dioxide journal March 2000
Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback journal December 2013
A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding journal November 2017
Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics journal April 2018
Handbook of SiC properties for fuel performance modeling journal September 2007
Fabrication and characterization of fully ceramic microencapsulated fuels journal July 2012
Multidimensional multiphysics simulation of TRISO particle fuel journal November 2013
Mechanical characteristics of SiC coating layer in TRISO fuel particles journal November 2013
Effects of thermal treatment on the mechanical integrity of silicon carbide in HTR fuel up to 2200 °C journal August 2014
Microhardness and Young's modulus of high burn-up UO2 fuel journal October 2016
Coated particle fuel: Historical perspectives and current progress journal March 2019
Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing journal October 2020
Safety demonstration tests using high temperature engineering test reactor journal October 2004
Transient tests on blower trip and rod removal at the HTR-10 journal March 2006
The PBMR steady-state and coupled kinetics core thermal-hydraulics benchmark test problems journal March 2006
The 3-D time-dependent transport code TORT-TD and its coupling with the 3D thermal-hydraulic code ATTICA3D for HTGR applications journal October 2012
Reactivity considerations for the on-line refuelling of a pebble bed modular reactor—Illustrating safety for the most reactive core fuel load journal October 2012
An endothermic chemical process facility coupled to a high temperature reactor. Part I: Proposed accident scenarios within the chemical plant journal May 2012
First elevated-temperature performance testing of coated particle fuel compacts from the AGR-1 irradiation experiment journal May 2014
The ATWS analysis of one control rod withdraw out of the HTR-10GT core in addition with bypass valve failure journal May 2014
Evaluation of the mechanical performance of silicon carbide in TRISO fuel at high temperatures journal September 2016
Initial results from safety testing of US AGR-2 irradiation test fuel journal April 2018
Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON journal August 2018
Measurement and Evaluation on Pulsing Characteristics and Experimental Capability of NSRR journal March 1977
Research and Development of HTTR Coated Particle Fuel journal June 1991
High Power Transient Characteristics and Capability of NSRR journal March 2002
Behavior of Coated Fuel Particle of High-Temperature Gas-Cooled Reactor under Reactivity-Initiated Accident Conditions journal November 2010
Evaluation of the Fracture Strength for Silicon Carbide Layers in the Tri-Isotropic-Coated Fuel Particle journal January 2007