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

Abstract

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.

Authors:
 [1]; ORCiD logo [2]; ORCiD logo [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1606788
Alternate Identifier(s):
OSTI ID: 1580317
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 530; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; NSRR; TRISO; BISON; Reactivity; Silicon carbide; Fracture

Citation Formats

Schappel, Danny, Brown, Nicholas R., and Terrani, Kurt A. Modeling reactivity insertion experiments of TRISO particles in NSRR using BISON. United States: N. p., 2019. Web. doi:10.1016/j.jnucmat.2019.151965.
Schappel, Danny, Brown, Nicholas R., & Terrani, Kurt A. Modeling reactivity insertion experiments of TRISO particles in NSRR using BISON. United States. https://doi.org/10.1016/j.jnucmat.2019.151965
Schappel, Danny, Brown, Nicholas R., and Terrani, Kurt A. Fri . "Modeling reactivity insertion experiments of TRISO particles in NSRR using BISON". United States. https://doi.org/10.1016/j.jnucmat.2019.151965. https://www.osti.gov/servlets/purl/1606788.
@article{osti_1606788,
title = {Modeling reactivity insertion experiments of TRISO particles in NSRR using BISON},
author = {Schappel, Danny and Brown, Nicholas R. and Terrani, Kurt A.},
abstractNote = {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.},
doi = {10.1016/j.jnucmat.2019.151965},
journal = {Journal of Nuclear Materials},
number = C,
volume = 530,
place = {United States},
year = {2019},
month = {12}
}

Journal Article:

Citation Metrics:
Cited by: 10 works
Citation information provided by
Web of Science

Save / Share:

Works referenced in this record:

The early history of high-temperature helium gas-cooled nuclear power reactors
journal, January 1991


Coated particle fuel: Historical perspectives and current progress
journal, March 2019


First elevated-temperature performance testing of coated particle fuel compacts from the AGR-1 irradiation experiment
journal, May 2014


Initial results from safety testing of US AGR-2 irradiation test fuel
journal, April 2018


Behavior of Coated Fuel Particle of High-Temperature Gas-Cooled Reactor under Reactivity-Initiated Accident Conditions
journal, November 2010

  • Umeda, Miki; Sugiyama, Tomoyuki; Nagase, Fumihisa
  • Journal of Nuclear Science and Technology, Vol. 47, Issue 11
  • DOI: 10.1080/18811248.2010.9711663

Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing
journal, October 2020


An endothermic chemical process facility coupled to a high temperature reactor. Part I: Proposed accident scenarios within the chemical plant
journal, May 2012


Transient tests on blower trip and rod removal at the HTR-10
journal, March 2006


Thermal behavior of the HTR-10 under combined PLOFC and ATWS condition initiated by unscrammed control rod withdrawal
journal, July 2018


The ATWS analysis of one control rod withdraw out of the HTR-10GT core in addition with bypass valve failure
journal, May 2014


Safety demonstration tests using high temperature engineering test reactor
journal, October 2004


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


The PBMR steady-state and coupled kinetics core thermal-hydraulics benchmark test problems
journal, March 2006


High Power Transient Characteristics and Capability of NSRR
journal, March 2002

  • Nakamura, Takehiko; Katanishi, Shoji; Kashima, Yoichi
  • Journal of Nuclear Science and Technology, Vol. 39, Issue 3
  • DOI: 10.1080/18811248.2002.9715184

Measurement and Evaluation on Pulsing Characteristics and Experimental Capability of NSRR
journal, March 1977


A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding
journal, November 2017


libMesh : a C++ library for parallel adaptive mesh refinement/coarsening simulations
journal, November 2006

  • Kirk, Benjamin S.; Peterson, John W.; Stogner, Roy H.
  • Engineering with Computers, Vol. 22, Issue 3-4
  • DOI: 10.1007/s00366-006-0049-3

Multidimensional multiphysics simulation of TRISO particle fuel
journal, November 2013


Microhardness and Young's modulus of high burn-up UO2 fuel
journal, October 2016


Handbook of SiC properties for fuel performance modeling
journal, September 2007


The thermal expansion of solid UO2 and (U, Pu) mixed oxides — a review and recommendations
journal, May 1988


Research and Development of HTTR Coated Particle Fuel
journal, June 1991


Evaluation of the Fracture Strength for Silicon Carbide Layers in the Tri-Isotropic-Coated Fuel Particle
journal, January 2007


Mechanical characteristics of SiC coating layer in TRISO fuel particles
journal, November 2013


Evaluation of the mechanical performance of silicon carbide in TRISO fuel at high temperatures
journal, September 2016


Effects of thermal treatment on the mechanical integrity of silicon carbide in HTR fuel up to 2200 °C
journal, August 2014


Fabrication and characterization of fully ceramic microencapsulated fuels
journal, July 2012


Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON
journal, August 2018