Enabling BWR fuel rod analysis in the BISON fuel performance code
Nuclear fuel vendors around the world are pursuing approaches to sustain the existing nuclear reactor fleet con- sisting primarily of pressurized-water reactors (PWRs) and boiling-water reactors (BWRs). To support the industry’s efforts, advanced modeling and simulation tools need to be capable of analyzing both legacy reactor concepts. BWR fuel rods are significantly different than those […]
Development and Refinement of Bison Models for Higher Burnup Application
Electric Power Research Institute (EPRI) is an international research organization funded by orga- nizations in the energy and government sectors. The company conducts research to tackle the energy challenges of its member organizations. In support of the U.S. nuclear industry, EPRI and Idaho National Laboratory were awarded a U.S. Department of Energy Technology Commercialization Fund […]
Axial Gas Communication Modeling with BISON
Overview presentation of the methodology used for axial gas communication implementation in BISON. Incorporates work from a previous LDRD coupled with ongoing efforts in a technology commercialization fund (TCF) project.
Axial Gas Communication Modeling in the BISON Fuel Performance Code
Presentation requested by our collaborators on the technology commercialization fund project. This presentation provides an overview of the axial gas communication capabilities in the BISON fuel performance code. A discussion on models that impact gas communication, the theory behind the implementation, verification, and validation cases are presented.
Compare Mechanistic Predictions for Doped UO2 Mechanical Response and Other Properties with Empirical Models and Experimental Measurements
The U.S. Department of Energy’s Nuclear Energy Advanced Modeling and Simulation program develops predictive capabilities using computational methods for the analysis and design of advanced reactor and fuel cycle systems. This program has been supporting the development of BISON, a high-fidelity, high resolution fuel performance tool at the engineering scale. As part of its development, […]
Assessment approach to advanced fuel models
This document constitutes completion of the NEAMS milestone M3MS-21IN0201016, which is titled: Assessment of advanced fuel improvements. In this report we present: (1) simulations of separate effects creep tests for uranium alloy and HT-9, (2) examples of standardizing and updating metallic fuel assessments to include the latest models and key output figures of merit, which […]
Advancements in modeling fuel pulverization and cladding behavior during a LOCA
During a loss of coolant accident (LOCA), there is the possibility of nuclear fuel rods to undergo a three step process known as fuel fragmentation, relocation, and dispersal (FFRD). The chance of FFRD occurring increases as the fuel burnup increases. To support the nuclear industry’s desire to increase the discharge burnup of nuclear fuels in […]
Advancements in modeling fuel pulverization and cladding behavior during a LOCA
During a loss-of-coolant accident (LOCA), it is possible for nuclear fuel rods to undergo a three-step process known as fuel fragmentation, relocation, and dispersal (FFRD). The chance of FFRD occurring increases as the fuel burnup increases. To support the nuclear industry’s desire to increase the discharge burnup of nuclear fuels in light-water reactors (LWRs), it […]