skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: LIGHT WATER REACTOR ACCIDENT TOLERANT FUELS IRRADIATION TESTING

Conference ·
OSTI ID:1236847

The purpose of Accident Tolerant Fuels (ATF) experiments is to test novel fuel and cladding concepts designed to replace the current zirconium alloy uranium dioxide (UO2) fuel system. The objective of this Research and Development (R&D) is to develop novel ATF concepts that will be able to withstand loss of active cooling in the reactor core for a considerably longer time period than the current fuel system while maintaining or improving the fuel performance during normal operations, operational transients, design basis, and beyond design basis events. It was necessary to design, analyze, and fabricate drop-in capsules to meet the requirements for testing under prototypic LWR temperatures in Idaho National Laboratory's Advanced Test Reactor (ATR). Three industry led teams and one DOE team from Oak Ridge National Laboratory provided fuel rodlet samples for their new concepts for ATR insertion in 2015. As-built projected temperature calculations were performed on the ATF capsules using the BISON fuel performance code. BISON is an application of INL’s Multi-physics Object Oriented Simulation Environment (MOOSE), which is a massively parallel finite element based framework used to solve systems of fully coupled nonlinear partial differential equations. Both 2D and 3D models were set up to examine cladding and fuel performance.

Research Organization:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
AC07-05ID14517
OSTI ID:
1236847
Report Number(s):
INL/CON-15-34949
Resource Relation:
Conference: TopFuel 2015, Zurich, Switzerland, 9/13/2015 - 9/17/2015
Country of Publication:
United States
Language:
English

Similar Records

Critical processes and parameters in the development of accident tolerant fuels drop-in capsule irradiation tests
Journal Article · Tue Dec 01 00:00:00 EST 2015 · Nuclear Engineering and Design · OSTI ID:1236847

EVALUATION OF ENHANCED ACCIDENT TOLERANT FUELS
Conference · Tue Sep 01 00:00:00 EDT 2015 · OSTI ID:1236847

Comparison of Subdivided Versus Full-Length Fuel Pin Burnup in the ATF-2 Safety Analysis
Journal Article · Wed Jun 15 00:00:00 EDT 2016 · Transactions of the American Nuclear Society · OSTI ID:1236847