Published December 15, 2010 | Version v1
Report

Analysis of mixed-oxide fuel behavior during RIA tests using FALCON MOD01

  • 1. ANATECH Corp., 5435 Oberlin Dr. San Diego, CA 92121 (United States)
  • 2. EPRI, 3412 Hillview Ave. Palo Alto, CA 94304 (United States)

Description

This paper summarises the development and verification of a MOX fuel pellet transient gaseous swelling model for use in the FALCON fuel performance code and the evaluation results of MOX fuel rods being tested at the Japan Atomic Energy Agency (JAEA) Nuclear Safety Research Reactor (NSRR). The FALCON code, developed under the sponsorship of EPRI, uses a fully two-dimensional finite element analysis methodology to model the thermal and mechanical behavior of the fuel and cladding under a variety of irradiation conditions. The fuel performance code, integrated with the MOX pellet model, was then applied to the analyses of 8 fuel rods tested at the NSRR facility. The test program is composed of 7 tests conducted at cold conditions and one test performed in the high temperature test capsule. The results show that FALCON demonstrates that pellet thermal expansion combined with gaseous swelling enhanced-PCMI can accurately represent the thermo-mechanical behavior of MOX pellets during rapid energy deposition. The comparison of the calculated results to the available experimental measurements for the MOX tests finds that gaseous swelling enhanced-PCMI is an important contributor to the mechanical behavior of MOX fuel rods under RIA conditions. Moreover, the model development and evaluation process has found that the MOX fuel pellet expansion process leading to cladding deformation can be several times higher than that arising from UO2 pellets at equivalent peak fuel enthalpy levels

Part of:
Nuclear Fuel Behaviour during Reactivity Initiated Accidents. Workshop Proceedings

Additional details

Publishing Information

Imprint Title
Nuclear Fuel Behaviour during Reactivity Initiated Accidents. Workshop Proceedings
Imprint Pagination
433 p.
Journal Page Range
p. 229-244
Report number
NEA-CSNI-R--2010-7

Conference

Title
Workshop on Nuclear Fuel Behaviour during Reactivity Initiated Accidents
Dates
9-11 Sep 2009
Place
Paris (France)

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
Nuclear Energy Agency of the OECD (NEA)
INIS RN
48058408
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; F CODES; FUEL PELLETS; MIXED OXIDE FUELS; PLUTONIUM DIOXIDE; SWELLING; VALIDATION
Descriptors DEC
ACTINIDE COMPOUNDS; CHALCOGENIDES; COMPUTER CODES; DEFORMATION; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PELLETS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; REACTOR MATERIALS; SIMULATION; SOLID FUELS; TESTING; TRANSURANIUM COMPOUNDS

Optional Information

Notes
8 refs.