Published August 1, 2012 | Version v1
Report Metadata-only

Analysis of the IFA-432, IFA-597, and IFA-597 MOX Fuel Performance Experiments by FRAPCON-3.4

Creators

  • 1. Oak Ridge National Laboratory, TN (United States)

Description

Validation of advanced nuclear fuel modeling tools requires careful comparison with reliable experimental benchmark data. A comparison to industry-accepted codes, that are well characterized, and regulatory codes is also a useful evaluation tool. In this report, an independent validation of the FRAPCON-3.4 fuel performance code is conducted with respect to three experimental benchmarks, IFA-432, IFA-597, and IFA-597mox. FRAPCON was found to most accurately model the mox rods, to within 2% of the experimental data, depending on the simulation parameters. The IFA-432 and IFA-597 rods were modeled with FRAPCON predicting centerline temperatures different, on average, by 21 percent.

Availability note (English)

Available from http://info.ornl.gov/sites/publications/files/Pub36515.pdf; PURL: https://www.osti.gov/servlets/purl/1048727/

Additional details

Identifiers

URL
http://info.ornl.gov/sites/publications/files/Pub36515.pdf; https://www.osti.gov/servlets/purl/1048727/;
DOI
10.2172/1048727;

Publishing Information

Imprint Pagination
67 p.
Report number
ORNL/TM--2012/195

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
43127915
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
BENCHMARKS; EVALUATION; NUCLEAR FUELS; PERFORMANCE; SIMULATION; VALIDATION
Descriptors DEC
ENERGY SOURCES; FUELS; MATERIALS; REACTOR MATERIALS; TESTING

Optional Information

Contract/Grant/Project number
NT0108020; NENT004; AC05-00OR22725
Notes
doi 10.2172/1048727
Funding organization
US Department of Energy (United States)