Full-length high-temperature severe fuel damage test No. 1

Technical Report · Sun Aug 01 00:00:00 EDT 1993

DOI:https://doi.org/10.2172/10187144· OSTI ID:10187144

Rausch, W N; Hesson, G M; Pilger, J P; King, L L; Goodman, R L; Panisko, F E

This report describes the first full-length high-temperature test (FLHT-1) performed by Pacific Northwest Laboratory (PNL) in the National Research Universal (NRU) reactor at Chalk River, Ontario, Canada. The test is part of a series of experiments being performed for the NRC as a part of their Severe Fuel Damage Program and is one of several planned for PNL`s Coolant Boilaway and Damage Progression Program. The report summarizes the test design and test plan. it also provides a summary and discussion of the data collected during the test and of the photos taken during the post-test examination. All objectives for the test were met. The key objective was to demonstrate that severe fuel damage tests on full-length fuel bundles can be safely conducted in the NRU reactor.

• Research Organization: Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10187144
• Report Number(s): PNL-5691; ON: DE94000560; TRN: 93:023995
• Resource Relation: Other Information: PBD: Aug 1993
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
NRU REACTOR
RESEARCH PROGRAMS
TESTING
US NRC
FUEL RODS
DAMAGE
REACTOR CORES
MELTDOWN
LOSS OF COOLANT
CORIUM
TEST FACILITIES
REACTOR SAFETY
ENGINEERING DRAWINGS
EXPERIMENTAL DATA
220900
220600
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS