Dissertation/Thesis Abstract

Fuel Plate Failure Experiments and Analyses in Irradiated U-10Mo Alloy
by Rice, Francine Joyce, M.S., University of Idaho, 2017, 138; 10259325
Abstract (Summary)

The Materials Management and Minimization (M3) Program intends to qualify a new high-density low-enriched-uranium (LEU) U–Mo monolithic fuel to enable conversion of five US high-performance research reactors (USHPRRs). This thesis presents the preliminary results and discussions related to post-irradiation blister anneal studies and fission product release scoping studies performed on U–Mo monolithic fuel plates.

Blister anneal testing on irradiated fuel plates is a temperature-resolved failure-threshold measurement technique historically used to assess fuel plate stability under off-normal operating conditions. The effects of fuel composition, geometry, fission density, and irradiation conditions are presented herein as parameters that were investigated for their impact on blister-threshold temperatures. The fission-product-transport scoping study successfully characterized the release, transport and temperature-resolved deposition behavior of iodine and cesium. Two failure temperatures were evaluated: 600 and 1250°C. Testing was performed in the main hot cell at the Materials and Fuels Complex located at Idaho National Laboratory.

Indexing (document details)
Advisor: Charit, Indrajit
Commitee: Christensen, Richard, Wachs, Daniel
School: University of Idaho
Department: Nuclear Engineering
School Location: United States -- Idaho
Source: MAI 56/04M(E), Masters Abstracts International
Source Type: DISSERTATION
Subjects: Nuclear engineering, Materials science
Keywords: Blister anneal, Blister threshold, Fission density, Fission product release, Fuel failure, Source term
Publication Number: 10259325
ISBN: 9781369822212
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