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

Title: Pre- and postirradiation evaluation of fuel in capsule HRB-14. [HTGR]

Abstract

Capsule HRB-14 was irradiated jointly by Oak Ridge National Laboratory and General Atomic Company (GA). This report covers the pre- and postirradiation characterization and evaluation of the GA fuel. The experiment was primarily to characterize the irradiation performance of TRISO-coated low-enriched (Th,U)O/sub 2/, UC/sub 0/ /sub 7/O/sub 0/ /sub 5/, and UO/sub 2/ particles and TRISO ThO/sub 2/ particles. Twenty cured-in-place fuel rods containing the fuel particles were irradiated at 960/sup 0/ to 1130/sup 0/C. The fluence was 4.5 to 8.3 x 10/sup 25/ n/m/sup 2/ (E > 29 fJ)/sub HTGR/. The fertile burnup was 4.1% to 8.5% fissions per initial metal atom (FIMA); the mixed oxide burnup was 14.5% to 19.3% FIMA; the uranium fissile burnup was 27.9% to 29.5% FIMA.

Authors:
Publication Date:
Research Org.:
General Atomic Co., San Diego, CA (USA)
OSTI Identifier:
6772940
Report Number(s):
GA-A-15969
TRN: 81-000850
DOE Contract Number:  
AT03-76ET35300
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; COATED FUEL PARTICLES; PHYSICAL RADIATION EFFECTS; HTGR TYPE REACTORS; THORIUM OXIDES; URANIUM CARBIDES; URANIUM DIOXIDE; BURNUP; FUEL RODS; MICROSTRUCTURE; PERFORMANCE TESTING; ACTINIDE COMPOUNDS; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; CRYSTAL STRUCTURE; FUEL ELEMENTS; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; OXIDES; OXYGEN COMPOUNDS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; TESTING; THORIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; 210300* - Power Reactors, Nonbreeding, Graphite Moderated; 360206 - Ceramics, Cermets, & Refractories- Radiation Effects

Citation Formats

Young, C. A.. Pre- and postirradiation evaluation of fuel in capsule HRB-14. [HTGR]. United States: N. p., 1980. Web. doi:10.2172/6772940.
Young, C. A.. Pre- and postirradiation evaluation of fuel in capsule HRB-14. [HTGR]. United States. https://doi.org/10.2172/6772940
Young, C. A.. 1980. "Pre- and postirradiation evaluation of fuel in capsule HRB-14. [HTGR]". United States. https://doi.org/10.2172/6772940. https://www.osti.gov/servlets/purl/6772940.
@article{osti_6772940,
title = {Pre- and postirradiation evaluation of fuel in capsule HRB-14. [HTGR]},
author = {Young, C. A.},
abstractNote = {Capsule HRB-14 was irradiated jointly by Oak Ridge National Laboratory and General Atomic Company (GA). This report covers the pre- and postirradiation characterization and evaluation of the GA fuel. The experiment was primarily to characterize the irradiation performance of TRISO-coated low-enriched (Th,U)O/sub 2/, UC/sub 0/ /sub 7/O/sub 0/ /sub 5/, and UO/sub 2/ particles and TRISO ThO/sub 2/ particles. Twenty cured-in-place fuel rods containing the fuel particles were irradiated at 960/sup 0/ to 1130/sup 0/C. The fluence was 4.5 to 8.3 x 10/sup 25/ n/m/sup 2/ (E > 29 fJ)/sub HTGR/. The fertile burnup was 4.1% to 8.5% fissions per initial metal atom (FIMA); the mixed oxide burnup was 14.5% to 19.3% FIMA; the uranium fissile burnup was 27.9% to 29.5% FIMA.},
doi = {10.2172/6772940},
url = {https://www.osti.gov/biblio/6772940}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1980},
month = {9}
}