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Title: Irradiation performance of HTGR fuel rods in HFIR experiments HRB-7 and -8

Abstract

The HRB-7 and -8 experiments were designed as a comprehensive test of mixed thorium-uranium oxide fissile particles with Th:U ratios from 0 to 8 for HTGR recycle application. In addition, fissile particles derived from Weak-Acid Resin (WAR) were tested as a potential backup type of fissile particle for HTGR recycle. These experiments were conducted at two temperatures (1250 and 1500/sup 0/C) to determine the influence of operating temperature on the performance parameters studied. The minor objectives were comparison of advanced coating designs where ZrC replaced SiC in the Triso design, testing of fuel coated in laboratory-scale equipment with fuel coated in production-scale coaters, comparison of the performance of /sup 233/U-bearing particles with that of /sup 235/U-bearing particles, comparison of the performance of Biso coatings with Triso coatings for particles containing the same type of kernel, and testing of multijunction tungsten-rhenium thermocouples. All objectives were accomplished. As a result of these experiments the mixed thorium-uranium oxide fissile kernel was replaced by a WAR-derived particle in the reference recycle design. A tentative decision to make this change had been reached before the HRB-7 and -8 capsules were examined, and the results of the examination confirmed the accuracy of the previous decision. Evenmore » maximum dilution (Th/U approximately equal to 8) of the mixed thorium-uranium oxide kernel was insufficient to prevent amoeba of the kernels at rates that are unacceptable in a large HTGR. Other results showed the performance of /sup 233/U-bearing particles to be identical to that of /sup 235/U-bearing particles, the performance of fuel coated in production-scale equipment to be at least as good as that of fuel coated in laboratory-scale coaters, the performance of ZrC coatings to be very promising, and Biso coatings to be inferior to Triso coatings relative to fission product retention.« less

Authors:
; ; ; ; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
7290600
Report Number(s):
ORNL-5228
TRN: 77-011265
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; COATED FUEL PARTICLES; PERFORMANCE TESTING; FUEL ELEMENTS; HTGR TYPE REACTORS; AMOEBA EFFECT; IRRADIATION; THORIUM OXIDES; URANIUM DIOXIDE; ACTINIDE COMPOUNDS; CHALCOGENIDES; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTORS; TESTING; THORIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; 210300* - Power Reactors, Nonbreeding, Graphite Moderated

Citation Formats

Valentine, K H, Homan, F J, Long, Jr, E L, Tiegs, T N, Montgomery, B H, Hamner, R L, and Beatty, R L. Irradiation performance of HTGR fuel rods in HFIR experiments HRB-7 and -8. United States: N. p., 1977. Web. doi:10.2172/7290600.
Valentine, K H, Homan, F J, Long, Jr, E L, Tiegs, T N, Montgomery, B H, Hamner, R L, & Beatty, R L. Irradiation performance of HTGR fuel rods in HFIR experiments HRB-7 and -8. United States. https://doi.org/10.2172/7290600
Valentine, K H, Homan, F J, Long, Jr, E L, Tiegs, T N, Montgomery, B H, Hamner, R L, and Beatty, R L. 1977. "Irradiation performance of HTGR fuel rods in HFIR experiments HRB-7 and -8". United States. https://doi.org/10.2172/7290600. https://www.osti.gov/servlets/purl/7290600.
@article{osti_7290600,
title = {Irradiation performance of HTGR fuel rods in HFIR experiments HRB-7 and -8},
author = {Valentine, K H and Homan, F J and Long, Jr, E L and Tiegs, T N and Montgomery, B H and Hamner, R L and Beatty, R L},
abstractNote = {The HRB-7 and -8 experiments were designed as a comprehensive test of mixed thorium-uranium oxide fissile particles with Th:U ratios from 0 to 8 for HTGR recycle application. In addition, fissile particles derived from Weak-Acid Resin (WAR) were tested as a potential backup type of fissile particle for HTGR recycle. These experiments were conducted at two temperatures (1250 and 1500/sup 0/C) to determine the influence of operating temperature on the performance parameters studied. The minor objectives were comparison of advanced coating designs where ZrC replaced SiC in the Triso design, testing of fuel coated in laboratory-scale equipment with fuel coated in production-scale coaters, comparison of the performance of /sup 233/U-bearing particles with that of /sup 235/U-bearing particles, comparison of the performance of Biso coatings with Triso coatings for particles containing the same type of kernel, and testing of multijunction tungsten-rhenium thermocouples. All objectives were accomplished. As a result of these experiments the mixed thorium-uranium oxide fissile kernel was replaced by a WAR-derived particle in the reference recycle design. A tentative decision to make this change had been reached before the HRB-7 and -8 capsules were examined, and the results of the examination confirmed the accuracy of the previous decision. Even maximum dilution (Th/U approximately equal to 8) of the mixed thorium-uranium oxide kernel was insufficient to prevent amoeba of the kernels at rates that are unacceptable in a large HTGR. Other results showed the performance of /sup 233/U-bearing particles to be identical to that of /sup 235/U-bearing particles, the performance of fuel coated in production-scale equipment to be at least as good as that of fuel coated in laboratory-scale coaters, the performance of ZrC coatings to be very promising, and Biso coatings to be inferior to Triso coatings relative to fission product retention.},
doi = {10.2172/7290600},
url = {https://www.osti.gov/biblio/7290600}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1977},
month = {5}
}