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Title: Assessment of fuel concepts. [BWR; PWR]

Abstract

The relative merits of various LWR UO/sub 2/ fuel concepts with the potential for improved power-ramping capability were qualitatively assessed. In the evaluation, it was determined that of the various concepts being considered, those that presently possess an adequately developed experience base include annular pellets, cladding coated with graphite on the inner surface, and packed-particle fuel. Therefore, these were selected for initial evaluation as part of the Fuel Performance Improvement Program. For this program, graphite-coated cladding is being used in conjunction with annular pellet fuel as one of the concepts with the anticipation of gaining the advantage of the combined improvements. The report discusses the following: the criteria used to evaluate the candidate fuel concepts; a comparison of the concepts selected for irradiation with the criteria, including a general description of their experience bases; and a general discussion of other candidate concepts, including identifying those which may be considered for out-of-reactor evaluation as part of this program, those for which the results of other programs will be monitored, and those which have been deleted from further consideration at this time.

Authors:
;
Publication Date:
Research Org.:
Battelle Pacific Northwest Labs., Richland, WA (USA)
OSTI Identifier:
6876037
Alternate Identifier(s):
OSTI ID: 6876037
Report Number(s):
COO-4066-3; PNL-2490
TRN: 79-001038
DOE Contract Number:
EY-76-C-02-4066; EY-76-C-06-1830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; FUEL ELEMENTS; PERFORMANCE; PWR TYPE REACTORS; COMPARATIVE EVALUATIONS; DESIGN; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS 210100* -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Bailey, W.J., and Barner, J.O. Assessment of fuel concepts. [BWR; PWR]. United States: N. p., 1978. Web. doi:10.2172/6876037.
Bailey, W.J., & Barner, J.O. Assessment of fuel concepts. [BWR; PWR]. United States. doi:10.2172/6876037.
Bailey, W.J., and Barner, J.O. Sun . "Assessment of fuel concepts. [BWR; PWR]". United States. doi:10.2172/6876037. https://www.osti.gov/servlets/purl/6876037.
@article{osti_6876037,
title = {Assessment of fuel concepts. [BWR; PWR]},
author = {Bailey, W.J. and Barner, J.O.},
abstractNote = {The relative merits of various LWR UO/sub 2/ fuel concepts with the potential for improved power-ramping capability were qualitatively assessed. In the evaluation, it was determined that of the various concepts being considered, those that presently possess an adequately developed experience base include annular pellets, cladding coated with graphite on the inner surface, and packed-particle fuel. Therefore, these were selected for initial evaluation as part of the Fuel Performance Improvement Program. For this program, graphite-coated cladding is being used in conjunction with annular pellet fuel as one of the concepts with the anticipation of gaining the advantage of the combined improvements. The report discusses the following: the criteria used to evaluate the candidate fuel concepts; a comparison of the concepts selected for irradiation with the criteria, including a general description of their experience bases; and a general discussion of other candidate concepts, including identifying those which may be considered for out-of-reactor evaluation as part of this program, those for which the results of other programs will be monitored, and those which have been deleted from further consideration at this time.},
doi = {10.2172/6876037},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 1978},
month = {Sun Jan 01 00:00:00 EST 1978}
}

Technical Report:

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  • New control room equipment designed to improve operator performance must be evaluated before adoption and installation. Two experimental concepts for a Safety Parameters Display System (SPDS) were evaluated to assess benefits and potential problems associated with the SPDS concept and its integration into control room operations. Participants were licensed utility operators undergoing retraining on a nuclear power plant simulator. Both quantitative and qualitative data were collected and analyzed on crew response to seven simulated accident conditions.
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