Planning support document for the EPRI Light Water Reactor Fuel Performance program

Roberts, John; Gelhaus, F.E.; Ocken, H.; Oldberg, S.; Thomas, G.R.

doi:10.2172/7327156

Cited by 10 publications

(7 citation statements)

References 0 publications

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“…The objective of this research program is to provide well-characterized Hg and He data to test existing theories for predicting gap and contact heat transfer. The determination of the sensitivity of the interface conductance to changes in the variables listed in Table 1 would allow a further refinement of computer programs such as COMETHE, ( 16 ) GAPCON-THERMAL, ( 17 • 18 ) FRAP-s, ( 1 g) and IAMBUS( 2 0) which predict the effects of gap and contact conductance in oxide fuel elements. The goal of this research is to extend measurements of H 9…”

Section: Llmentioning

confidence: 99%

Ex-reactor determination of thermal gap and contact conductance between uranium dioxide: zircaloy-4 interfaces. Stage I: low gas pressure. [PWR; BWR]

Garnier¹,

Begej²

1979

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This report was prepared u an account of work sponsored by the United States Government. Neither the United States nor the United States Nuclear Regulatory Commission, nor any of their employees, nor any of their contractors, subcontracton, or their employees, makes any warrant)', express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefuln~s of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights.

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Section: Llmentioning

confidence: 99%

Ex-reactor determination of thermal gap and contact conductance between uranium dioxide: zircaloy-4 interfaces. Stage I: low gas pressure. [PWR; BWR]

Garnier¹,

Begej²

1979

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“…hydriding occurring prior to a breach of cladding integrity). Since then, as reported by Roberts et al, primary hydriding has been (84) essentially eliminated by changes in fuel manufacture and design.…”

Section: Pickmanmentioning

confidence: 92%

“…Data are being obtained on the chemical elements present on the inner surfaces of irradiated fuel-rod cladding. (74) It is difficult to separate an SCC failure from a purely mechanical failure because the regions of highest strain and the most aggressive corrosion coincide in location, as concluded that the relative contributions (84) of stress and chemistry to SCC need better definition.…”

Section: Aasmentioning

confidence: 99%

State-of-the-technology review of fuel-cladding interaction. Fuel Performance Improvement Program

Bailey¹,

Wilson²,

MacGowan³

et al. 1977

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The Fuel Performance Improvement Program recently initiated by the Energy Research and Development Administration (now the Department of Energy) has as its objective the identification and demonstration of fuel concepts with improved power-Famp performance. The results of the overall program will be used to establish the technical bases for the design of such fuels. Consumers Power Company, Exxon Nuclear Company, and Battelle, Pacific Northwest Laboratories are the three participants in the program. The objective of Task 1 under the program is to assess the state of the technology of fuel-cladding interaction and to identify fuel concepts with potential for improved power-ramping capabilities in order to provide direction and technical support for the program scope. Task 1 consists of two activities. The first activity involved a literature survey and a summarization of postulated fuel-cladding-interaction < mechanisms and associated supportive data. The results of that activity are described in this report and include comments on experience with powerramped fuel, fuel-cladding mechanical interaction, stress-corrosion cracking and fission-product embrittlement, potential remedial actions, fuelcladding-interaction mechanistic considerations, other ongoing programs, and related patents of interest. The second activity provides an assessment of the candidate fuel concepts to be evaluated as part of this program. The results of the assessment are presented in a separate report, which contains the supportive information and rationale for the selection of the primary fuel concepts to be evaluated in this program.

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“…However, Exxon does not merelv copy the previous design but instead, provides their own design and performs the analysis to meet ENC criteria. The reference planning support document fully describes the details of these (32) projects.^ ' -14-…”

Section: Exxonmentioning

confidence: 99%

Fuel performance annual report, period through December 1978. [PWR; BWR]

Houston¹

1979

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Planning support document for the EPRI Light Water Reactor Fuel Performance program

Cited by 10 publications

References 0 publications

Ex-reactor determination of thermal gap and contact conductance between uranium dioxide: zircaloy-4 interfaces. Stage I: low gas pressure. [PWR; BWR]

Ex-reactor determination of thermal gap and contact conductance between uranium dioxide: zircaloy-4 interfaces. Stage I: low gas pressure. [PWR; BWR]

State-of-the-technology review of fuel-cladding interaction. Fuel Performance Improvement Program

Fuel performance annual report, period through December 1978. [PWR; BWR]

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