Fuel Performance Improvement Program. Semiannual Progress Report, October 1979-March 1980. [PWR; BWR]. PDF Download
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![Fuel Performance Improvement Program. Semiannual Progress Report, October 1979-March 1980. [PWR; BWR]. PDF](https://books.google.com/books/content/images/frontcover/Tt3zzAEACAAJ?fife=w150-h200)
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Languages : en
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Progress on the Fuel Performance Improvement Program's fuel design tests and demonstration irradiations for October 1979 through March 1980 is reported. Included are the results of out-of-reactor experiments with Zircaloy cladding using a device that simulates the interaction between fuel and cladding. Also included are reports on the irradiation of the advanced LWR fuel designs in the Halden Boiling Water Reactor and in Consumers Power Company's Big Rock Point Reactor. The establishment of the technical bases and licensing requirements for the advanced fuel concepts are also described.
![Fuel Performance Improvement Program. Semiannual Progress Report, October 1979-March 1980. [PWR; BWR]. PDF](https://books.google.com/books/content/images/frontcover/Tt3zzAEACAAJ?fife=w80-h100)
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Languages : en
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Progress on the Fuel Performance Improvement Program's fuel design tests and demonstration irradiations for October 1979 through March 1980 is reported. Included are the results of out-of-reactor experiments with Zircaloy cladding using a device that simulates the interaction between fuel and cladding. Also included are reports on the irradiation of the advanced LWR fuel designs in the Halden Boiling Water Reactor and in Consumers Power Company's Big Rock Point Reactor. The establishment of the technical bases and licensing requirements for the advanced fuel concepts are also described.
Author: C. E. Crouthamel
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Languages : en
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Category : Power resources
Languages : en
Pages : 1364
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![Fuel-performance-improvement Program. Semiannual Progress Report, October 1980-March 1981. [Sphere-pac and Annular-coated-pressurized]. PDF](https://books.google.com/books/content/images/frontcover/5ULSwQEACAAJ?fife=w80-h100)
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Progress on the Fuel Performance Improvement Program's fuel test and demonstration irradiations is reported for the period of October 1980-March 1981. The purpose of the program is to test and demonstrate improved light water reactor fuel concepts that are more resistant to failure from pellet-cladding interaction during power increases than standard pellet fuel. This would also offer extended burnup potential and, hence, improved uranium utilization.
![Fuel Performance Improvement Program. Quarterly Progress Report October--December 1978. [BWR; PWR]. PDF](https://books.google.com/books/content/images/frontcover/Nq7RwQEACAAJ?fife=w80-h100)
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Languages : en
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The Fuel Performance Improvement Program has as its objective the identification and demonstration of fuel concepts with improved power ramp performance. Improved fuels are being sought to allow reduction or elimination of fuel related operating guidelines on nuclear power plants such that the fuel may be power manuvered within the rates allowed by the system technical specifications. The program contains a combination of out-of-reactor studies, in-reactor experiments and in-reactor demonstrations. Fuel concepts initially being considered include annular pellets, cladding internally coated with graphite and packed-particle fuls. The performance capability of each concept will be compared to a reference fuel of contemporary pellet design by irradiations in the Halden Boiling Water Reactor. Fuel design and process development is being completed and fuel rod fabrication will begin for the Halden test rods and for the first series of in-reactor experiments. The in-reactor demonstrations are being performed in the Big Rock Point reactor to show that the concepts pose no undue risk to commercial operation. Additional concepts may be considered as the result of a state-of-the-technology review of fuel-cladding interaction and assessment of fuel concepts and the out-of-reactor studies. The results of the program will be used to establish the technical bases for design of fuels with improved power ramp performance.
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Languages : en
Pages : 71
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Book Description
The Fuel Performance Improvement Program has as its objective the identification and demonstration of fuel concepts with improved power ramp performance. Improved fuels are being sought to allow reduction or elimination of fuel related operating guidelines on nuclear power plants such that the fuel may be power maneuvered within the rates allowed by the system technical specifications. The program contains a combination of out-of-reactor studies, in-reactor experiments and in-reactor demonstrations. Fuel concepts initially being considered include annular pellets, cladding internally coated with graphite and packed-particle fuels. The performance capability of each concept will be compared to a reference fuel of contemporary pellet design by irradiations in the Halden Boiling Water Reactor. Fuel design and process development is being completed and fuel rod fabrication will begin for the Halden test rods and for the first series of in-reactor experiments. The in-reactor demonstrations are being performed in the Big Rock Point reactor to show that the concepts pose no undue risk to commercial operation. Additional concepts may be considered as the result of a state-of-the-technology review of fuel-cladding interaction and assessment of fuel concepts and the out-of-reactor studies. The results of the program will be used to establish the technical bases for design of fuels with improved power ramp performance.
![Fuel Performance Improvement Program. Quarterly/annual Progress Report, October 1977--September 1978. [BWR; PWR]. PDF](https://books.google.com/books/content/images/frontcover/LdrbwQEACAAJ?fife=w80-h100)
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Languages : en
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This quarterly/annual report reviews and summarizes the activities performed in support of the Fuel Performance Improvement Program (FPIP) during Fiscal Year 1978 with emphasis on those activities that transpired during the quarter ending September 30, 1978. Significant progress has been made in achieving the primary objectives of the program, i.e., to demonstrate commercially viable fuel concepts with improved fuel - cladding interaction (FCI) behavior. This includes out-of-reactor experiments to support the fuel concepts being evaluated, initiation of instrumented test rod experiments in the Halden Boiling Water Reactor (HBWR), and fabrication of the first series of demonstration rods for irradiation in the Big Rock Point Reactor (BRPR).
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Languages : en
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The objective of the Fuel Performance Improvement Program is to develop, test, and demonstrate basically two advanced fuel designs with the capability for improved power ramping performance and thus increase the capability of achieving extended burnup levels to better utilize uranium resources. The irradiations are being supported by out-of-reactor experiments to evaluate the effect of graphite coatings to inhibit stress-corrosion-cracking type cladding failures that are related to pellet-cladding interaction. Instrumented test irradiations in the Halden Boiling Water Reactor (HBWR) have achieved peak burnups of 697 GJ/kgM (8.1 MWd/kgM) with reference, annular-coated-pressurized, and sphere-pac rods.
![Fuel Performance Improvement Program. Quarterly Progress Report, January--March 1979. [LWR]. PDF](https://books.google.com/books/content/images/frontcover/ou3QwQEACAAJ?fife=w80-h100)
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Languages : en
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Book Description
Progress in various tasks of the LWR Fuel Performance Improvement Program is summarized. These tasks include the testing and demonstration program, out-of-reactor experiments, in-reactor experiments, in-reactor demonstrations, and fuel performance evaluations.
![Fuel Performance Improvement Program. Quarterly Progress Report, October--December 1977. [LWR]. PDF](https://books.google.com/books/content/images/frontcover/LqvWwQEACAAJ?fife=w80-h100)
Author:
Publisher:
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Category :
Languages : en
Pages :
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Book Description
The Fuel Performance Improvement Program has as its objective the identification and demonstration of fuel concepts with improved power ramp performance. Improved fuels are being sought to allow reduction or elimination of fuel related operating guidelines on nuclear power plants such that the fuel may be power maneuvered within the rates allowed by the system technical specifications. The program contains a combination of out-of-reactor studies, in-reactor experiments and in-reactor demonstrations. Fuel concepts initially being considered include annular pellets, cladding internally coated with graphite and packed-particle fuels. The performance capability of each concept will be compared to a reference fuel of contemporary pellet design by irradiations in the Halden Boiling Water Reactor. Fuel design and process development is being completed and fuel rod fabrication will begin for the Halden test rods and for the first series of in-reactor experiments. The in-reactor demonstrations are being performed in the Big Rock Point reactor to show that the concepts pose no undue risk to commercial operation. Additional concepts may be considered as the result of a state-of-the-technology review of fuel-cladding interaction and assessment of fuel concepts and the out-of-reactor studies. The results of the program will be used to establish the technical bases for design of fuels with improved power ramp performance.
