Design and operation of gamma scan and fission gas sampling systems for characterization of irradiated commercial nuclear fuel [electronic resource]
One of the primary objectives of the Materials Characterization Center (MCC) is to acquire and characterize spent fuels used in waste form testing related to nuclear waste disposal. The initial steps in the characterization of a fuel rod consist of gamma scanning the rod and sampling the gas contain...
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Online Access |
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| Corporate Authors: | , |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Las Vegas, Nev. : Oak Ridge, Tenn. :
United States. Dept. of Energy. Office of Civilian Radioactive Waste Management ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1989.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Design and operation of gamma scan and fission gas sampling systems for characterization of irradiated commercial nuclear fuel |h [electronic resource] |
| 260 | |a Las Vegas, Nev. : |b United States. Dept. of Energy. Office of Civilian Radioactive Waste Management ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1989. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 09/01/1989. | ||
| 500 | |a "pnl-6732" | ||
| 500 | |a "DE90001862" | ||
| 500 | |a Mellinger, G.B.; Knox, C.A.; Thornhill, R.E. | ||
| 520 | 3 | |a One of the primary objectives of the Materials Characterization Center (MCC) is to acquire and characterize spent fuels used in waste form testing related to nuclear waste disposal. The initial steps in the characterization of a fuel rod consist of gamma scanning the rod and sampling the gas contained in the fuel rod (referred to as fission gas sampling). The gamma scan and fission gas sampling systems used by the MCC are adaptable to a wide range of fuel types and have been successfully used to characterize both boiling water reactor (BWR) and pressurized water reactor (PWR) fuel rods. This report describes the design and operation of systems used to gamma scan and fission gas sample full-length PWR and BWR fuel rods. 1 ref., 10 figs., 1 tab. | |
| 536 | |b AC06-76RL01830. | ||
| 650 | 7 | |a Beta Decay Radioisotopes. |2 local. | |
| 650 | 7 | |a Laser Drilling. |2 local. | |
| 650 | 7 | |a Radioactive Waste Management. |2 local. | |
| 650 | 7 | |a Fuel Scanning. |2 local. | |
| 650 | 7 | |a Cesium 134. |2 local. | |
| 650 | 7 | |a Cesium 137. |2 local. | |
| 650 | 7 | |a Electromagnetic Radiation. |2 local. | |
| 650 | 7 | |a Measuring Instruments. |2 local. | |
| 650 | 7 | |a Radioactive Waste Processing. |2 local. | |
| 650 | 7 | |a Sampling. |2 local. | |
| 650 | 7 | |a Isotopes. |2 local. | |
| 650 | 7 | |a Materials Drilling. |2 local. | |
| 650 | 7 | |a Gamma Radiography. |2 local. | |
| 650 | 7 | |a Fuel Elements. |2 local. | |
| 650 | 7 | |a Fission Spectra. |2 local. | |
| 650 | 7 | |a Ionizing Radiations. |2 local. | |
| 650 | 7 | |a Isomeric Transition Isotopes. |2 local. | |
| 650 | 7 | |a Machining. |2 local. | |
| 650 | 7 | |a Reactor Materials. |2 local. | |
| 650 | 7 | |a Gamma Fuel Scanning. |2 local. | |
| 650 | 7 | |a Maintenance. |2 local. | |
| 650 | 7 | |a Bwr Type Reactors. |2 local. | |
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Waste Management. |2 local. | |
| 650 | 7 | |a Internal Conversion Radioisotopes. |2 local. | |
| 650 | 7 | |a Reactor Components. |2 local. | |
| 650 | 7 | |a Radioisotopes. |2 local. | |
| 650 | 7 | |a Design. |2 local. | |
| 650 | 7 | |a Water Moderated Reactors. |2 local. | |
| 650 | 7 | |a Nuclear Fuels. |2 local. | |
| 650 | 7 | |a Waste Processing. |2 local. | |
| 650 | 7 | |a Beta-minus Decay Radioisotopes. |2 local. | |
| 650 | 7 | |a Radioactive Waste Disposal. |2 local. | |
| 650 | 7 | |a Processing. |2 local. | |
| 650 | 7 | |a Waste Disposal. |2 local. | |
| 650 | 7 | |a Spectra. |2 local. | |
| 650 | 7 | |a Fuels. |2 local. | |
| 650 | 7 | |a Gamma Radiation. |2 local. | |
| 650 | 7 | |a Fuel Rods. |2 local. | |
| 650 | 7 | |a Energy Sources. |2 local. | |
| 650 | 7 | |a Management. |2 local. | |
| 650 | 7 | |a Materials. |2 local. | |
| 650 | 7 | |a Odd-even Nuclei. |2 local. | |
| 650 | 7 | |a Water Cooled Reactors. |2 local. | |
| 650 | 7 | |a Alkali Metal Isotopes. |2 local. | |
| 650 | 7 | |a Odd-odd Nuclei. |2 local. | |
| 650 | 7 | |a Cesium Isotopes. |2 local. | |
| 650 | 7 | |a Spent Fuels. |2 local. | |
| 650 | 7 | |a Industrial Radiography. |2 local. | |
| 650 | 7 | |a Radiations. |2 local. | |
| 650 | 7 | |a Pwr Type Reactors. |2 local. | |
| 650 | 7 | |a Nuclei. |2 local. | |
| 650 | 7 | |a Years Living Radioisotopes. |2 local. | |
| 650 | 7 | |a Hours Living Radioisotopes. |2 local. | |
| 650 | 7 | |a Management Of Radioactive And Non-radioactive Wastes From Nuclear Facilities. |2 edbsc. | |
| 650 | 7 | |a Instrumentation Related To Nuclear Science And Technology. |2 edbsc. | |
| 650 | 7 | |a Specific Nuclear Reactors And Associated Plants. |2 edbsc. | |
| 710 | 2 | |a Pacific Northwest Laboratory. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Civilian Radioactive Waste Management. |4 spn. | |
| 710 | 2 | |a Pacific Northwest National Laboratory (U.S.). |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
| 856 | 4 | 0 | |u http://www.osti.gov/servlets/purl/5530813/ |z Online Access |
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