Hot fuel examination facility-north fuel element puncturing and gas sampling system
Description
A remotely operated laser fuel element gas-sampling system has been put into service at the Hot Fuel Examination Facility (HFEF) North. This system provides the ability to puncture the cladding of a capsule or fuel element in its plenum region to measure its free volume and pressure and to gather gas samples for composition and isotopic analyses. The element is punctured and pressure data are taken with which to calculate the element's prepuncture internal pressure. After a gas sample is taken, the plenum is evacuated and then back-filled from known calibrated volumes to determine its free volume. The element or capsule may then be repressurized with any specified gas and the cladding puncture rewelded. Although these welds are primarily for radioactive contamination control of the element and the hot cell and are not qualified for fuel element in-reactor service, the welds that have been made are well characterized and have been tested to 6.89 x 105 Pa (100 psia)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 57
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 336-337
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Joint meeting of the European Nuclear Society and the American Nuclear Society.
- Dates
- 30 Oct - 4 Nov 1988.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21002604
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANL; EBR-2 REACTOR; FFTF REACTOR; FISSION PRODUCTS; FUEL ASSEMBLY DISMANTLING; FUEL CANS; GAS ANALYSIS; HOT CELLS; MASS SPECTROSCOPY; NEODYMIUM LASERS; NUCLEAR POWER PLANTS; OPTICAL SYSTEMS; PERFORMANCE; PRESSURE MEASUREMENT; RELIABILITY; REPAIR; SAMPLING; SHIPPINGPORT REACTOR; SPENT FUEL ELEMENTS; TEST FACILITIES; TREAT REACTOR; VOLUME
- Descriptors DEC
- AIR COOLED REACTORS; AMPLIFIERS; BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EQUIPMENT; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; ISOTOPES; LABORATORY EQUIPMENT; LASERS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; SOLID HOMOGENEOUS REACTORS; SOLID STATE LASERS; SPECTROSCOPY; TEST REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-881011--.