Advanced fuel assembly characterization capabilities based on gamma tomography at the Halden boiling water reactor

Conference · Sun Jul 01 04:00:00 EDT 2012

OSTI ID:22105826

Holcombe, S.; Eitrheim, K. ^[1]; Svaerd, S. J. ^[2]; Hallstadius, L.; Willman, C. ^[3]

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1. Inst. for Energy Technology, OECD Halden Reactor Project, P.O. BOX 173, NO-1751 Halden (Norway)
2. Div. of Applied Nuclear Physics, Uppsala Univ., Box 516, SE-751 20 Uppsala (Sweden)
3. Westinghouse Electric Sweden AB, SE-721 63 Vaesteraas (Sweden)

Characterization of individual fuel rods using gamma spectroscopy is a standard part of the Post Irradiation Examinations performed on experimental fuel at the Halden Boiling Water Reactor. However, due to handling and radiological safety concerns, these measurements are presently carried out only at the end of life of the fuel, and not earlier than several days or weeks after its removal from the reactor core. In order to enhance the fuel characterization capabilities at the Halden facilities, a gamma tomography measurement system is now being constructed, capable of characterizing fuel assemblies on a rod-by-rod basis in a more timely and efficient manner. Gamma tomography for measuring nuclear fuel is based on gamma spectroscopy measurements and tomographic reconstruction techniques. The technique, previously demonstrated on irradiated commercial fuel assemblies, is capable of determining rod-by-rod information without the need to dismantle the fuel. The new gamma tomography system will be stationed close to the Halden reactor in order to limit the need for fuel transport, and it will significantly reduce the time required to perform fuel characterization measurements. Furthermore, it will allow rod-by-rod fuel characterization to occur between irradiation cycles, thus allowing for measurement of experimental fuel repeatedly during its irradiation lifetime. The development of the gamma tomography measurement system is a joint project between the Inst. for Energy Technology - OECD Halden Reactor Project, Westinghouse (Sweden), and Uppsala Univ.. (authors)

• Research Organization: American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
• OSTI ID: 22105826
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL ASSEMBLIES
FUEL RODS
GAMMA SPECTROSCOPY
IRRADIATION
NUCLEAR FUELS
NUCLEAR INDUSTRY
POST-IRRADIATION EXAMINATION
REACTOR CORES
REACTOR SAFETY
SWEDEN
TOMOGRAPHY