Non-destructive measurements of burnup by gamma ray spectroscopy
Description
Differential burn up distribution along several ET-RR-1 reactor fuel baskets of different irradiation history and cooling times were evaluated. A linear relationship between burn up and activity of Cs-137, Cs-134 and Ce-144 were used. A Ge (Li) detector was used to scan the gamma spectra of the spent fuel baskets under study. The average burn up values obtained from reactor operator files together with the measured activity ratio corrected for irradiation history and cooling time, of several fuel baskets, were used to calculate the constants of the linear equation. The values of these constants were used to evaluate the differential burn up values along other fuel baskets. The results were compared favorably with the declared operator values. (author). 9 refs, 6 figs, 1 tab
Additional details
Publishing Information
- Imprint Title
- In-core fuel management practices. Proceedings of two technical committee meetings and workshops held in Madrid, 12-15 July 1988, and Vienna, 4-7 December 1989
- Imprint Pagination
- 438 p.
- Journal Page Range
- p. 419-425.
- Report number
- IAEA-TECDOC--567
Conference
- Title
- Technical committee meeting and workshop on in-core fuel management.
- Dates
- 4-7 Dec 1989.
- Place
- Vienna (Austria).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 22023591
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FUEL ELEMENTS; FUEL SCANNING; GAMMA SPECTROSCOPY; NONDESTRUCTIVE TESTING; WWR-S-CAIRO REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; MATERIALS TESTING; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SPECTROSCOPY; TANK TYPE REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWR TYPE REACTORS