Published February 1983
| Version v1
Report
Feasibility of on-line fuel condition monitoring
Description
The relationship between fuel rod damage and fission product release is investigated to assess the feasibility of using on-line gamma spectroscopy of reactor coolant to estimate not only numbers of detected fuel rods, but also the type of core damage which may occur during an accident or off-normal transient. Fission product release signatures for various fuel conditions and accident scenarios are compared, and unique indicators of fuel damage, ranging from cladding pinholes to severely damaged fuel rods, are suggested. The configuration of monitoring hardware and data analysis soft ware are described, and the benefits, development needs, and usefulness of the envisaged power plant system are discussed
Additional details
Publishing Information
- Imprint Title
- Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 3
- Journal Page Range
- p. 1608-1616.
- Report number
- NUREG/CP--0027-Vol.3
Conference
- Title
- International meeting on thermal nuclear reactor safety (ANS topical meeting).
- Dates
- 29 Aug - 2 Sep 1982.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14792468
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAILED ELEMENT DETECTION; FAILED ELEMENT MONITORS; FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; GAMMA SPECTROSCOPY; POWER REACTORS; RADIATION MONITORING; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; DETECTION; MONITORING; REACTOR ACCIDENTS; REACTORS; SAFETY; SPECTROSCOPY