Review of fuel burnup techniques in U.S
Description
Measurement of fuel burnup and the development of methods for measurement of fuel burnup are performed at numerous industrial and government laboratories. Most of the burnup measurements are associated with fuel development and testing for fast, light water and gas cooled reactors. Development and evaluation of burnup methods are primarily centered in government laboratories. The development work is directed at fast reactor applications, but most of the methods being tested are likely to be useful for light water reactors also. Determination of fission yields from various actinide nuclides continues to be a major activity. Most burnup measurements use a combined heavy element-neodymium-148 method. High resolution gamma spectroscopy is used frequently, both for non-destructive scanning and destructive burnup analysis. Several spectrophotometric methods have been used. The most successful spectrophotometric determination is zirconium for gas cooled reactor fuel. Development work includes better separation techniques and evaluation of new monitors
Additional details
Publishing Information
- Imprint Title
- Dosimetry methods for fuels, cladding, and structural materials
- Journal Page Range
- p. 469-475.
- Report number
- NUREG/CP--0004(Vol.1)
Conference
- Title
- dosimetry methods for fuels, cladding and structural materials.
- Acronym
- 2. ASTM-EURATOM symposium on reactor dosimetry
- Dates
- 2 - 7 Oct 1977.
- Place
- Palo Alto, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10441739
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; GAMMA SPECTROSCOPY; MEASURING METHODS; NUCLEAR FUELS; REVIEWS
- Descriptors DEC
- DOCUMENT TYPES; ENERGY SOURCES; FUELS; REACTOR MATERIALS; SPECTROSCOPY