Published August 22, 1977
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Determination of fuel irradiation parameters. Required accuracies and available methods
Description
This paper reports on the present point of some main methods to determine the nuclear parameters of fuel irradiation in testing reactors (nuclear power, burn up, ...) The different methods (theoretical or experimental) are reviewed: neutron measurements and calculations, gamma scanning, heat balance, ... . The required accuracies are reviewed: they are of 3-5 % on flux, fluences, nuclear power, burn-up, conversion factor. These required accuracies are compared with the real accuracies available which are the present time of order of 5-20 % on these parameters
Availability note (English)
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10433482.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- CEA-CONF--4163
Conference
- Title
- dosimetry methods for fuels, cladding and structural materials.
- Acronym
- 2. Symposium on reactor dosimetry
- Dates
- 3 - 7 Oct 1977.
- Place
- Palo Alto, Calif., USA.
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 10433482
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; BURNUP; FUEL PINS; MEASURING METHODS; NEUTRON DOSIMETRY; NEUTRON FLUENCE; NEUTRON FLUX; PHYSICAL RADIATION EFFECTS; POWER DENSITY
- Descriptors DEC
- DOSIMETRY; FUEL ELEMENTS; RADIATION EFFECTS; RADIATION FLUX; REACTOR COMPONENTS