Published August 22, 1977 | Version v1
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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)

MF available from INIS under the Report Number.

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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