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CALCULATIONS OF CROSS SECTIONS AND BURNUP FOR THE BR3

Author
Eitz, A. W.
Published
[Place of publication not identified] : [publisher not identified], 1961.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1961.
Physical Description
microopaque : positive ; 8 x 13 cm

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Summary
Using the Ferranti-Mercury digital computer, effective therinal and epithermal absorption and fission cross sections for the core of the BR3 were calculated depending on the form of the neutron spectrum. Applying these cross sections, burnup calculations were made taking into account the spectrum variation in the course of the burnup. For all calculations constant moderator temperature and constant thermal output of the reactor were assumed. (auth)
Report Numbers
BLG-66
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
NSA number: NSA-16-008428
OSTI Identifier 4818161
Research organization: Brussels. Centre d'Etude de l'Energie Nucleaire.
View MARC record | catkey: 38673048