METHODS OF CALCULATION FOR USE IN THE DESIGN OF SHIELDS FOR POWER REACTORS
Technical Report
·
OSTI ID:4157561
Recommendations are given on methods of calculation for use in the design of shields for the gas cooled, graphite moderated, natural uranium reactors of the U.K. Civil Power Program. Topics dealt with include: primary shielding of neutron and gamma radiation, nuclear heating, coolant activation, fission product energy decay rates, and radiation streaming in ducts. A new method of calculating neutron penetration is introduced and compared with experimental measurements in a Calder Hall Reactor shield. (auth)
- Research Organization:
- United Kingdom Atomic Energy Authority. Research Group. Atomic Energy Research Establishment, Harwell, Berks, England
- NSA Number:
- NSA-14-022588
- OSTI ID:
- 4157561
- Report Number(s):
- AERE-R-3216
- Country of Publication:
- United Kingdom
- Language:
- English
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