Partially Flat Radial Flux and Power with Minimum Leakage
Journal Article
·
· Nuclear Science and Engineering
OSTI ID:4224872
- North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.
Non-uniform core loadings may be expected to yield a given degree of flux or power density flattening with a minimum amount of core fuel investment. For a specified degree of thermal neutron flux or power density flattening in a large cores the problem is to obtain the non-uniform core loading which achieves criticality with a minimum of neutron leakage from the core. Typical results of preliminary calculations are given for a 14ft. diam. right cylindrical active core of a sodium graphite-type reactor with an infinite radial reflector.
- Research Organization:
- North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- NSA Number:
- NSA-13-017429
- OSTI ID:
- 4224872
- Journal Information:
- Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 1 Vol. 2; ISSN 0029-5639
- Publisher:
- Taylor & Francis
- Country of Publication:
- United States
- Language:
- English
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