Calculations of k for Some Small U233-, U235-, and Pu239-Fueled Fast Reactors
- Argonne National Lab., Idaho Falls, ID (United States)
Values of the multiplication constant, k, have been calculated for a number of small U233-, U235-, and Pu239-fueled fast reactors through use of a cross-section set previously used by the author for investigation of a number of U235-fueled ZPR-III assemblies. The reactors considered in the present report are (a)GODIVA, TOPSY, JEMIMA, JEZEBEL, POPSY, and U233 assemblies constructed at Los Alamos; (b) three plutonium-graphite critical assemblies constructed with the reactor VERA at AWRE, Aldermaston, England; (c) the plutonium-fueled Mark-IV loading of the EBR-I reactor at Idaho Division of ANL; and (d) a plutonium and U235-fueled mockup in ZPR-III of a proposed French reactor, RAPSODIE.
- Research Organization:
- Argonne National Laboratory (ANL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- DOE Contract Number:
- W-31109-ENG-38
- NSA Number:
- NSA-18-023010
- OSTI ID:
- 4093938
- Report Number(s):
- ANL-6850
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CRITICAL ASSEMBLIES
CROSS SECTIONS
Critical Assemblies
Cross-Section
EMR-I Reactor
FAST NEUTRONS
GRAPHITE
JEZEBEL
MOCKUP
MULTIPLICATION FACTORS
Nuclear Criticality Safety Program (NCSP)
PLUTONIUM 239
POPSY
RAPSODIE
REACTORS
RESEARCH REACTORS
TOPSY
URANIUM 233
URANIUM 235
VERA
ZPR-III
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CRITICAL ASSEMBLIES
CROSS SECTIONS
Critical Assemblies
Cross-Section
EMR-I Reactor
FAST NEUTRONS
GRAPHITE
JEZEBEL
MOCKUP
MULTIPLICATION FACTORS
Nuclear Criticality Safety Program (NCSP)
PLUTONIUM 239
POPSY
RAPSODIE
REACTORS
RESEARCH REACTORS
TOPSY
URANIUM 233
URANIUM 235
VERA
ZPR-III