URANIUM AND PLUTONIUM FUELLED LATTICES WITH GRAPHITE AND WATER MODERATION: A COMPARISON OF EXPERIMENT AND THEORY.
Journal Article
·
· pp 15-26 of The Physics Problems in Thermal Reactor Design. London, British Nuclear Energy Society, 1967.
OSTI ID:4546150
- Research Organization:
- Atomic Energy Establishment, Winfrith, Eng.
- NSA Number:
- NSA-22-022868
- OSTI ID:
- 4546150
- Journal Information:
- pp 15-26 of The Physics Problems in Thermal Reactor Design. London, British Nuclear Energy Society, 1967., Journal Name: pp 15-26 of The Physics Problems in Thermal Reactor Design. London, British Nuclear Energy Society, 1967.
- Country of Publication:
- United Kingdom
- Language:
- English
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Related Subjects
ANALYSIS
BURNUP
COMPUTERS
CONFIGURATION
EFFICIENCY
FUELS
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GRAPHITE/effects of moderating properties on optimum fuel burnup in plutonium and uranium lattices
(E/T)
N38700* --Reactor Components
Fuels & Accessories
PLUTONIUM
PLUTONIUM/burnup in graphite and water moderated lattices of
computer analysis for optimum
(E/T)
PROGRAMMING
REACTOR CORE
REACTORS
REACTORS
THERMAL/core structure for
computer analysis of fuel burnup in optimum
(E/T)
URANIUM
URANIUM/burnup in graphite and water moderated lattices of
computer analysis for optimum
(E/T)
WATER MODERATOR
WATER/effects of moderating properties on optimum fuel burnup in plutonium and uranium lattices
(E/T)
BURNUP
COMPUTERS
CONFIGURATION
EFFICIENCY
FUELS
GRAPHITE MODERATOR
GRAPHITE/effects of moderating properties on optimum fuel burnup in plutonium and uranium lattices
(E/T)
N38700* --Reactor Components
Fuels & Accessories
PLUTONIUM
PLUTONIUM/burnup in graphite and water moderated lattices of
computer analysis for optimum
(E/T)
PROGRAMMING
REACTOR CORE
REACTORS
REACTORS
THERMAL/core structure for
computer analysis of fuel burnup in optimum
(E/T)
URANIUM
URANIUM/burnup in graphite and water moderated lattices of
computer analysis for optimum
(E/T)
WATER MODERATOR
WATER/effects of moderating properties on optimum fuel burnup in plutonium and uranium lattices
(E/T)