Reactivity studies on the final preconceptual reference design of the Advanced Neutron Source
An Advanced Neutron Source (ANS) with a peak thermal neutron flux of 8.0 {minus} 9.0 {times} 10{sup 19} m{sup {minus}2}s{sup {minus}1} is being designed for condensed matter physics, materials science, isotope production, and fundamental physics research. A final preconceptual reference reactor design has been selected in order to examine the safety, performance, and costs associated with this one design. This report presents reactor physics analyses of safety aspects of the reference reactor design that are related to core reactivity changes. These analyses include control rod worth, shutdown rod worth, heavy water voiding, light water ingress, single fuel element criticality, fuel element movement, and neutron beam tube flooding. The positive and negative findings are explored for each of these analyses. Based on these analyses, some design modifications that further improve the reactor safety are identified and recommended. 12 refs., 4 figs., 16 tabs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6991839
- Report Number(s):
- EGG-NE-8940; ON: DE90013098
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900 -- Nuclear Reactor Technology-- Reactor Safety
C CODES
COMPUTER CODES
CONTROL ELEMENTS
CONTROL ROD WORTHS
COOLING SYSTEMS
CRITICALITY
DESIGN
E CODES
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
M CODES
MECHANICS
NEUTRON FLUX
P CODES
PHYSICS
RADIATION FLUX
REACTIVITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
WATER INFLUX
22 GENERAL STUDIES OF NUCLEAR REACTORS
220700* -- Nuclear Reactor Technology-- Plutonium & Isotope Production Reactors
220900 -- Nuclear Reactor Technology-- Reactor Safety
C CODES
COMPUTER CODES
CONTROL ELEMENTS
CONTROL ROD WORTHS
COOLING SYSTEMS
CRITICALITY
DESIGN
E CODES
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
M CODES
MECHANICS
NEUTRON FLUX
P CODES
PHYSICS
RADIATION FLUX
REACTIVITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR PHYSICS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
WATER INFLUX