Reactor physics methods for the preconceptual core design of the advanced neutron source
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5619656
Idaho National Engineering Laboratory (INEL) and Oak Ridge National Laboratory (ORNL) have been jointly working to develop and evaluate preconceptual reactor core configurations for the advanced neutron source. This paper reviews the reactor physics methods used to compute reactor parameters and demonstrates that the laboratories achieve good agreement on these parameters.
- OSTI ID:
- 5619656
- Report Number(s):
- CONF-871101-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 55; Conference: Joint meeting of the American Nuclear Society and the Atomic Industrial Forum, Los Angeles, CA, USA, 15-19 Nov 1987
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
NEUTRON SOURCE FACILITIES
DESIGN
REACTOR CORES
REACTOR KINETICS
RESEARCH REACTORS
PLANNING
ACCURACY
CROSS SECTIONS
GROUP THEORY
HFIR REACTOR
IDAHO NATIONAL ENGINEERING LABORATORY
NEUTRON FLUX
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
ONE-DIMENSIONAL CALCULATIONS
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S CODES
THERMAL NEUTRONS
TWO-DIMENSIONAL CALCULATIONS
X CODES
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COMPUTER CODES
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
FERMIONS
HADRONS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
KINETICS
MATHEMATICS
NATIONAL ORGANIZATIONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRONS
NUCLEONS
RADIATION FLUX
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
NEUTRON SOURCE FACILITIES
DESIGN
REACTOR CORES
REACTOR KINETICS
RESEARCH REACTORS
PLANNING
ACCURACY
CROSS SECTIONS
GROUP THEORY
HFIR REACTOR
IDAHO NATIONAL ENGINEERING LABORATORY
NEUTRON FLUX
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
ONE-DIMENSIONAL CALCULATIONS
ORNL
S CODES
THERMAL NEUTRONS
TWO-DIMENSIONAL CALCULATIONS
X CODES
BARYONS
COMPUTER CODES
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
FERMIONS
HADRONS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
KINETICS
MATHEMATICS
NATIONAL ORGANIZATIONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRONS
NUCLEONS
RADIATION FLUX
RADIATION TRANSPORT
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors