Monte Carlo methods, models, and applications for the Advanced Neutron Source

Conference · Fri Jun 01 00:00:00 EDT 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6023697

Redmond, II, E L; Ryskamp, J M ^[1]

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1. Idaho National Energy Lab., Idaho Falls (USA)

A three-dimensional, continuous-energy, coupled neutron-gamma Monte Carlo model of the advanced neutron source (ANS) final preconceptual reference core design has been developed using MCNP Version 3b. This model contains the reactor core with control rods, the heavy-water reflector tank with shutdown rods and representative beam tubes, and the outer light-water poor. Eighty homogenized fuel zones per fuel element are used to represent the radical and axial {sup 235}U fuel grading. This model is the most sophisticated, physically accurate reactor physics model of the ANS currently available. The purpose of this summary is to demonstrate the MCNP methods and applications for the ANS.

• OSTI ID: 6023697
• Report Number(s): CONF-900608-; CODEN: TANSA; TRN: 91-008340
• Journal Information: Transactions of the American Nuclear Society; (USA), Vol. 61; Conference: American Nuclear Society (ANS) annual meeting, Nashville, TN (USA), 10-14 Jun 1990; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
REACTOR PHYSICS
M CODES
MONTE CARLO METHOD
RESEARCH REACTORS
PLANNING
ACCURACY
COMPARATIVE EVALUATIONS
CONTROL ELEMENTS
CROSS SECTIONS
DESIGN
EFFICIENCY
ERRORS
FISSION PRODUCTS
FUEL ELEMENTS
IRRADIATION
MULTIGROUP THEORY
NEUTRON FLUX
NEUTRON REFLECTORS
NEUTRON SOURCES
NEUTRON TRANSPORT
REACTOR CORES
SCRAM RODS
THERMAL NEUTRONS
URANIUM 235
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYONS
COMPUTER CODES
ELEMENTARY PARTICLES
EVEN-ODD NUCLEI
FERMIONS
HADRONS
HEAVY NUCLEI
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MATERIALS
MINUTES LIVING RADIOISOTOPES
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEI
NUCLEONS
PARTICLE SOURCES
PHYSICS
RADIATION FLUX
RADIATION SOURCES
RADIATION TRANSPORT
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
TRANSPORT THEORY
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
220700* - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors