Monte Carlo methods, models, and applications to the advanced neutron source

Journal Article · Sun Sep 01 04:00:00 EDT 1991 · Nuclear Technology; (United States)

OSTI ID:5780224

Redmond, E L; Redmond, I I; Ryskamp, J M ^[1]

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1. Idaho National Engineering Lab., EG and G Idaho, Inc., Idaho Falls, ID (US)

This paper reports on three-dimensional continuous-energy coupled neutron-gamma Monte Carlo models of the Advanced Neutron Source (ANS) final preconceptual and conceptual reference core designs developed using the Monte Carlo Neutron and Photon transport code (MCNP) Version 3b. These models contain the reactor core with control rods, the heavy water reflector tank with shutdown rods and some beam tubes, and the outer light water pool. Eighty homogenized fuel zones per fuel element are used to represent the radial and axial {sup 235}U fuel distribution. These models are the most sophisticated, physically accurate reactor physics models of the ANS currently available. The use of MCNP methods and applications to the ANS are demonstrated. Beam tube studies, coolant voiding studies, and many criticality studies have already been performed, as have studies with variance reduction techniques. In comparison with deterministic methods, MCNP proves superior in calculating the core multiplication factor and neutron fluxers in the reflector. The MCNP code offers the ANS project the capability of performing complicated reactor physics calculations not currently possible with most deterministic methods.

• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5780224
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 95:3; ISSN NUTYB; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE ISO
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
ANALOG SYSTEMS
CALCULATION METHODS
COMPUTER CODES
CRITICALITY
EVEN-ODD NUCLEI
EXPERIMENTAL REACTORS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUNCTIONAL MODELS
HEAVY NUCLEI
HEAVY WATER COOLED REACTORS
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
LOSS OF COOLANT
M CODES
MINUTES LIVING RADIOISOTOPES
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEI
PHOTON TRANSPORT
PHYSICS
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR PHYSICS
REACTOR SAFETY
REACTOR SIMULATORS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATORS
SPONTANEOUS FISSION RADIOISOTOPES
SUBCRITICAL ASSEMBLIES
THREE-DIMENSIONAL CALCULATIONS
URANIUM 235
URANIUM ISOTOPES