Calculational problem for deep penetration of neutrons through a one-bend sodium duct
Description
This problem features a two-dimensional geometry representing a sodium duct surrounded by concrete that can easily be modeled with both Monte Carlo and two-dimensional S/sub N/ codes. The neutron source is placed on an external duct surface, has a uniform spectrum over the energy range of 5 to 2 MeV, and is forward peaked with a cosine distribution. The average distance covered by a neutron leaving the duct surface at the exit is about 360 cm. The importance sampling method of the Monte Carlo code TRIPOLI-2 is used. Fluxes and detector responses are tabulated for several surfaces defined along the neutron path in the sodium. A population of approximately 5000 neutrons undergoes about one million collisions giving flux and current at the duct exit with a standard error of 7.5%. 3 figures, 6 tables
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12598330.pdf
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Additional details
Publishing Information
- Imprint Title
- Review of the theory and applications of Monte Carlo methods
- Journal Page Range
- p. 219-229.
- Report number
- ORNL/RSIC--44
Conference
- Title
- Seminar on theory and applications of Monte Carlo methods.
- Dates
- Apr 1980.
- Place
- Oak Ridge, TN, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12598330
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CONCRETES; DUCTS; FAST NEUTRONS; LMFBR TYPE REACTORS; MEV RANGE 01-10; MONTE CARLO METHOD; MULTIGROUP THEORY; NEUTRON FLUX; NEUTRON TRANSPORT; SODIUM; THEORETICAL DATA; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ALKALI METALS; BARYONS; BREEDER REACTORS; BUILDING MATERIALS; DATA; ELEMENTARY PARTICLES; ELEMENTS; ENERGY RANGE; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FERMIONS; HADRONS; INFORMATION; LIQUID METAL COOLED REACTORS; METALS; MEV RANGE; NEUTRAL-PARTICLE TRANSPORT; NEUTRONS; NUCLEONS; NUMERICAL DATA; RADIATION FLUX; RADIATION TRANSPORT; REACTORS; TRANSPORT THEORY