Empirical formulas of neutron flux distributions in cylindrical ducts in water or concrete shields

Journal Article · Thu Jun 01 04:00:00 EDT 1989 · Nuclear Science and Engineering; (USA)

OSTI ID:5199534

Miura, T ^[1]

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1. Ship Research Inst., Tokai, Ibaraki (Japan). Tokai Branch

The author presents empirical formulas derived that describe neutron flux distributions in straight and bent cylindrical steel-walled ducts in symmetrical and asymmetrical geometries. Asymmetry is defined by the slant angle between the duct axis and a line passing through the center of the duct mouth and source. Streaming neutrons are divided into direct, albedo, and penetration components. The first two components are described by a function of the axial distance in units of the square root of the line-of-sight area. The last component is described by a function of the neutron flux distribution in the shield in the absence of the duct.

• OSTI ID: 5199534
• Journal Information: Nuclear Science and Engineering; (USA), Journal Name: Nuclear Science and Engineering; (USA) Vol. 102:2; ISSN 0029-5639; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
360605 -- Materials-- Radiation Effects
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALLOYS
BARYONS
BUILDING MATERIALS
CALCULATION METHODS
CONCRETES
DATA
DUCTS
ELEMENTARY PARTICLES
EPITHERMAL NEUTRONS
EXPERIMENTAL DATA
FAST NEUTRONS
FERMIONS
GEOMETRY
HADRONS
HYDROGEN COMPOUNDS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATHEMATICS
NEUTRON FLUX
NEUTRONS
NUCLEONS
NUMERICAL DATA
OXYGEN COMPOUNDS
RADIATION FLUX
REACTOR COMPONENTS
SHIELDING MATERIALS
STEELS
THEORETICAL DATA
THERMAL NEUTRONS
WATER