Measurement and calculations of angular neutron flux spectra from iron slabs bombarded with 14. 8 MeV neutrons
Journal Article
·
· Nuclear Science and Engineering; (United States)
OSTI ID:6109273
- Japan Atomic Energy Research Inst., Ibaraki (Japan). Dept. of Reactor Engineering
In a next step experimental deuterium-tritium (D-T) burning fusion reactor such as the International Thermonuclear Experimental Reactor (ITER), iron is a key material in the shielding component for protecting the superconducting magnet from radiation heating. In this paper, angular neutron flux spectra leaking from iron slabs with various thicknesses up to 600 mm have been measured by the time-of-flight technique. The results are compared with calculations by the MCNP Monte Carlo code and the DOT3.5 two-dimensional discrete ordinates code with the JENDL-3 nuclear data file and wit ENDF/B-IV. In the DOT3.5 calculations, a cross-section set with a self-shielding correction factor is also applied to examine its effect. The results show that the MCNP calculations based on both files agree very well for the main part of the deeply penetrating neutron spectrum, but the DOT3.5 code without a self-shielding correction underestimates the high-energy flux and the flux in the resonance energy range with increasing slab thickness. The self-shielding correction factor improves the underestimation, but the calculated flux is still smaller than the MCNP calculation.
- OSTI ID:
- 6109273
- Journal Information:
- Nuclear Science and Engineering; (United States), Journal Name: Nuclear Science and Engineering; (United States) Vol. 115:1; ISSN NSENAO; ISSN 0029-5639
- Country of Publication:
- United States
- Language:
- English
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Journal Article
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·
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Journal Article
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Sat Oct 31 23:00:00 EST 1987
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·
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Measurement of neutron energy spectrum below 10 keV in an iron shield bombarded by deuterium-tritium neutrons and benchmark test of evaluated nuclear data from 14 MeV to 1 eV
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Fri Jan 31 23:00:00 EST 1997
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OSTI ID:449588
Related Subjects
663610* -- Neutron Physics-- (1992-)
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700480 -- Fusion Technology-- Component Development
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CLOSED PLASMA DEVICES
DATA
DIMENSIONS
ELEMENTS
EXPERIMENTAL DATA
INFORMATION
IRON
ITER TOKAMAK
MATERIALS
METALS
Ma
Materials Studies-- (1992-)
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON LEAKAGE
NEUTRON SPECTRA
NEUTRON TRANSPORT
NUMERICAL DATA
RADIATION FLUX
RADIATION TRANSPORT
SELF-SHIELDING
SHIELDING
SHIELDING MATERIALS
SPECTRA
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR MATERIALS
THICKNESS
TOKAMAK DEVICES
TRANSITION ELEMENTS
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700480 -- Fusion Technology-- Component Development
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CLOSED PLASMA DEVICES
DATA
DIMENSIONS
ELEMENTS
EXPERIMENTAL DATA
INFORMATION
IRON
ITER TOKAMAK
MATERIALS
METALS
Ma
Materials Studies-- (1992-)
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON LEAKAGE
NEUTRON SPECTRA
NEUTRON TRANSPORT
NUMERICAL DATA
RADIATION FLUX
RADIATION TRANSPORT
SELF-SHIELDING
SHIELDING
SHIELDING MATERIALS
SPECTRA
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR MATERIALS
THICKNESS
TOKAMAK DEVICES
TRANSITION ELEMENTS