Neutron streaming through a slit and duct in concrete shields and comparison with a Monte Carlo analysis

Journal Article · Mon Aug 01 04:00:00 EDT 1983 · Nucl. Sci. Eng.; (United States)

OSTI ID:5300590

Hiroyuki, H; Hideshi, F; Masatsugu, A; Shigehiro, A; Yoshiaki, O

A series of measurements of about14-MeV deuterium-tritium neutrons streaming through a slit and a duct in concrete shields has been carried out using a Cockcroft-Walton-type neutron generator. Measured neutron energy spectra are compared with calculations in six configurations of the shields. The configurations are the simplified geometries of streaming paths of tokamak reactors, such as a divertor throat and a neutral beam injection port. The measured data were obtained with an NE-213 liquid scintillator using pulse shape discrimination methods to resolve neutron and gamma-ray pulse height data and using a spectral unfolding code to convert these data to energy spectra. The experiments were analyzed by a Monte Carlo code. The calculated neutron energy spectra slightly underestimate the measured data, especially in the range of 6 to 8 MeV. The agreement between the calculated and measured integral flux above 2.2 MeV ranges from 87.5 to 72.% depending on the configurations.

• Research Organization: Hitachi Ltd., Energy Research Laboratory, 1168 Moriyama-cho, Hitachi, Ibaraki 316
• OSTI ID: 5300590
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 84:4; ISSN NSENA
• Country of Publication: United States
• Language: English

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BUILDING MATERIALS
CALCULATION METHODS
COMPUTER CODES
CONCRETES
CONFIGURATION
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LIQUID SCINTILLATION DETECTORS
MATERIALS
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NEUTRON SOURCES
NEUTRON SPECTRA
NEUTRON TRANSPORT THEORY
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NUCLEI
NUCLEONS
NUMERICAL DATA
ODD-EVEN NUCLEI
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STABLE ISOTOPES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRANSPORT THEORY
TRITIUM
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