Neutron-Gamma-ray-coupled albedo Monte Carlo method streaming analysis
Journal Article
·
· Fusion Technol.; (United States)
OSTI ID:6986248
The neutron-gamma-ray-coupled albedo Monte Carlo (AMC) method has been developed and implemented in MORSE-I. The energy- and angle-dependent differential albedo data, which include secondary gamma rays, are calculated for a slab layer with one dimensional transport theory. Fundamental formulas for this method are described. The applicability to shielding design of fusion reactors is confirmed by analyzing the radiation streaming experiment conducted at the Fusion Neutronics Source facility, Japan Atomic Energy Research Institute. The AMC method has reproduced well the experimental data of radiation dose rates and spectra with an accuracy of approximately 10%. It is shown that the AMC method is several times more efficient than the ordinary Monte Carlo calculation in obtaining data necessary for the design with expected accuracy.
- Research Organization:
- NAIG Nuclear Research Lab., Nippon Atomic Industry Group Co., Ltd., 4-1 Ukishima-cho, Kawasaki
- OSTI ID:
- 6986248
- Journal Information:
- Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 10:3; ISSN FUSTE
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ACCURACY
ALBEDO
BEAMS
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTER-AIDED DESIGN
DOSE RATES
ENERGY DEPENDENCE
GAMMA SPECTRA
GAMMA TRANSPORT THEORY
INCIDENCE ANGLE
LAYERS
M CODES
MONTE CARLO METHOD
NEUTRON SPECTRA
NEUTRON TRANSPORT THEORY
ONE-DIMENSIONAL CALCULATIONS
PARTICLE BEAMS
RADIATION STREAMING
SECONDARY BEAMS
SHIELDING
SLABS
SPECTRA
THERMONUCLEAR REACTORS
TRANSPORT THEORY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ACCURACY
ALBEDO
BEAMS
COMPUTER CALCULATIONS
COMPUTER CODES
COMPUTER-AIDED DESIGN
DOSE RATES
ENERGY DEPENDENCE
GAMMA SPECTRA
GAMMA TRANSPORT THEORY
INCIDENCE ANGLE
LAYERS
M CODES
MONTE CARLO METHOD
NEUTRON SPECTRA
NEUTRON TRANSPORT THEORY
ONE-DIMENSIONAL CALCULATIONS
PARTICLE BEAMS
RADIATION STREAMING
SECONDARY BEAMS
SHIELDING
SLABS
SPECTRA
THERMONUCLEAR REACTORS
TRANSPORT THEORY