Shield design for the Fusion Materials Irradiation Test facility

Conference · Tue Mar 01 00:00:00 EST 1983

OSTI ID:5816691

Carter, L L; Mann, F M; Morford, R J; Wilcox, A D; Johnson, D L; Huang, S T

The shield design for the Fusion Materials Irradiation Test facility is based upon one-, two- and three-dimensional transport calculations with experimental measurements utilized to refine the nuclear data including the neutron cross sections from 20 to 50 MeV and the gamma ray and neutron source terms. The high energy neutrons and deuterons produce activation products from the numerous reactions that are kinematically allowed. The analyses for both beam-on and beam-off (from the activation products) conditions have required extensive nuclear data libraries and the utilization of Monte Carlo, discrete ordinates, point kernel and auxiliary computer codes.

• Research Organization: Westinghouse Hanford Co., Richland, WA (USA); Parsons (Ralph M.) Co., Pasadena, CA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 5816691
• Report Number(s): HEDL-SA-2754-FP; CONF-830538-15; ON: DE83016006
• Resource Relation: Conference: 6. international conference on radiation shielding, Tokyo, Japan, 16 May 1983
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
FMIT LINAC
SHIELDING
DESIGN
CROSS SECTIONS
GAMMA RADIATION
NEUTRON REACTIONS
NEUTRON TRANSPORT THEORY
ACCELERATORS
BARYON REACTIONS
ELECTROMAGNETIC RADIATION
HADRON REACTIONS
IONIZING RADIATIONS
LINEAR ACCELERATORS
NUCLEAR REACTIONS
NUCLEON REACTIONS
RADIATIONS
TRANSPORT THEORY
700209* - Fusion Power Plant Technology- Component Development & Materials Testing