Skyshine study for next generation of fusion devices

Conference · Sun Feb 01 00:00:00 EST 1987

OSTI ID:6056838

Gohar, Y; Yang, S

A shielding analysis for next generation of fusion devices (ETR/INTOR) was performed to study the dose equivalent outside the reactor building during operation including the contribution from neutrons and photons scattered back by collisions with air nuclei (skyshine component). Two different three-dimensional geometrical models for a tokamak fusion reactor based on INTOR design parameters were developed for this study. In the first geometrical model, the reactor geometry and the spatial distribution of the deuterium-tritium neutron source were simplified for a parametric survey. The second geometrical model employed an explicit representation of the toroidal geometry of the reactor chamber and the spatial distribution of the neutron source. The MCNP general Monte Carlo code for neutron and photon transport was used to perform all the calculations. The energy distribution of the neutron source was used explicitly in the calculations with ENDF/B-V data. The dose equivalent results were analyzed as a function of the concrete roof thickness of the reactor building and the location outside the reactor building.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6056838
• Report Number(s): CONF-870405-15; ON: DE87011531; TRN: 87-031649
• Resource Relation: Conference: Topical conference on theory and practice in radiation protection and shielding, Knoxville, TN, USA, 22 Apr 1987; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
TOKAMAK TYPE REACTORS
RADIATION SCATTERING ANALYSIS
SHIELDING
CONCRETES
DEUTERIUM
EXPERIMENTAL DATA
MATHEMATICAL MODELS
MONTE CARLO METHOD
NEUTRON SOURCES
NEUTRON TRANSPORT
PHOTON TRANSPORT
RADIATION DOSES
RADIATION PROTECTION
TRITIUM
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CHEMICAL ANALYSIS
DATA
DOSES
HYDROGEN ISOTOPES
INFORMATION
ISOTOPES
LIGHT NUCLEI
MATERIALS
NEUTRAL-PARTICLE TRANSPORT
NONDESTRUCTIVE ANALYSIS
NUCLEI
NUMERICAL DATA
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
PARTICLE SOURCES
RADIATION SOURCES
RADIATION TRANSPORT
RADIOISOTOPES
STABLE ISOTOPES
THERMONUCLEAR REACTORS
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering
700206 - Fusion Power Plant Technology- Environmental Aspects