You need JavaScript to view this

A study on radiation shielding analysis for toroidal field coils of a tokamak-type fusion reactor

Technical Report:

Abstract

A study on the radiation shield for toroidal field (TF) coils of a tokamak type fusion device is reported. The study was performed to provide the design data base for the radiation shielding analysis for TF coils which can be commonly used for other systems, and to produce some universal recommendation about the neutron flux attenuation in the shield of a fusion reactor. Some simple estimation procedure instead of difficult and expensive neutron calculation can be carried out in this case on the basis of the fundamental knowledge on neutron behavior. The present studies are composed of the fundamentals required for shield estimation, the analysis of shield effectiveness, the analysis of the shielding performance of blankets, the analysis of radiation permeating through the inhomogeneous blanket and shield of a fusion reactor, and the analysis of the TF coil shield of the International Thermonuclear Experimental Reactor (ITER) on the basis of the results of the ITER conceptual design activities for three years. The methodological recommendation was developed for the ANISN and the DOT3 codes. (K.I.).
Authors:
Zimin, Sergei [1] 
  1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Publication Date:
Aug 01, 1992
Product Type:
Technical Report
Report Number:
JAERI-M-92-120
Reference Number:
SCA: 700480; PA: JPN-92:011319; SN: 93000918724
Resource Relation:
Other Information: PBD: Aug 1992
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER TOKAMAK; SHIELDING; THERMONUCLEAR REACTORS; MAGNET COILS; SHIELDS; BREEDING BLANKETS; RADIATION STREAMING; NEUTRON TRANSPORT THEORY; FAST NEUTRONS; SUPERCONDUCTING COILS; HEATING; NEUTRON FLUX; CROSS SECTIONS; SENSITIVITY ANALYSIS; NEUTRON REACTIONS; 700480; COMPONENT DEVELOPMENT; MATERIALS STUDIES
OSTI ID:
10111324
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE93753398; TRN: JP9211319
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
226 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Zimin, Sergei. A study on radiation shielding analysis for toroidal field coils of a tokamak-type fusion reactor. Japan: N. p., 1992. Web.
Zimin, Sergei. A study on radiation shielding analysis for toroidal field coils of a tokamak-type fusion reactor. Japan.
Zimin, Sergei. 1992. "A study on radiation shielding analysis for toroidal field coils of a tokamak-type fusion reactor." Japan.
@misc{etde_10111324,
title = {A study on radiation shielding analysis for toroidal field coils of a tokamak-type fusion reactor}
author = {Zimin, Sergei}
abstractNote = {A study on the radiation shield for toroidal field (TF) coils of a tokamak type fusion device is reported. The study was performed to provide the design data base for the radiation shielding analysis for TF coils which can be commonly used for other systems, and to produce some universal recommendation about the neutron flux attenuation in the shield of a fusion reactor. Some simple estimation procedure instead of difficult and expensive neutron calculation can be carried out in this case on the basis of the fundamental knowledge on neutron behavior. The present studies are composed of the fundamentals required for shield estimation, the analysis of shield effectiveness, the analysis of the shielding performance of blankets, the analysis of radiation permeating through the inhomogeneous blanket and shield of a fusion reactor, and the analysis of the TF coil shield of the International Thermonuclear Experimental Reactor (ITER) on the basis of the results of the ITER conceptual design activities for three years. The methodological recommendation was developed for the ANISN and the DOT3 codes. (K.I.).}
place = {Japan}
year = {1992}
month = {Aug}
}