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Shielding analysis of the ITER/EDA NBI duct

Technical Report:

Abstract

This report discusses the shielding properties of the ITER/EDA NBI ducts based on the current JCT design of the 24 superconductive toroidal field coils (the 24 TFC). The two-dimensional transport calculations have been performed by DOT 3.5. First, the neutron fluxes, dose to insulator and peak nuclear heating rate were calculated in the TFC and the NBI duct. The X-Y calculational model with detail description of the neutron source shape and the TFC geometry is used for that calculation. Second, the R-Z calculational model with detail description of the NBI components was set up. The nuclear heating in the NBI cryo panels and displacement damage in NBI copper grids were obtained in that calculation. In summary, it it concluded that the shielding performance of the current NBI duct design is enough to decrease all considered neutronics responses below the limits. (author).
Authors:
Zimin, S; Takatsu, Hideyuki; Sato, Satoshi; Tsunematsu, Toshihide; Inoue, Takashi; Ohara, Yoshihiro; [1]  Maki, Koichi
  1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Publication Date:
Aug 01, 1994
Product Type:
Technical Report
Report Number:
JAERI-Tech-94-015
Reference Number:
SCA: 700460; PA: JPN-94:012130; EDB-95:026565; SN: 95001319938
Resource Relation:
Other Information: PBD: Aug 1994
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER TOKAMAK; SHIELDS; SHIELDING; FAST NEUTRONS; NEUTRON TRANSPORT; NEUTRON LEAKAGE; NEUTRON FLUX; NEUTRON FLUENCE; 700460; HEATING AND FUELING SYSTEMS; FUELS
OSTI ID:
10109266
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE95737222; TRN: JP9412130
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
42 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Zimin, S, Takatsu, Hideyuki, Sato, Satoshi, Tsunematsu, Toshihide, Inoue, Takashi, Ohara, Yoshihiro, and Maki, Koichi. Shielding analysis of the ITER/EDA NBI duct. Japan: N. p., 1994. Web.
Zimin, S, Takatsu, Hideyuki, Sato, Satoshi, Tsunematsu, Toshihide, Inoue, Takashi, Ohara, Yoshihiro, & Maki, Koichi. Shielding analysis of the ITER/EDA NBI duct. Japan.
Zimin, S, Takatsu, Hideyuki, Sato, Satoshi, Tsunematsu, Toshihide, Inoue, Takashi, Ohara, Yoshihiro, and Maki, Koichi. 1994. "Shielding analysis of the ITER/EDA NBI duct." Japan.
@misc{etde_10109266,
title = {Shielding analysis of the ITER/EDA NBI duct}
author = {Zimin, S, Takatsu, Hideyuki, Sato, Satoshi, Tsunematsu, Toshihide, Inoue, Takashi, Ohara, Yoshihiro, and Maki, Koichi}
abstractNote = {This report discusses the shielding properties of the ITER/EDA NBI ducts based on the current JCT design of the 24 superconductive toroidal field coils (the 24 TFC). The two-dimensional transport calculations have been performed by DOT 3.5. First, the neutron fluxes, dose to insulator and peak nuclear heating rate were calculated in the TFC and the NBI duct. The X-Y calculational model with detail description of the neutron source shape and the TFC geometry is used for that calculation. Second, the R-Z calculational model with detail description of the NBI components was set up. The nuclear heating in the NBI cryo panels and displacement damage in NBI copper grids were obtained in that calculation. In summary, it it concluded that the shielding performance of the current NBI duct design is enough to decrease all considered neutronics responses below the limits. (author).}
place = {Japan}
year = {1994}
month = {Aug}
}