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Japanese contributions to blanket design for ITER

Technical Report:

Abstract

ITER, the first integrated fusion nuclear experimental reactor, will be equipped with tritium breeding blanket to produce tritium required for the ITER operation, in which annual tritium consumption will reach 6 kg. All participants (Japan, the EC, the USA and the USSR) in the ITER CDA (Conceptual Design Activity) have conducted conceptual design of ITER blanket (cooling water temperature {<=} 100degC) utilizing their own technology bases. Because of superiority of currently available data base and technology, solid breeder blanket has been selected as the first option among many proposals including the solid breeder blankets, the liquid metal blankets and the aqueous lithium salt blankets. This report describes the results of the following design and analytical studies on the Japanese proposal of Li{sub 2}O pebble type blanket : 1) blanket structural concepts, 2) neutronics, 3) thermal-hydraulics, 4) mechanical characteristics, 5) tritium recovery process and tritium inventory, and 7) fabrication and assembly technology. (author).
Authors:
Kuroda, Toshimasa; Yoshida, Hiroshi; Takatsu, Hideyuki [1] 
  1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment; and others
Publication Date:
Aug 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-133
Reference Number:
SCA: 700450; PA: JPN-91:011232; SN: 92000630648
Resource Relation:
Other Information: PBD: Aug 1991
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER TOKAMAK; BREEDING BLANKETS; TRITIUM; BREEDING PELLETS; TRITIUM RECOVERY; INVENTORIES; SPECIFICATIONS; RESEARCH PROGRAMS; 700450; BLANKETS AND COOLING SYSTEMS
OSTI ID:
10110913
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE92751041; TRN: JP9111232
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
199 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Kuroda, Toshimasa, Yoshida, Hiroshi, and Takatsu, Hideyuki. Japanese contributions to blanket design for ITER. Japan: N. p., 1991. Web.
Kuroda, Toshimasa, Yoshida, Hiroshi, & Takatsu, Hideyuki. Japanese contributions to blanket design for ITER. Japan.
Kuroda, Toshimasa, Yoshida, Hiroshi, and Takatsu, Hideyuki. 1991. "Japanese contributions to blanket design for ITER." Japan.
@misc{etde_10110913,
title = {Japanese contributions to blanket design for ITER}
author = {Kuroda, Toshimasa, Yoshida, Hiroshi, and Takatsu, Hideyuki}
abstractNote = {ITER, the first integrated fusion nuclear experimental reactor, will be equipped with tritium breeding blanket to produce tritium required for the ITER operation, in which annual tritium consumption will reach 6 kg. All participants (Japan, the EC, the USA and the USSR) in the ITER CDA (Conceptual Design Activity) have conducted conceptual design of ITER blanket (cooling water temperature {<=} 100degC) utilizing their own technology bases. Because of superiority of currently available data base and technology, solid breeder blanket has been selected as the first option among many proposals including the solid breeder blankets, the liquid metal blankets and the aqueous lithium salt blankets. This report describes the results of the following design and analytical studies on the Japanese proposal of Li{sub 2}O pebble type blanket : 1) blanket structural concepts, 2) neutronics, 3) thermal-hydraulics, 4) mechanical characteristics, 5) tritium recovery process and tritium inventory, and 7) fabrication and assembly technology. (author).}
place = {Japan}
year = {1991}
month = {Aug}
}