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Design study of fusion experimental reactor tritium plant, (2). Tritiated water and radioactive solid waste processing facilities

Abstract

A preliminary design study of radio active waste processing and storage plants has been carried out for the ITER-CDA like fusion experimental reactor. The present report describes specifications of major components, system configuration, and building layout of the following plants; (1) Review of industrial technology for processing low level solid wastes from commercial nuclear power stations in Japan, (2) Water distillation plant for tritium reduction of the fusion experimental reactor primary cooling loop, (3) Water distillation plants for detritiation of tritiated waste water generated from the reactor building tritium safety systems, (4) Low level solid wastes processing facilities, (5) High level rad-wastes transportation facility, (6) Storage facility (5-year capacity) for the high and low level solid wastes. It was quantitatively clarified that realistic design of fusion experimental reactor with small production of radio active wastes is one of the key concerns for the realization of its construction in the early next stage. (author).
Authors:
Yoshida, Hiroshi; Naruse, Hideo; Ohkawa, Yoshinao; [1]  Asahara, Masaharu; Yokogawa, Nobuhisa; Tanemori, Nozomu; Horikiri, Hitoshi
  1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Publication Date:
Jul 01, 1993
Product Type:
Technical Report
Report Number:
JAERI-M-93-136
Reference Number:
SCA: 052001; 700460; PA: JPN-93:011139; EDB-94:011949; ERA-19:003168; NTS-94:014117; SN: 93001119355
Resource Relation:
Other Information: PBD: Jul 1993
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; D-T REACTORS; RADIOACTIVE WASTE PROCESSING; WASTE STORAGE; ITER TOKAMAK; BREEDING BLANKETS; TRITIUM; TRITIUM RECOVERY; WASTE DISPOSAL; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; 052001; 700460; WASTE PROCESSING; HEATING AND FUELING SYSTEMS; FUELS
OSTI ID:
10110102
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE94727552; TRN: JP9311139
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
128 p.
Announcement Date:
Jun 30, 2005

Citation Formats

Yoshida, Hiroshi, Naruse, Hideo, Ohkawa, Yoshinao, Asahara, Masaharu, Yokogawa, Nobuhisa, Tanemori, Nozomu, and Horikiri, Hitoshi. Design study of fusion experimental reactor tritium plant, (2). Tritiated water and radioactive solid waste processing facilities. Japan: N. p., 1993. Web.
Yoshida, Hiroshi, Naruse, Hideo, Ohkawa, Yoshinao, Asahara, Masaharu, Yokogawa, Nobuhisa, Tanemori, Nozomu, & Horikiri, Hitoshi. Design study of fusion experimental reactor tritium plant, (2). Tritiated water and radioactive solid waste processing facilities. Japan.
Yoshida, Hiroshi, Naruse, Hideo, Ohkawa, Yoshinao, Asahara, Masaharu, Yokogawa, Nobuhisa, Tanemori, Nozomu, and Horikiri, Hitoshi. 1993. "Design study of fusion experimental reactor tritium plant, (2). Tritiated water and radioactive solid waste processing facilities." Japan.
@misc{etde_10110102,
title = {Design study of fusion experimental reactor tritium plant, (2). Tritiated water and radioactive solid waste processing facilities}
author = {Yoshida, Hiroshi, Naruse, Hideo, Ohkawa, Yoshinao, Asahara, Masaharu, Yokogawa, Nobuhisa, Tanemori, Nozomu, and Horikiri, Hitoshi}
abstractNote = {A preliminary design study of radio active waste processing and storage plants has been carried out for the ITER-CDA like fusion experimental reactor. The present report describes specifications of major components, system configuration, and building layout of the following plants; (1) Review of industrial technology for processing low level solid wastes from commercial nuclear power stations in Japan, (2) Water distillation plant for tritium reduction of the fusion experimental reactor primary cooling loop, (3) Water distillation plants for detritiation of tritiated waste water generated from the reactor building tritium safety systems, (4) Low level solid wastes processing facilities, (5) High level rad-wastes transportation facility, (6) Storage facility (5-year capacity) for the high and low level solid wastes. It was quantitatively clarified that realistic design of fusion experimental reactor with small production of radio active wastes is one of the key concerns for the realization of its construction in the early next stage. (author).}
place = {Japan}
year = {1993}
month = {Jul}
}