Published November 2018 | Version v1
Journal article

Availability improvement of ITER blanket remote handling system

  • 1. Department of ITER Project, National Institutes for Quantum and Radiological Science and Technology, Naka-shi, Ibaraki-ken 311-0193 (Japan)
  • 2. Advanced System Design & Engineering Dept., Isogo Nuclear Engineering Center, Toshiba Corporation, Yokohama-shi, Kanagawa-ken, 235-8522 (Japan)

Description

Highlights: •Characteristics of the remote-handling systems for fusion reactors and methods to improve their availability were studied. •It was concluded that preventive maintenance is a powerful method to improve availability of the remote-handling systems. •A procedure to optimise parameters of preventive maintenance was proposed. •By applying the procedure to the ITER Blanket Remote Handling System, effectiveness of the procedure was shown. -- Abstract: Availability is of the utmost importance in remote-handling systems for fusion reactors. A number of factors are specific to this application in terms of availability. After investigating those factors, we have concluded that preventive maintenance is the best method to universally increase remote handling system availability. As such, we created a procedure through reliability block diagram analysis that takes availability, completion probability, and number of failures into account to determine the parameters for preventive maintenance and determine the quantity of spare parts required. By applying our procedure preventive maintenance increased the availability of the ITER blanket remote handling system from 46% to 88%, while the expected number of total failures was reduced from 5.5 to 1.6. Completion probability remained at virtually 100%, thus demonstrating that our procedure can improve system availability.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2018.02.049

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2018.02.049;
PII
S0920379618301509;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
136
Journal Issue
Part A
Journal Page Range
p. 390-393
ISSN
0920-3796
CODEN
FEDEEE

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
51017605
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
AVAILABILITY; FAILURES; ITER TOKAMAK; MAINTENANCE; PROBABILITY; RELIABILITY; REMOTE HANDLING
Descriptors DEC
CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
© 2018 Elsevier B.V. All rights reserved.