Published 2001 | Version v1
Miscellaneous Open

Assessment of structural integrity of Monju steel liner against sodium leakage and combustion. Overview

Creators

  • 1. Japan Nuclear Cycle Development Institute, Monju Construction Office, Fukui (Japan)
  • 2. Japan Nuclear Cycle Development Institute, Oarai Engineering Center, Ibaraki (Japan)
  • 3. Kawasaki Heavy Industries, LTD, Tokyo (Japan)

Description

This report overviews the structural analyses and model tests to estimate the structural integrity of the lining structure of Monju under a postulated condition of sodium leakage and combustion. In these evaluations, both thinning of the liner due to molten salt type corrosion and thermal loading on the liner are conservatively assumed. Strain limits are determined and used to judge the structural integrity of the liner on basis of tensile and bending tests of the liner material. (author)

Availability note (English)

Available from INIS in electronic form

Files

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Additional details

Publishing Information

Imprint Pagination
[19 p.]
Report number
INIS-FR--961

Conference

Title
9. international conference on nuclear engineering
Dates
8-12 Apr 2001
Place
Nice, Acropolis (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
33015271
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENDING; CORROSION; F CODES; MOCKUP; MONJU REACTOR; REACTOR SAFETY; SIMULATION; SODIUM; THERMAL STRESSES
Descriptors DEC
ALKALI METALS; BREEDER REACTORS; CHEMICAL REACTIONS; COMPUTER CODES; DEFORMATION; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; METALS; POWER REACTORS; REACTORS; SAFETY; SODIUM COOLED REACTORS; STRESSES; STRUCTURAL MODELS

Optional Information

Notes
7 refs.