Published 1985 | Version v1
Book Metadata-only

Development of non-linear seismic analysis code - full scale modal testing for CANDU 600 MWe fuelling machine

Creators

  • 1. Atomic Energy of Canada Ltd., Sheridan Park, Ontario. CANDU Operations
  • 2. Electric Power Development Co. Ltd., Tokyo (Japan)
  • 3. Muto Inst. of Structural Mechanics, Inc., Tokyo (Japan)

Description

This paper describes the approach adopted to study the dynamic behaviour of the CANDU 600 fuelling machine system with its unique on power refuelling capability in order to seismically qualify the CANDU Reactor for use in Japan. A description is given of the features and functions of a special purpose non-linear finite element code developed for the dynamic analysis of the system. The results obtained from this code and the full scale modal testing are correlated and the correlation analysis results are presented. (orig.)

Additional details

Publishing Information

Publisher
North-Holland.
Imprint Place
Amsterdam (Netherlands)
ISBN
0-444-86965-4
Imprint Title
Transactions of the 8th international conference on structural mechanics in reactor technology. Vol. K(b)
Imprint Pagination
543 p.
Journal Page Range
p. 401-407.

Conference

Title
8. international conference on structural mechanics in reactor technology (SMIRT-8).
Dates
19-23 Aug 1985.
Place
Brussels (Belgium).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
19078799
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CANDU TYPE REACTORS; DYNAMIC LOADS; FINITE ELEMENT METHOD; JAPAN; MATHEMATICAL MODELS; MECHANICAL TESTS; REACTOR CHARGING MACHINES; SEISMIC EFFECTS; VERIFICATION
Descriptors DEC
ASIA; DEVELOPED COUNTRIES; HEAVY WATER MODERATED REACTORS; MATERIALS TESTING; NUMERICAL SOLUTION; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS

Optional Information

Secondary number(s)
EUR--10001-DE/EN/FR.