Published 1997
| Version v1
Miscellaneous
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Design verification of the CANFLEX fuel bundle - quality assurance requirements for mechanical flow testing
Creators
- 1. Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)
- 2. Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)
Description
As part of the design verification program for the new fuel bundle, a series of out-reactor tests was conducted on the CANFLEX 43-element fuel bundle design. These tests simulated current CANDU 6 reactor normal operating conditions of flow, temperature and pressure. This paper describes the Quality Assurance (QA) Program implemented for the tests that were run at the testing laboratories of Atomic Energy of Canada Limited (AECL) and Korea Atomic energy Research Institute (KAERI). (author)
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31006080.pdf
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Additional details
Publishing Information
- ISBN
- 0-919784-50-X
- Imprint Title
- Proceedings of the fifth international conference on CANDU fuel. V.1,2
- Imprint Pagination
- [923 p.]
- Journal Page Range
- (v.1) p. 52-59
- Report number
- INIS-CA--0072
Conference
- Title
- 5. International conference on CANDU fuel
- Dates
- 21-25 Sep 1997
- Place
- Toronto, ON (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 31006080
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; COORDINATED RESEARCH PROGRAMS; FEASIBILITY STUDIES; FUEL ELEMENT CLUSTERS; KAERI; MECHANICAL TESTS; QUALITY ASSURANCE; REACTOR SAFETY; THERMAL STRESSES; VERIFICATION
- Descriptors DEC
- FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; KOREAN ORGANIZATIONS; MATERIALS TESTING; NATIONAL ORGANIZATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; RESEARCH PROGRAMS; SAFETY; STRESSES; TESTING; THERMAL REACTORS
Optional Information
- Notes
- 4 refs., 1 tab., 1 fig.