Published 1997 | Version v1
Miscellaneous Open

Design verification of the CANFLEX fuel bundle - quality assurance requirements for mechanical flow testing

  • 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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Part of:
Proceedings of the fifth international conference on CANDU fuel. V.1,2

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)

Optional Information

Notes
4 refs., 1 tab., 1 fig.