Analysis of delayed creep rupture test conditions to qualify new calandria tubes for CANDU-6 reactors
Creators
- 1. Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)
Description
CATHENA Mod 3.5c/Rev 0 model was used to conservatively calculate the quasi steady-state temperature and pressure conditions that are likely to exist if a pressure tube were to break spontaneously within a CANDU-6 reactor during normal operating conditions. The objective of the analysis was to recommend test conditions to assess calandria-tube resistance to delayed creep failure. These CT test conditions are required to design full-scale creep rupture tests that represent the conditions expected in a CANDU-6 reactor that would exist shortly after a spontaneous pressure-tube rupture. The calculated average through-wall CT temperatures for the quasi steady-state period following inlet, centre, and outlet pressure-tube breaks were 176oC, 186oC, and 194oC, respectively. Thus the analysis indicated that it would be conservative if future creep-rupture tests for new CANDU-6 calandria tubes were performed at a uniform temperature between 176oC and 194oC. The 176oC and 194oC average calandria-tube temperatures correspond to a pressure of 11.02 MPa and 10.55 MPa, respectively. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-80-1
- Imprint Title
- 6. International conference on simulation methods in nuclear engineering
- Imprint Pagination
- 119 Megabytes
- Journal Page Range
- [15 p.]
Conference
- Title
- 6. international conference on simulation methods in nuclear engineering
- Dates
- 12-15 Oct 2004
- Place
- Montreal, Quebec (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 36107449
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALANDRIAS; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; CREEP; PRESSURE TUBES
- Descriptors DEC
- CONTAINERS; HEAVY WATER MODERATED REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; TUBES
Optional Information
- Notes
- 6 refs., 2 tabs., 7 figs.