Analysis of transient dry patch behavior on CANDU reactor calandria tubes in a LOCA with late stagnation and impaired ECI
Description
An analytical method to describe the behavior of transient dry patches on CANDU reactor calandria tubes has been developed. Dry patches may form following the sagging of a pressure tube onto a calandria tube in certain low-probability scenarios in which a loss-of-coolant accident occurs with subsequent failure or impairment of the emergency cooling injection function. Results of the analysis show that the dry patches will not grow beyond a few degrees on each side of the bottom of the calandria tube and will rewet within a few tens of seconds, with the values depending on the specific CANDU reactor design and the mechanism of dry patch formation and rewetting. Maximum local calandria tube temperatures reached during the transient will be about 5500C to 7000C. There will be no significant effects (<150C) on fuel, sheath and maximum pressure tube temperatures. The analytical results provide confidence that pressure tube and calandria tube integrity will not be threatened by dry-patch formation in the LOCA scenarios studied
Files
Additional details
Publishing Information
- Imprint Title
- Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 3
- Journal Page Range
- p. 1556-1566.
- Report number
- NUREG/CP--0027-Vol.3
Conference
- Title
- International meeting on thermal nuclear reactor safety (ANS topical meeting).
- Dates
- 29 Aug - 2 Sep 1982.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14792463
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; DEFORMATION; DRYOUT; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PRESSURE TUBES; REACTOR SAFETY; SPATIAL DISTRIBUTION; TEMPERATURE DISTRIBUTION; THERMAL STRESSES
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; STRESSES; THERMAL REACTORS; TUBES