Simulation and analysis of the thermal and deformation behaviour of 'as-received' and 'hydrided' pressure tubes used in the circumferential temperature distribution experiments (end of life/pressure tube behaviour)
Description
It is postulated that in-reactor pressure tubes may be subjected to radiation damage and dissolved deuterium which could change the pressure tube characteristics and lead to different behaviour than that of as-received pressure tubes under large LOCA (loss of coolant) conditions. A hydrided pressure tube was used to study the effect of dissolved hydrogen on thermal-mechanical behaviour. In the experiment, simulating an in-reactor (hydrided) pressure tube with circumferential differential temperature under boil-off conditions, the pressure tube ballooned into contact with the calandria tube. The pressure tube used in this experiment was hydrided in a furnace to a nominal value of 200 μg/g dissolved hydrogen. This test was a repeat of the first supplementary boil-off test (S-5-1) which used an as-received pressure tube. The objective of this paper is to analyze the results obtained from the simulation of this Boil-Off test using the SMARTT computer code and to examine the effect of hydriding on the thermal and ballooning behaviour of the pressure tube by comparison with the results obtained from test S-5-1. A discussion of the results obtained from this comparison is presented together with an analysis of their application to the analysis of pressure tube behaviour in CANDU reactors. (author). 13 refs., 1 tab., 16 figs
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Additional details
Publishing Information
- Imprint Title
- CNS proceedings of the 16. annual conference, volume I and II
- Imprint Pagination
- 2 v.
- Journal Page Range
- (v.2) [16 p.].
- Report number
- INIS-CA--0053
Conference
- Title
- 16. Annual conference of the Canadian Nuclear Society.
- Dates
- 4-7 Jun 1995.
- Place
- Saskatoon, SK (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 28076177
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; CREEP; DEFORMATION; DRYOUT; EXPERIMENTAL DATA; FUEL CHANNELS; HEAT TRANSFER; HYDRIDATION; LOSS OF COOLANT; PICKERING-1 REACTOR; PRESSURE TUBES; REACTOR SAFETY EXPERIMENTS; S CODES; SPATIAL DISTRIBUTION; STRAINS; TEMPERATURE DISTRIBUTION; THERMAL STRESSES
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; COMPUTER CODES; DATA; DISTRIBUTION; ENERGY TRANSFER; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; MECHANICAL PROPERTIES; NATURAL URANIUM REACTORS; NUMERICAL DATA; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SIMULATION; STRESSES; THERMAL REACTORS; TUBES