Simulation methodology for pressure tube integrity analysis and comparison with experiments
- 1. Ontario Hydro, Toronto, ON (Canada)
Description
The computer code SMARTT (Simulation Method for Azimuthal and Radial Temperature Transients) is used in safety analysis of CANDU reactors to predict fuel and pressure tube thermal and mechanical behaviour under asymmetric coolant conditions such as stratified flow. This paper presents comparisons of SMARTT predictions with preliminary results of two experiments in which large temperature non-uniformities developed on pressure tubes undergoing heatup and transverse strain at 1.0 MPa internal pressure. Temperature asymmetries developed as a result of slow boil-off of coolant in the channel. The SMARTT temperature predictions are shown to agree well with the experimental results. SMARTT accurately predicts the time at which the pressure tube balloons into contact with the calandria tube. The transient liquid level in the channel can also be accurately predicted using a simple venting/boil-off model
Additional details
Additional titles
- Augmented title (English)
- SMARTT code
Publishing Information
- ISBN
- 0-919784-11-9
- Imprint Title
- Proceedings of the 2. international conference on simulation methods in nuclear engineering
- Imprint Pagination
- 950 p.
- Journal Page Range
- p. 515-533.
- Report number
- INIS-mf--12868(v.1,2)
Conference
- Title
- 2. International conference on simulation methods in nuclear engineering.
- Dates
- 14-16 Oct 1986.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 22063961
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; DEFORMATION; FUEL CHANNELS; LOSS OF COOLANT; PRESSURE TUBES; S CODES; TEMPERATURE DISTRIBUTION; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; FLUID FLOW; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; TUBES