Development of the MINI-SMARTT code for fuel element/pressure tube contact
- 1. Ontario Hydro, Toronto, ON (Canada)
Description
The MINI-SMARTT computer code was developed at Ontario Hydro from the existing SMARTT computer code in order to analyse the thermal-mechanical behaviour of the pressure tube due to the contact of a hot fuel element (FE/PT contact). This paper describes the development of the models used in the MINI-SMARTT code and its application to the FE/PT contact accident scenario. Sensitivity studies examining the effect of various parameters on code predictions and sample FE/PT contact calculations are included. The results given show that the MINI-SMARTT code is a flexible model which may be used to predict the thermal-mechanical behaviour of the pressure tube under a wide range of FE/PT contact conditions. Comparisons of MINI-SMARTT predictions with a detailed pin radiation code show close agreement for heat flux and pressure tube temperatures
Additional details
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. 534-550.
- 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
- 22063962
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; DEFORMATION; FUEL ELEMENTS; HEAT TRANSFER; LOSS OF COOLANT; M CODES; PRESSURE TUBES; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; TUBES