Strain model and zircaloy-steam reaction model in the TUF code and their application in large LOCA
Description
As an integral part of a generic study of the Emergency Coolant Injection System effectiveness in Ontario Hydro reactors during a large break Loss of Coolant Accident (LOCA), the TUF (Two-Unequal-Fluids) code has been developed to enhance safety analysis capability. Recent enhancement to the TUF code includes the pressure tube transverse strain model and the zircaloy-steam reaction model. These models are employed to predict thermal-mechanical response of fuel channels and determine the thermal heat load to the moderator during postulated large LOCA scenarios. Presented in this paper are the description of the models, the cross-code comparison of the predictions between the TUF code and the SMARTT code and the discussion of parameters that may affect the pressure tube strain and the effect of pressure tube ballooning into contact with the calandria tube on the system response simulations. The modified TUF code is employed to quantify the extent of pressure tube ballooning and to calculate the thermal heat load to moderator. (author) 14 refs., 4 tabs., 16 figs
Additional details
Additional titles
- Augmented title (English)
- Loss of coolant accidents
Publishing Information
- Imprint Title
- Proceedings of the Canadian Nuclear Society 15. annual conference
- Imprint Pagination
- [1000 p.].
- Journal Page Range
- (v.1) [22 p.].
- ISSN
- 0227-1907
- Report number
- INIS-mf--14987(v.1,2)
Conference
- Title
- 15. annual conference of the Canadian Nuclear Society; 34. annual conference of the Canadian Nuclear Association.
- Dates
- 5-8 Jun 1994.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 28014275
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; ECCS; FUEL CHANNELS; FUEL-COOLANT INTERACTIONS; HEAT TRANSFER; LOSS OF COOLANT; OXIDATION; PRESSURE TUBES; REACTOR SAFETY; S CODES; STEAM; STRAINS; T CODES; TWO-PHASE FLOW; ZIRCALOY 4
- Descriptors DEC
- ACCIDENTS; ALLOY-ZR98SN-4; ALLOYS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; COMPUTER CODES; CORROSION RESISTANT ALLOYS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; EVALUATION; FLUID FLOW; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAVY WATER MODERATED REACTORS; IRON ADDITIONS; MATERIALS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TUBES; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS