Published June 1980
| Version v1
Report
COBRA-TF reflood model and analysis of FLECHT reflood experiments
Description
COBRA-TF, a two-fluid, three-field transient thermal hydraulic analysis code is being developed at PNL. To simulate bottom reflood tests, both a reflood entrainment model and a quench front model have been developed. Qualification of this model is underway and several FLECHT forced reflood tests (3 to 15 cm/sec reflood rate) have been simulated. Generally good data comparisons were achieved, though areas for further improvement were indicated
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Title
- Thermal reactor safety
- Journal Page Range
- p. 975-982.
- Report number
- CONF-800403--(Vol.2)
Conference
- Title
- ANS thermal reactor safety meeting.
- Dates
- 8 - 11 Apr 1980.
- Place
- Knoxville, TN, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11570366
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS