Published June 1980
| Version v1
Report
Computational methods with respect to LOCA transient analysis
Description
LOCA simulation presents a wide range of problems to the analyst. Widely differing time scales for the important physical phenonema require the use of numerical schemes with high levels of implicitness and robust characteristics. The TRAC computer code has been designed using economical yet stable finite difference algorithms. The important short time constant phenonema are incorporated implicity and blended schemes allow material Courant limits to be exceeded in some of the one dimensional components. A new two-step procedure will allow future versions to handle small break LOCA's even more efficiently
Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Title
- Thermal reactor safety
- Journal Page Range
- p. 632-638.
- Report number
- CONF-800403--(Vol.1)
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
- 11570346
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; 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