A PC-based computer program for simulation of containment pressurization
Description
This paper reports that a PC-based computer program has been developed to simulate a pressurized water reactor (PWR) containment during various transients. This containment model is capable of determining pressure and temperature history of a PWR containment in the event of a loss of coolant accident, as well as main steam line breaks inside the containment. Conservation of mass and energy equations are applied to the containment model. Development of the program is based on minimization of input specified information and user friendliness. Maximization of calculation efficiency is obtained by superseding the traditional trial and error procedure for determination of the state variables and implementation of an explicit solution for pressure. The program includes simplified models for active heat removal systems. The results are in close agreement between the present model and CONTEMPT-MOD5 computer code for pressure and temperature inside the containment
Additional details
Publishing Information
- Publisher
- Society for Computer Simulation.
- Imprint Place
- Philadelphia, PA (United States)
- ISBN
- 0-911801-67-7
- Imprint Title
- Proceedings of simulators VII
- Imprint Pagination
- 328 p.
- Journal Page Range
- p. 216-220.
Conference
- Title
- 1990 Society for Computer Simulation (SCS) Eastern multiconference.
- Dates
- 23-26 Apr 1990.
- Place
- Nashville, TN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24027411
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTER CODES; HEAT TRANSFER; LOSS OF COOLANT; MICROCOMPUTERS; PERFORMANCE TESTING; PRESSURE GRADIENTS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY EXPERIMENTS; REACTOR SIMULATORS; REAL TIME SYSTEMS; RELIABILITY; TEMPERATURE GRADIENTS; TESTING; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; ANALOG SYSTEMS; COMPUTERS; COOLING SYSTEMS; DIGITAL COMPUTERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUNCTIONAL MODELS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-900494--.