Published 1977
| Version v1
Book
Computer code DAPSY for the calculation of pressure wave propagation in the primary coolant system of light water reactors
Description
For investigation of pressure wave phenomena in the primary coolant system it proved to be necessary to develop a computer code for the calculation of 3-dimensional single-phase and two-phase flow of water and steam. In order to avoid the severe difficulties of a 3-dimensional code an attempt was made to substitute the real geometry by the connection of one-dimensional flow paths to a pipe network. With such a pipe arrangement it is possible to apply known one-dimensional codes for the computation of the flow
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL
- Imprint Title
- Thermal reactor safety. Vol. I
- Journal Page Range
- p. 420-435.
Conference
- Title
- Thermal reactor safety meeting.
- Dates
- 31 Jul - 5 Aug 1977.
- Place
- Sun Valley, ID, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10437323
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; D CODES; PRESSURE GRADIENTS; PRIMARY COOLANT CIRCUITS; TWO-PHASE FLOW; WATER COOLED REACTORS; WAVE PROPAGATION
- Descriptors DEC
- COOLING SYSTEMS; FLUID FLOW; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS