Published 1984
| Version v1
Book
A generalized finite difference model for PHWR system blow down
Creators
- 1. Reactor Analysis and Studies Section, Bhabha Atomic Research Centre, Bombay 400 085
Description
This paper deals with the development of a computer code based on a generalized finite difference scheme for simultaneous solution of one dimensional, one fluid partial differential equations. The mass, momentum and energy equations at point nodes are used for this analysis. Comparison of this technique with contemporary mass centred control volume approach has been discussed. The method has been applied for validation to published experimental results. The results obtained with this method for analysis of a Loss of Coolant Accident (LOCA) for a single ended rupture of the inlet cold header of Rajasthan Atomic Power Plant (RAPP) are presented
Additional details
Publishing Information
- Publisher
- Elsevier.
- Imprint Place
- New York, NY (USA)
- Imprint Title
- Multi-Phase flow and heat transfer III. Part B: Applications
- Journal Page Range
- p. 57-67.
Conference
- Title
- 3. multi-phase flow and heat transfer symposium.
- Dates
- 18-20 Apr 1983.
- Place
- Miami, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17045149
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; COMPUTER CODES; COMPUTERIZED SIMULATION; FINITE DIFFERENCE METHOD; FLOW MODELS; LOSS OF COOLANT; NUCLEAR POWER PLANTS; ONE-DIMENSIONAL CALCULATIONS; PARTIAL DIFFERENTIAL EQUATIONS; PHWR TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; DIFFERENTIAL EQUATIONS; EQUATIONS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; ITERATIVE METHODS; MATHEMATICAL MODELS; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL POWER PLANTS