Hybrid computer model for the loss-of-coolant accident in pressurized water reactors
Book
·
OSTI ID:4350948
From international nuclear industries fair; Basel, Switzerland (16 Oct 1972). The current analytical techniques for the prediction of the plant dynamic behavior during a loss-of-coolant accident in pressurized water reactors are inadequate. More sophisticated approaches, needed for the plant safety evaluation, require prohibitively large amount of digital computer storage and running time. A hybrid (digital-analog) computer technique as a means for improving the computational efficiency for the solution of the loss-of-coolant accident problem. (6 references) (auth)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-29-026018
- OSTI ID:
- 4350948
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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