Thermal-Hydraulic Systems Safety Analysis to Support the Design Process for the Advanced Neutron Source Reactor
| Autor: | L. S. Ghan, C. D. Fletcher |
|---|---|
| Rok vydání: | 1991 |
| Předmět: |
Nuclear and High Energy Physics
Source code Computer science 020209 energy Nuclear engineering media_common.quotation_subject 02 engineering and technology Nuclear reactor Condensed Matter Physics law.invention 020303 mechanical engineering & transports Safeguard 0203 mechanical engineering Nuclear Energy and Engineering Nuclear reactor core law 0202 electrical engineering electronic engineering information engineering Systems design Research reactor Light-water reactor Engineering design process media_common |
| Zdroj: | Nuclear Technology. 95:228-246 |
| ISSN: | 1943-7471 0029-5450 |
| Popis: | Large thermal-hydraulic systems computer codes are most often applied to investigate safety issues in existing nuclear facilities. One such code is applied to aid the design process for a proposed state-of-the-art research reactor. The RELAP5 computer code is used to simulate system response to hypothetical loss-of coolant accidents (LOCAs) in an early design of the Advanced Neutron Source (ANS). Among accident scenarios, a LOCA event is expected to be one of the most challenging to the ANS reactor core; similar analyses for other accident types are in progress. This is the first detailed study of ANS transient system response during accidents, and the outcome of the analysis is used to benefit the design process. The ANS model used is based on an early (preconceptual) cool ing system design layout. This early design has since been superseded by an improved design that is partly based on the results of these studies. The calculated responses of the early design to representative LOCA events are de... |
| Databáze: | OpenAIRE |
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