Multi-channel grouping techniques for conducting reactor safety studies
Conference
·
OSTI ID:7348285
In conducting safety studies for postulated unprotected accidents in an LMFBR system, it is common practice to employ multi-channel coupled neutronics, thermal hydraulics computer programs such as SAS3A or MELT-III. The multichannel feature of such code systems is important if the natural fuel failure incoherencies and the resulting sodium void/fuel motion reactivity feedbacks--which have strong spatial variations--are to be properly modeled. Because of the large amounts of computer time associated with many channel runs, however, there is a strong incentive to conduct parametric studies with as few channels as possible. The paper presented is focused on methods successfully employed to accomplish this end for a study of the hypothetical unprotected transient overpower accident conducted for the FFTF.
- Research Organization:
- Hanford Engineering Development Lab., Richland, Wash. (USA)
- OSTI ID:
- 7348285
- Report Number(s):
- HEDL-SA-996; CONF-751101-89
- Country of Publication:
- United States
- Language:
- English
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ACCIDENTS
COMPUTER CALCULATIONS
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FAST REACTORS
FFTF REACTOR
LIQUID METAL COOLED REACTORS
MATHEMATICAL MODELS
REACTOR ACCIDENTS
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RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST REACTORS