SASSYS analysis of EBR-II SHRT experiments
Description
SASSYS is a general purpose one-dimensional thermal-hydraulic LMR systems analysis code. The application of SASSYS to studies of protected and unprotected transient analysis of LMR designs, such as PRISM and SAFR, is commonplace. This usage requires that a strong validation base exist for SASSYS. Validation of a code such as SASSYS is made up of a variety of activities such as, application of separate component models to model problems where the solution is analytically known, cross comparison with other codes and, most importantly, comparison with experiment. The EBR-II reactor is being used to perform experiments that address a wide range of LMR safety issues. The most important of these so far have been the SHRT series of experiments, begun in 1984, which culminated in the unprotected loss-of-flow and loss-of-heat sink transients performed as a demonstration to an international audience of fast reactor experts. The SASSYS-1 systems thermal hydraulic code for LMR's has been applied to the analysis of selected EBR-II SHRT experiments. The results show that SASSYS can predict the transient thermal hydraulic and reactivity behavior of EBR-II under these conditions. This contributes to the validation of the modelling of EBR-II with SASSYS and of the code itself
Availability note (English)
Available from NTIS, PC A02/MF A01; 1 as DE87011371.Files
19023867.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- CONF-871101--20
Conference
- Title
- Joint meeting of the American Nuclear Society and the Atomic Industrial Forum.
- Dates
- 15-19 Nov 1987.
- Place
- Los Angeles, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19023867
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EBR-2 REACTOR; EXPERIMENT PLANNING; HEAT TRANSFER; HYDRAULICS; LOSS OF FLOW; ONE-DIMENSIONAL CALCULATIONS; PUMPS; REACTIVITY; REACTOR COOLING SYSTEMS; REACTOR SAFETY; S CODES; SPECIFICATIONS; SYSTEMS ANALYSIS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; EQUIPMENT; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; PLANNING; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SODIUM COOLED REACTORS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.