Published May 1986
| Version v1
Report
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Documentation of input data and model parameters for the SAS3D ULOF simulation of the SNR-300 Mark-II EOC7 core
Description
A model of the SNR-300 Mark-II core at end of cycle 7 (EOC7) has been set up at KfK for the simulation of the unprotected loss of flow (ULOF) accidents with the SAS3D code. This report documents the channel definition for this model, the geometrical and thermohydraulic data of the different channels and of the primary loop. It also gives the assumptions applied in the simulation of the initial sate of the core for fuel restructuring, fuel and clad swelling and for the steady state gas release. The appendix includes the correction sets to the SAS3D source that have been specifically introduced for the simulation of the Mark-II core and also the complete listing of the SAS3D input data
Availability note (English)
Available from INIS in electronic form
Files
Additional details
Publishing Information
- Imprint Pagination
- 61 p.
- Report number
- KFK-PSB--01.02.06P93A
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37002694
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; LOSS OF FLOW; SAFETY ANALYSIS; SNR REACTOR; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SODIUM COOLED REACTORS
Optional Information
- Notes
- Refs, tabs, figs
- Secondary number(s)
- INIS-DE-PSB--126