Published 1975
| Version v1
Report
Restricted
Model tests for the emergency cooling system of the prototype reactor SNR 300
Description
The accident considered is a pipe rupture of the pump pressure pipe coupled with a failure of the pump shutdown system. The emergency cooling concept is based upon natural convection inside the tank generated by heat added in the core and a heat sink consisting of immersion coolers attached to the inside of the tank. This cooling circuit within the tank is covered by a computer program (NOTUNG) drafted by the Interatom company for a theoretical model describing the thermodynamic behavior of the circuit. Model tests to support the analytical calculations are outlined. Comparison between calculation and experiment was made. (auth)
Availability note (English)
MF available from INIS under the Report Number.
Files
System files
(249.7 kB)
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Additional details
Publishing Information
- Imprint Pagination
- 214 p.
- Report number
- EURFNR--1200
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7228574
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; DATA; ECCS; NATURAL CONVECTION; PERFORMANCE TESTING; SNR REACTOR
- Descriptors DEC
- BREEDER REACTORS; CONVECTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT TRANSFER; INFORMATION; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; SODIUM COOLED REACTORS; TESTING
Optional Information
- Notes
- Translation of KFK--1895 Work performed under United States--Euratom Fast Reactor Exchange Program.