New cooling system of the FRG-1 two barrier system of the primary coolant cycle
Creators
Description
The GKSS research center operates the swimming pool reactor FRG-1 with a thermal power of 5 MW as national neutron source for neutron scattering experiments and sample irradiation as well. Before changing the primary coolant cycle consisted of the reactor core and the closed piping including pumps, heat exchanger and delay tank. The closed cooling circuit was located underneath the reactor pool, in the so-called radioactive cellar. This piping system served secondary coolant system. Due to the location of the primary coolant cycle below the operation pool a postulated 2-F line break and simultaneous failure of the pool slide gate valve could lead to a falling dry of the total reactor core. the new primary coolant system was built in the beginning 2002 in a partitioned cell all within the radioactive cellar, so that the reactor core remains with water with the assumed incident. Due to the new two barrier-inclusion of the primary circuit only the melting of two fuel plates (from total 252 fuel plates) has to be taken into account. This measure and the core compactness in 2000 with a neutron flux gain of a factor of 2 makes the FRG-1 ready for the next 15 years of reactor operation. (author)
Files
36019470.pdf
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Additional details
Publishing Information
- Imprint Title
- IGORR 9: Proceedings of the 9. meeting of the International Group On Research Reactors
- Imprint Pagination
- 346 p.
- Journal Page Range
- [3 p.]
- Report number
- INIS-XA-C--030
Conference
- Title
- 9. meeting of the International Group On Research Reactors
- Acronym
- IGORR 9
- Dates
- 24-28 Mar 2003
- Place
- Sydney (Australia)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36019470
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLOSED-CYCLE COOLING SYSTEMS; FAILURES; FRG-1 REACTOR; FUEL PLATES; HEAT EXCHANGERS; NEUTRON FLUX; PRIMARY COOLANT CIRCUITS; PUMPS; REACTOR CORES; REACTOR OPERATION; REACTOR VESSELS; VALVES
- Descriptors DEC
- CONTAINERS; CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FUEL ELEMENTS; OPERATION; POOL TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 1 ref., 2 figs