Study of thermal-hydraulic characteristics during decay heat removal in a pool-type fast breeder reactor

Journal Article · Wed Apr 01 04:00:00 EST 1992 · Nuclear Technology; (United States)

OSTI ID:5534620

Akutsu, M; Okabe, Y; Satoh, K ^[1]; Kamide, H; Hayashi, K ^[2]; Naohara, N ^[3]; Shibata, Y ^[4]

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1. Japan Atomic Power Co., 1-6-1 Ohte-machi, Chiyoda-ku, Tokyo 100 (JP)
2. Power Reactor and Nuclear Fuel Development Corp., O-arai Engineering Center, 4002 Narita-cho, O-arai-machi, Ibaraki 311-13 (JP)
3. Central Research Inst. of Electric Power Industry, 2-11-1 Iwatokita, Komae-shi, Tokyo 201 (JP)
4. Hitachi, Ltd., Hitachi Works, 3-1-1 Saiwai-cho, Hitachi-shi 317 (JP)

This paper reports that the thermal-hydraulic characteristics of a pool-type fast breeder reactor during decay heat removal are studied experimentally with a one-eighth-scaled three-dimensional reactor model using water as the working fluid. The model is designed to simulate reactor operations from full power to scram transient and decay heat removal conditions as well as two types of decay heat removal systems, a direct reactor auxiliary cooling system (DRACS) and a primary reactor auxiliary cooling system (PRACS). The transient thermal-hydraulic performance of the DRACS is compared with that of the PRACS for the water test results. The results are used to evaluate the accuracy of the multidimensional analysis codes AQUA and THERVIS. The analytical results are generally in good agreement with the measurements.

• OSTI ID: 5534620
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 98:1; ISSN 0029-5450; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
A CODES
ACCURACY
AFTER-HEAT REMOVAL
BREEDER REACTORS
COMPUTER CODES
COOLING SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
HYDROGEN COMPOUNDS
MATHEMATICAL MODELS
OPERATION
OXYGEN COMPOUNDS
POOL TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
REACTORS
REMOVAL
SCRAM
SHUTDOWN
SIMULATION
T CODES
TESTING
THERMODYNAMICS
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS