Thermohydraulic model experiments on the transition from forced to natural circulation for pool-type fast reactors

Journal Article · Tue Sep 01 00:00:00 EDT 1992 · Nuclear Technology; (United States)

OSTI ID:7147038

Hoffmann, H; Marten, K; Weinberg, D ^[1]

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1. Kernforschungszentrum Karlsruhe GmbH (Germany)

In this paper, thermohydraulic studies on the transition from forced to natural convection are carried out using the 1:20 scale RAMONA three-dimensional reactor model with water as the simulant fluid. In the investigations, a scram from 40% load operation of a fast reactor is simulated. The core mass flows and the core as well as the hot plenum temperatures are measured as a function of time for various core power levels, coastdown curves of the primary- and secondary-side pumps, and for various delay times for the start of the immersion coolers after a scram. These parameters influence the onset of the natural circulation in the reactor tank. The main result is that the longer the intermediate heat exchanger coolability is ensured and the later the immersion coolers start to operate, the higher is the natural-circulation flow and, hence, the lower are the core temperatures.

• OSTI ID: 7147038
• Journal Information: Nuclear Technology; (United States), Vol. 99:3; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
42 ENGINEERING
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
FAST REACTORS
NATURAL CONVECTION
POOL TYPE REACTORS
MASS TRANSFER
R CODES
REACTOR CORES
SCRAM
SIMULATION
TEMPERATURE MEASUREMENT
WATER
COMPUTER CODES
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
HEAT TRANSFER
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTOR SHUTDOWN
REACTORS
SHUTDOWN
WATER COOLED REACTORS
WATER MODERATED REACTORS
220100* - Nuclear Reactor Technology- Theory & Calculation
420400 - Engineering- Heat Transfer & Fluid Flow
990200 - Mathematics & Computers