A study on the jet pump characteristic curve in boiling water reactor
Description
The jet pump models of RELAP5/MOD2, RETRAN-02/MOD3, and RELAP4/MOD3 are compared. From the investigation of the momentum equations, it is found that the normal quadrant jet pump models of these codes are essentially the same. In this paper, it is found that the relationship between the flow ratio, M, and the heat ratio, N, is uniquely determined for a given jet pump geometry provided that the wall friction and gravitational head are neglected. In other words, under the given assumptions the M - N characteristic curve will not change with power level, recirculation pump speed and loop flow rate. The effect of the gravitational head on the M - N curve has been found to be significant for low flow conditions. As a result, a guideline has been given to the definition of the specific energy (or the head ratio). Sensitivity studies on the key parameters have been performed. It is found that the generic M - N curve should not be used for a jet pump which does not have the same nozzle to throat area ratio as that of the generic jet pump
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0585-9
- Imprint Title
- Proceedings of power plant transients---1990
- Imprint Pagination
- 128 p.
- Journal Page Range
- p. 81-88.
Conference
- Title
- American Society of Mechanical Engineers (ASME) winter annual meeting.
- Dates
- 25-30 Nov 1990.
- Place
- Dallas, TX (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24022616
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; COOLANT LOOPS; FLUID FLOW; M CODES; NOZZLES; PERFORMANCE TESTING; R CODES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SAFETY ANALYSIS
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901194--.