Transient two-phase performance of LOFT reactor coolant pumps
Description
Performance characteristics of Loss-of-Fluid Test (LOFT) reactor coolant pumps under transient two-phase flow conditions were obtained based on the analysis of two large and small break loss-of-coolant experiments conducted at the LOFT facility. Emphasis is placed on the evaluation of the transient two-phase flow effects on the LOFT reactor coolant pump performance during the first quadrant operation. The measured pump characteristics are presented as functions of pump void fraction which was determined based on the measured density. The calculated pump characteristics such as pump head, torque (or hydraulic torque), and efficiency are also determined as functions of pump void fractions. The importance of accurate modeling of the reactor coolant pump performance under two-phase conditions is addressed. The analytical pump model, currently used in most reactor analysis codes to predict transient two-phase pump behavior, is assessed
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE84005123.Files
15046438.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- CONF-831111--16
Conference
- Title
- ASME winter annual meeting.
- Dates
- 13-18 Nov 1983.
- Place
- Boston, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15046438
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LOFT REACTOR; PERFORMANCE; PUMPS; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- EQUIPMENT; FLUID FLOW; PWR TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS