Simulation of sodium pumps for nuclear power plants. Technical report 1 Oct 80-1 May 81

Technical Report · Fri May 01 00:00:00 EDT 1981

DOI:https://doi.org/10.2172/5370933· OSTI ID:5370933

Boadu, H O

A single-phase pump model for analysis of transients in sodium cooled fast breeder nuclear power plants has been presented, where homologous characteristic curves are used to predict the behavior of the pump during operating transients. The pump model has been incorporated into BRENDA and FFTF; two system cases to simulate Clinch River Breeder Reactor Plant (CRBRP) and the Fast Flux Test Facility (FFTF) respectively. Two simulation test results for BRENDA which is one loop representation of a three loop plant have been presented. They are: (1) Primary pump coastdown to natural circulation coupled with scram failure, and (2) 10 percent deviation of primary speed with plant controllers incorporated.

• Research Organization: Arizona Univ., Tucson (USA). Dept. of Nuclear Engineering
• OSTI ID: 5370933
• Report Number(s): NUREG/CR-2188; TRN: 82-011628
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLINCH RIVER BREEDER REACTOR
PUMPS
FFTF REACTOR
COMPUTERIZED SIMULATION
MATHEMATICAL MODELS
NUCLEAR POWER PLANTS
PERFORMANCE
REACTOR SAFETY
SODIUM
TRANSIENTS
ALKALI METALS
BREEDER REACTORS
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
NUCLEAR FACILITIES
POWER PLANTS
POWER REACTORS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SIMULATION
SODIUM COOLED REACTORS
TEST REACTORS
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding