Impact of nonabsorbing control rod tips on kinetics feedback for BWR turbine trip without bypass RETRAN-03 analyses
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5805635
- Pennsylvania State Univ., University Park (United States)
RETRAN-03 studies were performed for the boiling water reactor (BWR) turbine trip without bypass (TTWOB) event to investigate how the non-neutron-absorbing material on control rod tips affect scram delay timing and reactivity feedback. Scram delay, Doppler temperature, and moderator void (density) feedback were varied to assess their relative impact on kinetics behavior. Although a generic point-kinetics RETRAN-03 TTWOB model 2 was employed, actual plant information was used to develop the basic and parametric cases.
- OSTI ID:
- 5805635
- Report Number(s):
- CONF-930601-; CODEN: TANSAO
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Vol. 68; Conference: American Nuclear Society (ANS) annual meeting, San Diego, CA (United States), 20-24 Jun 1993; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
Similar Records
Peach Bottom BWR Turbine Trip Benchmark Analyses with RETRAN-3D and CORETRAN
Investigation of BWR (boiling water reactor) instability phenomena using RETRAN-03
Validation of RETRAN-03 by simulating a peach bottom turbine trip and boiloff at the full integral simulation test facility
Journal Article
·
Fri Oct 15 00:00:00 EDT 2004
· Nuclear Science and Engineering
·
OSTI ID:5805635
Investigation of BWR (boiling water reactor) instability phenomena using RETRAN-03
Conference
·
Wed Nov 01 00:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5805635
Validation of RETRAN-03 by simulating a peach bottom turbine trip and boiloff at the full integral simulation test facility
Journal Article
·
Sun Nov 01 00:00:00 EST 1992
· Nuclear Technology; (United States)
·
OSTI ID:5805635
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
SAFETY ANALYSIS
CONTROL ELEMENTS
COMPUTERIZED SIMULATION
PERSONAL COMPUTERS
R CODES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
COMPUTER CODES
COMPUTERS
DIGITAL COMPUTERS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
MICROCOMPUTERS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
SAFETY
SIMULATION
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
220900 - Nuclear Reactor Technology- Reactor Safety
22 GENERAL STUDIES OF NUCLEAR REACTORS
BWR TYPE REACTORS
SAFETY ANALYSIS
CONTROL ELEMENTS
COMPUTERIZED SIMULATION
PERSONAL COMPUTERS
R CODES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
COMPUTER CODES
COMPUTERS
DIGITAL COMPUTERS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
MICROCOMPUTERS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
SAFETY
SIMULATION
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
220900 - Nuclear Reactor Technology- Reactor Safety