Results and analysis of a loss-of-feedwater induced ATWS experiment in the LOFT facility. [PWR]
Abstract
An anticipated transient without scram (ATWS), initiated by a loss of feedwater, was experimentally simulated in the Loss-of-Fluid Test (LOFT) pressurized water reactor (PWR). Primary system pressure was controlled using a two-position actuator relief valve to simulate a scaled power-operated relief valve (PORV) and safety relief valve (SRV) representative of those in a commercial PWR. Auxiliary feedwater injection was delayed during the experiment until the plant recovery phase where long-term shutdown was achieved by an operator-controlled plant recovery procedure without inserting the control rods. The system transient response predicted by the RELAP5/MOD1 computer code showed good agreement with the experimental data.
- Authors:
- Publication Date:
- Research Org.:
- EG and G Idaho, Inc., Idaho Falls (USA); Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
- OSTI Identifier:
- 5492521
- Report Number(s):
- EGG-M-07083; CONF-830702-26
ON: DE84000562
- DOE Contract Number:
- AC07-76ID01570
- Resource Type:
- Technical Report
- Resource Relation:
- Conference: 21. ASME/AIChE national heat transfer conference, Seattle, WA, USA, 24 Jul 1983; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ATWS; HEAT TRANSFER; HYDRAULICS; PWR TYPE REACTORS; COMPUTER CALCULATIONS; EXPERIMENTAL DATA; FEEDWATER; LOFT REACTOR; PRESSURE GRADIENTS; REACTOR SAFETY; STEAM SYSTEMS; TEMPERATURE GRADIENTS; THEORETICAL DATA; ACCIDENTS; DATA; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID MECHANICS; HYDROGEN COMPOUNDS; INFORMATION; MECHANICS; NUMERICAL DATA; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; TANK TYPE REACTORS; TEST REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
Citation Formats
Grush, W H, Woerth, S C, and Koizumi, Y. Results and analysis of a loss-of-feedwater induced ATWS experiment in the LOFT facility. [PWR]. United States: N. p., 1983.
Web.
Grush, W H, Woerth, S C, & Koizumi, Y. Results and analysis of a loss-of-feedwater induced ATWS experiment in the LOFT facility. [PWR]. United States.
Grush, W H, Woerth, S C, and Koizumi, Y. 1983.
"Results and analysis of a loss-of-feedwater induced ATWS experiment in the LOFT facility. [PWR]". United States.
@article{osti_5492521,
title = {Results and analysis of a loss-of-feedwater induced ATWS experiment in the LOFT facility. [PWR]},
author = {Grush, W H and Woerth, S C and Koizumi, Y},
abstractNote = {An anticipated transient without scram (ATWS), initiated by a loss of feedwater, was experimentally simulated in the Loss-of-Fluid Test (LOFT) pressurized water reactor (PWR). Primary system pressure was controlled using a two-position actuator relief valve to simulate a scaled power-operated relief valve (PORV) and safety relief valve (SRV) representative of those in a commercial PWR. Auxiliary feedwater injection was delayed during the experiment until the plant recovery phase where long-term shutdown was achieved by an operator-controlled plant recovery procedure without inserting the control rods. The system transient response predicted by the RELAP5/MOD1 computer code showed good agreement with the experimental data.},
doi = {},
url = {https://www.osti.gov/biblio/5492521},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Jan 01 00:00:00 EST 1983},
month = {Sat Jan 01 00:00:00 EST 1983}
}
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