RELAP/FRAP-T6 analysis of seized and sheared shaft accidents
Description
Argonne National Laboratory (ANL) performed audit calculations of a Reactor Coolant Pump (RCP) seized/sheared shaft transient for the Westinghouse Seabrook Plant using RELAP5/MOD 1.5 (Cycle 32) and FRAP-T6. The objective was to determine the effect of time of loss of offsite power and other single component failures on the peak clad temperature. The RCP shaft seizure event was modeled in RELAP5 by using the pump model shaft stop option. In modeling the sheared shaft failure, the faulted pump was replaced with a branch component having no flow losses. In general, the RELAP5-predicted system response for the seized shaft transient was very comparable to the results presented in the Seabrook FSAR, although the Reactor Coolant System (RCS) pressure response was somewhat different. The RELAP5 sheared-shaft analysis results were very similar to those for the seized shaft
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE84006470.Files
15072974.pdf
Files
(106.0 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:f44d6fb0c19031a039b7c0540b5136de
|
106.0 kB | Preview Download |
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- CONF-840614--17
Conference
- Title
- Annual meeting of the American Nuclear Society.
- Dates
- 3-8 Jun 1984.
- Place
- New Orleans, LA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15072974
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; FAILURES; HEAT TRANSFER; HYDRAULICS; HYDRODYNAMICS; PRIMARY COOLANT CIRCUITS; PUMPS; PWR TYPE REACTORS; REACTOR SAFETY
- Descriptors DEC
- COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLUID MECHANICS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS