Simulation of the Winfrith SGHWR X-trip blowdown experiment using RELAP-UK Mk IV and RETRAN-UK. Final report
Description
The paper describes calculations with the thermal hydraulics codes RELAP-UK Mk IV and RETRAN to model the behavior of the Winfrith Steam Generating Heavy Water Reactor (WSGHWR) during a controlled depressurization experiment. The results of the simulations are compared with each other and with the experimental data. In the X-trip experiment a reactor trip was initiated from a steady operating condition of 90% of full power and the reactor allowed to depressurize via steam dump lines from the steam drums. During the transient data from a variety of instruments measuring coolant parameters, such as pressures, flows and temperatures, and plant state such as valve positions, were recorded. The version of RETRAN employed in the calculations was a development version of RETRAN-UK with the addition of a number of features from RELAP-UK, including Bryce slip and the Holmes drift flux model. The first 100 seconds of the X-trip transient in one of the two reactor loops has been simulated, during which time the system pressure falls from 940 to 170 psia
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A07/MF A01 as DE82901330.
Files
Additional details
Publishing Information
- Imprint Pagination
- 138 p.
- Report number
- EPRI-NP--2140
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13680209
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; DEPRESSURIZATION; HEAT TRANSFER; HYDRAULICS; PERFORMANCE; PRESSURE GRADIENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; SGHWR REACTOR; STEAM
- Descriptors DEC
- COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS