A study on effective system depressurization during a PWR vessel bottom break LOCA with HPI failure and gas inflow prevention. ROSA-V/LSTF test SB-PV-05
Creators
- 1. Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan)
Description
A small break loss-of-coolant accident (SBLOCA) experiment was conducted at the Large Scale Test Facility (LSTF) of ROSA-V program to study effects of accident management (AM) measures on core cooling, which are important in case of total failure of high pressure injection (HPI) system during an SBLOCA at a pressurized water reactor (PWR). The LSTF is a full-height and 1/48 volume-scaled facility simulating a 4-loop Westinghouse-type PWR (3423 MWt). The experiment, SB-PV-05, simulated a PWR vessel bottom SBLOCA with a rupture of nine instrument tubes, which is equivalent to 0.18% cold leg break. It is clarified that AM actions with steam generator (SG) depressurization to achieve a primary loop cooling rate at -55 K/h and auxiliary feedwater supply for 30 minutes are effective to avoid core uncovery by actuating the low pressure injection (LPI) system. It is also shown through the comparison with the previous experiment of SB-PV-03 that prevention of non-condensable gas inflow from the accumulator injection system (AIS) is very important to actuate the LPI to achieve adequate core cooling. This report presents experiment results of SB-PV-05 in detail and shows the effects of gas inflow prevention on core cooling through the estimation of primary coolant mass and energy balance in the primary system. (author)
Availability note (English)
Available from JAEA; DOI: https://doi.org/10.11484/jaea-research-2006-072
Files
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 155 p.
- Report number
- JAEA-Research--2006-072
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 38054877
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AUXILIARY WATER SYSTEMS; DEPRESSURIZATION; FEEDWATER; HEAT TRANSFER; HIGH PRESSURE COOLANT INJECTION; LOSS OF COOLANT; MASS BALANCE; PRESSURE VESSELS; PWR TYPE REACTORS; RUPTURES; STEAM GENERATORS; THERMAL HYDRAULICS; TUBES
- Descriptors DEC
- ACCIDENTS; AUXILIARY SYSTEMS; BOILERS; CONTAINERS; ECCS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 12 refs., 58 figs., 19 tabs.