A model for calculation of RCS pressure during reflux boiling under reduced inventory conditions and its assessment against PKL data. [Reactor Cooling Systems (RCS)]

Conference · Tue Jan 01 00:00:00 EST 1991

OSTI ID:7232887

Palmrose, D E ^[1]; Mandl, R M ^[2]

---

1. EG and G Idaho, Inc., Idaho Falls, ID (United States)
2. Siemens AG, Berlin (Germany)

There has been recent interest in the United States concerning the loss of residual heat removal system (RHRS) under reduced coolant inventory conditions for pressurized water reactors. This issue is also of interest in the Federal Republic of Germany and an experiment was performed in the integral PKL-HI experimental facility at Siemens-KWU to supply applicable data. Recently, an NRC-sponsored effort has been undertaken at the Idaho-National Engineering Laboratory to identify and analyze the important thermal-hydraulic phenomena in pressurized water reactors following the long term loss-of-RHRS during reduced inventory operation. The thermal-hydraulic response of a closed reactor coolant system during such a transient is investigated in this report. Some of the specific processes investigated include: reflux condensation in the steam generators, the corresponding pressure increase in the reactor coolant system, and void fraction distributions on the primary side of the system. Mathematical models of these and other physical processes Experiment B4.5.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 7232887
• Report Number(s): EGG-M-91413; CONF-911079-32; ON: DE92017898
• Resource Relation: Conference: 19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting, Bethesda, MD (United States), 28-30 Oct 1991
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
HEAT TRANSFER
HYDRAULICS
BOILING
MATHEMATICAL MODELS
PRESSURE DEPENDENCE
PRESSURE VESSELS
REACTOR SAFETY
STEAM GENERATORS
TEMPERATURE DEPENDENCE
BOILERS
CONTAINERS
COOLING SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MECHANICS
PHASE TRANSFORMATIONS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
SAFETY
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled