Ice-condenser aerosol tests

Technical Report · Sun Sep 01 00:00:00 EDT 1991

DOI:https://doi.org/10.2172/6018916· OSTI ID:6018916

Ligotke, M W; Eschbach, E J; Winegardner, W K ^[1]

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1. Pacific Northwest Lab., Richland, WA (United States)

This report presents the results of an experimental investigation of aerosol particle transport and capture using a full-scale height and reduced-scale cross section test facility based on the design of the ice compartment of a pressurized water reactor (PWR) ice-condenser containment system. Results of 38 tests included thermal-hydraulic as well as aerosol particle data. Particle retention in the test section was greatly influenced by thermal-hydraulic and aerosol test parameters. Test-average decontamination factor (DF) ranged between 1.0 and 36 (retentions between {approximately}0 and 97.2%). The measured test-average particle retentions for tests without and with ice and steam ranged between DF = 1.0 and 2.2 and DF = 2.4 and 36, respectively. In order to apparent importance, parameters that caused particle retention in the test section in the presence of ice were steam mole fraction (SMF), noncondensible gas flow rate (residence time), particle solubility, and inlet particle size. Ice-basket section noncondensible flows greater than 0.1 m{sup 3}/s resulted in stable thermal stratification whereas flows less than 0.1 m{sup 3}/s resulted in thermal behavior termed meandering with frequent temperature crossovers between flow channels. 10 refs., 66 figs., 16 tabs.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Regulatory Applications; Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6018916
• Report Number(s): NUREG/CR-5768; PNL-7765; ON: TI92000595
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
ICE CONDENSERS
PERFORMANCE TESTING
PWR TYPE REACTORS
CONTAINMENT SYSTEMS
AEROSOLS
CONTAINMENT
DECONTAMINATION
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
I CODES
PARTICLE SIZE
PARTICULATES
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
RUPTURES
STEAM
TEMPERATURE MEASUREMENT
TEST FACILITIES
ACCIDENTS
CLEANING
COLLOIDS
COMPUTER CODES
CONDENSERS
COOLING SYSTEMS
DISPERSIONS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
MECHANICS
PARTICLES
POWER REACTORS
REACTOR COMPONENTS
REACTORS
SAFETY
SIZE
SOLS
STEAM CONDENSERS
TESTING
THERMAL REACTORS
VAPOR CONDENSERS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220900 - Nuclear Reactor Technology- Reactor Safety