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Title: Ice-condenser aerosol tests

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.
Authors:
; ;  [1]
  1. (Pacific Northwest Lab., Richland, WA (United States))
Publication Date:
OSTI Identifier:
6018916
Report Number(s):
NUREG/CR-5768; PNL--7765
ON: TI92000595
DOE Contract Number:
AC06-76RL01830
Resource Type:
Technical Report
Research Org:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications; Pacific Northwest Lab., Richland, WA (United States)
Sponsoring Org:
NRC; Nuclear Regulatory Commission, Washington, DC (United States)
Country of Publication:
United States
Language:
English
Subject:
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