[en] General statements may be made on the behavior of single-component and multi-component aerosols in the Nuclear Safety Pilot Plant vessel. The removal processes for U₃O₈, Fe₂O₃, and U₃O₈ + Fe₂O₃ aerosols are enhanced in a steam-air atmosphere. Steam-air seems to have little effect on removal of concrete aerosol from the vessel atmosphere. A steam-air environment causes a change in aerosol shape from chain-agglomerate to basically spherical for U₃O₈, Fe₂O₃, and U₃O₈ + Fe₂O₃ aerosol; for concrete the change in aerosol shape is from chain-agglomerate to partially spherical. The mass ratio of the individual components of a multi-component aerosol seems to have an observable influence on the resultant behavior of these aerosols in steam. The enhanced rate of removal of the U₃O₈, the Fe₂O₃, and the mixed U₃O₈ + Fe₂O₃ aerosols from the atmosphere of the NSPP vessel by steam-air is probably caused by the change in aerosol shape and the condensation of steam on the aerosol surfaces combining to increase the effect of gravitational settling. The apparent lack of an effect by steam-air on the removal rate of concrete aerosol could result from a differing physical/chemical response of the surfaces of this aerosol to condensing steam

[en] The behavior of aerosols assumed to be characteristic of those generated during light water reactor (LWR) accident sequences and released into containment is being studied. Recent activities in the ORNL Aerosol Release and Transport Project include studies of (1) the thermal hydraulic conditions existing during Nuclear Safety Pilot Plant (NSPP) aerosol tests in steam-air environments, (2) the thermal output and aerosol mass generation rates for plasma torch aerosol generators, and (3) the influence of humidity on the shape of agglomerated aerosols of various materials. A new Aerosol-Moisture Interaction Test (AMIT) facility was prepared at the NSPP site to accommodate the aerosol shape studies; several tests with Fe₂O₃ aerosol have been conducted. In addition to the above activities a special study was conducted to determine the suitability of the technique of aerosol production by plasma torch under the operating conditions of future tests of the LWR Aerosol Containment Experiments (LACE) at the Hanford Engineering Development Laboratory. 3 refs., 2 figs., 7 tabs

[en] This data record report summarizes the results from five tests involving Fe₂O₃ test aerosol in a steam-air environment and one test in a dry air environment. This research sponsored by the US Nuclear Regulatory Commission was conducted in the Nuclear Safety Pilot Plant at the Oak Ridge National Laboratory. The purpose of this project is to provide a data base on the behavior of aerosols in containment under conditions assumed to occur in postulated LWR accident sequences; this data base will provide experimental validation of aerosol behavioral codes under development. In the report a brief description is given of each test together with the results in the form of tables and graphs. Included are data on aerosol mass concentration, aerosol fallout and plateout rates, total mass fallout and plateout, aerosol particle size, vessel atmosphere pressure, vessel atmosphere temperatures, temperature gradients near the vessel wall, and steam condensation rates on the vessel wall

[en] This report summarizes progress for the Aerosol Release and Transport Program sponsored by the Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Accident Evaluation, for the period April 1984 to September 1984. Topics discussed include (1) the experimental program in the Fuel Aerosol Simulant Test Facility, (2) NSPP experiments involving an aerosol of limestone-aggregate concrete in a steam-air atmosphere, (3) revisions in the NSPP experimental program, (4) experiments relating to NSPP thermohydraulic conditions, (5) aerosol-moisture interaction test plans, (6) aerosol code implementation activities, (7) improvements in data processing procedures for NSPP experiments, and (8) a study comparing in-vessel and ex-vessel cascade impactor aerosol size measurements in the NSPP

[en] This data record report summarizes the results from three tests involving mixed aerosols of uranium oxide and iron oxide in a steam-air environment and one test in a dry environment. This research, sponsored by the US Nuclear Regulatory Commission, was conducted in the Nuclear Safety Pilot Plant at the Oak Ridge National Laboratory. The purpose of this project is to provide a data base on the behavior of aerosols in containment under conditions assumed to occur in postulated LWR accident sequences;this data base will provide experimental validation of aerosol behavioral codes under development. In the report, a brief description is given of each test together with the results in the form of tables and graphs. Included are data on aerosol mass concentration, aerosol fallout and plateout rates, total mass fallout and plateout, aerosol particle size, vessel atmosphere pressure, vessel atmosphere temperatures, temperature gradients near the vessel wall, and steam condensation rates on the vessel wall

[en] Topics discussed include: (1) the experimental program in the Fuel Aerosol Simulant Test (FAST) Facility; (2) NSPP experiments involving mixtures of aerosols of iron oxide and uranium oxide in steam and dry atmospheres; (3) support work for the DEMONA (West Germany) and Marviken (Sweden) projects; (4) analysis of core-melt experiments involving boric oxide volatility; (5) initial operation of the new 250-kW induction generator; (6) comparisons of NAUA results with experiments; and (7) tests and improvements in the UVABUBL-II code

[en] This report summarizes progress for the Aerosol Release and Transport Program sponsored by the Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Accident Evaluation, for the period October 1985-March 1986. Topics discussed include (1) Aerosol-Moisture Interaction Test (AMIT) experiments 5002 through 5006; (2) efforts to measure the aerodynamic shape factor chi during these experiments; (3) a development test for determining parameters for generating concrete aerosols; (4) data concerning water-vapor generation during plasma torch operation; (5) the use of the ideal gas law in calculating relative humidity; (6) initial comparisons of CONTAIN code results with experimental data for an iron oxide aerosol-steam experiment in the NSPP Facility; (7) pretest predictions using the CONTAIN code for LACE experiment LA-2

[en] This data record report summaries the results from six tests involving U₃O₈ test aerosol in a steam-air environment and one test demonstrating the effect of condensing steam on an agglomerated U₃O₈ test aerosol. This research sponsored by the US Nuclear Regulatory Commission was conducted in the Nuclear Safety Pilot Plant at the Oak Ridge National Laboratory. The purpose of this project is to provide a data base on the behavior of aerosols in containment under conditions assumed to occur in postulated LWR accident sequences; this data base will provide experimental validation of aerosol behavioral codes under development. In the report a brief description is given of each test together with the results in the form of tables and graphs. Included are data on aerosol mass concentration, aerosol fallout and plateout rates, total mass fallout and plateout, aerosol particle size, vessel atmosphere pressure, vessel atmosphere temperatures, temperature gradients near the vessel wall, and steam condensation rates on the vessel wall

[en] This report summarizes progress for the Aerosol Release and Transport Program sponsored by the Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Accident Evaluation, for the period April 1985-September 1985. Topics discussed include (1) a steam-only test performed in the NSPP vessel; (2) development tests to study thermal input and generation efficiency; (3) Aerosol-Moisture Interaction Test (AMIT) preliminary and development tests to check various features of the AMIT facility; (4) data from the first two tests in the AMIT program; (5) an analysis of changes necessary in Andersen Mark-III impactor design for AMIT experiments; (6) the theory of capillary condensation on aerosols at nominally undersaturated humidity levels; (7) work in modifying data processing codes to accommodate data retrieval equipment changes; (8) correction of sample volume calculations for NSPP experiments on aerosols in steam-air environments; and (9) implementation and application of the CONTAIN code. 2 refs., 9 figs., 8 tabs

[en] This report summarizes progress for the Aerosol Release and Transport Program sponsored by the Nuclear Regulatory Commission's Office of Nuclear Regulatory Research, Division of Accident Evaluation, for the period January - March 1982. Topics discussed include (1) the source term experimental program in the Fuel Aerosol Simulant Facility; (2) Fe₂0₃ in steam (light-water reactor accident) aerosol experiments in the Nuclear Safety Pilot Plant (NSPP); (3) core-melt experiments in the Containment Research Installation-II Facility, including studies of the behavior of fission product simulant elements as well as control rod silver alloy components; and (4) analytical modeling of the moisture balance in steam experiments in the NSPP