Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Large containment-scale vessel at EPRI with controlled injection and monitoring of surrogate fission product aerosols in steam/air environments Test Identification: ACE Phase B tests SA-Related Topics / Phenomena:Iodine behavior and retention within containment under reactor accident conditions. 4 intermediate scale tests investigate the effects of radiation, pH, surfaces and initial iodine speciation on iodine behavior. Measured Parameters: T, p, r.h., steam, aerosol concentration, size distribution and iodine Modelling: RTF facility is a replaceable, cylindrical main vessel, in which a Co-60 radiation source (2 kGy/h) can be placed. The main vessel can be partially filled with water with chemical additives. Electrical heaters on the outer surface of the main vessel The heaters can maintain temperature at max 80 oC. Iodine feed can contain a small amount (370 MBq) of I-131 for gamma-counting techniques. A spray header is included inside the main vessel. The water pool and the gas space can be mixed with separate recirculation loops. The inner surface of the main vessel was Keeler & Long self-priming epoxy-amine paint in three tests and stainless steel in one test. Simulation Code: MELCOR, MAAP, COCOSYS, ASTEC Experimental Research Program: ACE, ACEX Link to PIRT: WP-1.5 ST-24, ST-26, ST-42, ST-46, ST-47, ST-48
References: [1] Kupferschmidt W.C.H., Ball J.M., Buttazoni J.B., Evans G.J., Jobe D.J., Melnyk A.J., Palson A.S., Portman R., Sanipelli G.G., ""Final report on the ACE/RTF experiments, ACE-TR-B3, AECL Whiteshell Laboratories, Manitoba, Canada, July 1992. [2] Beahm E.C., Brown M.L., Shockley W.E, ""Adsorption of iodine on aerosols"", ACE-TR-B5, ORNL/M-1079, Oak Ridge National Laboratory, Oak Ridge TN, USA, December 1990.
[3] Alleman R.T., McCormack J.D., Dickinson D.R., Ritzman R.L., ""Results of Large Scale Iodine Experiment at the Containment Systems Test Facility"", ACE Phase B report TR-B10, May 1992.
[4] Ritzman R.L. ""An assessment of the current data base on iodine behavior in containment during severe accidents"". ACE-TR-B26. EPRI, Palo Alto CA, USA. December 1992. (ILin comment: provides a good review on iodine chemistry data base in view of reactor safety -worth revisiting in light of present SAM and new reactor designs"")
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Large containment-scale vessel at EPRI with controlled injection and monitoring of surrogate fission product aerosols in steam/air environments Test Identification: ACE L1 SA-Related Topics / Phenomena: n/a Measured Parameters: T, p, r.h., steam, aerosol concentration, size distribution and iodine Modelling: Test with partially oxidized PWR core melt (mass 212 kg, with 70% of Zr oxidised) and limestone-common sand (LCS) concrete with rebar (amount 8.8·10-2 g/cm3 of concrete). Initial powders included 9.8 kg of Zr-metal and fission products. Initial powders included 13.4 kg of Zr-metal and fission product species Ba, La, Sr, Ce,Mo as oxides, SnTe and ZrTe2. Simulation Code: MELCOR, MAAP, COCOSYS, ASTEC Experimental Research Program: ACE, ACEX Link to PIRT: WP-1.5 ST-6
References: [1] Thompson D.K. , Fink J.K., ""ACE MCCI Test L1 Posttest Operations Information Package"", ACE TR-C11, Argonne National Laboratory, May 1989.
[2] Thompson D.H. and Fink J.K., ""AVE MCCI Test L1, Test Data Report Thermal Hydraulics"", ACE TR-C14 Vol I, Argonne national Laboratory, January 1990.
[3] Fink J.K., ""ACE MCCI Test L1 Test Data Report , Volume 2, Aerosol Analysis"", ACE TR-C14 vol II, Argonne National Laboratory, March 1990.
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Large containment-scale vessel at EPRI with controlled injection and monitoring of surrogate fission product aerosols in steam/air environments Test Identification: ACE L2 SA-Related Topics / Phenomena: n/a Measured Parameters: T, p, r.h., steam, aerosol concentration, size distribution and iodine Modelling: Test with partially oxidized PWR core melt (mass 300 kg, with 70% of Zr oxidised) and siliceous concrete (comparable to German BETA test concrete) with rebar (amount 8.8·10-2 g/cm3 of concrete). Initial powders included 13.4 kg of Zr-metal and fission product species Ba, La, Sr, Ce,Mo as oxides and SnTe. The total mass fraction of FP material was 1.4 wt-%. Simulation Code: MELCOR, MAAP, COCOSYS, ASTEC Experimental Research Program: ACE, ACEX Link to PIRT: WP-1.5 ST-6
Hydrogen was measured in the off-gas indicating oxidation of Zr in the early heatup-phase of corium powders. Concrete ablation period was 46 min. Ablation started at concrete temp. The aerosol measurement line filters were plugged by SiO2/Si-aggromerates containing K,Te,Sn,S,Na, Fe after 41 min. Splattering from the melt surface was observed. The fission product released fractions ranged from 3E-5 (La) to 0.59 (Te). The ablation depth of concrete was 12.7 cm at the end of test.
References: [1] Thompson D.H., Fink J.K., ""Post-Test Operations Information Package"", ACE-TR-C8, Argonne National Laboratory, March 1989.
[2] Fink J.K., ""Test Data Report, Volume II - Aerosol Analysis, ACE-TR-C10, vol II, Argonne National Laboratory, November 1989.
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Large containment-scale vessel at EPRI with controlled injection and monitoring of surrogate fission product aerosols in steam/air environments Test Identification: ACE L4 SA-Related Topics / Phenomena: n/a Measured Parameters: T, p, r.h., steam, aerosol concentration, size distribution and iodine Modelling: Simulant melt was partially oxidised (Zr 50% oxidised) BWR corium, mass 300 kg. Tellurium was present as ZrTe2 within the Zircaloy-4 inserts. The other fission product species contained in the corium powders were Ba, La, Ce, Mo, all as oxides. All metal and B4C was placed in inserts on top of the concrete slab. The concrete slab was 2-layered Soviet type concrete: serpentine layer (5.1-cm deep) on top of ordinary structural concrete. SS rebar mass in the concrete slab was 2.6 kg. Simulation Code: MELCOR, MAAP, COCOSYS, ASTEC Experimental Research Program: ACE, ACEX Link to PIRT: WP-1.5 ST-6
Concrete ablation period was 128 min (when test target erosion of 12.7 cm was reached). Fision product releases were low, highest release fraction was for Te (0.6). The release of Ba, Mo and Sr was of the order 1E-3, the release fraction of Ce, La and U was less than 1E-4. The release fractions of concrete aerosols and boron was higher - of the order of 1E-1.
References: [1] Thompson D.H, Fink J.K., ""ACE MCCI Test L4 Posttest Operations Information Package"", ACE TR-C20, Argonne National Laboratory, November 1990.
[2] Thompson D.H., Fink J.K., ""ACE MCCI Test L4 Test Data Report Volume I - Thermal Hydraulics"", ACETR-C30 Vol I, Argonne National Laboratory, October 1991.
[3] Fink J.K., Thompson D.H., ""ACE MCCI Test L4 Test Data Report Volume II - Aerosol Analysis, Argonne National Laboratory, February 1992.
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Large containment-scale vessel at EPRI with controlled injection and monitoring of surrogate fission product aerosols in steam/air environments Test Identification: ACE L5 SA-Related Topics / Phenomena: n/a Measured Parameters: T, p, r.h., steam, aerosol concentration, size distribution and iodine Modelling: Test concrete slab composition corresponds to limestone-common sand (LCS) concrete used in Zion PWR. Core melt is fully oxidised:UO2-ZrO2-Fe2O3-NiO-Cr2O3-BaO-SrO-La2O3- CeO2 with total mass 293.1 kg. The concrete was limestone-common sand (LCS) with rebar (amount 8.8·10-2 g/cm3 of concrete). Simulation Code: MELCOR, MAAP, COCOSYS, ASTEC Experimental Research Program: ACE, ACEX Link to PIRT: WP-1.5 ST-6
The fission product releases of BaO, CeO, La2O3, SrO and UO2 ranged from 8.0E-3 to 2.4E-2 percent of the inventory. The ablation period was 121 min. Ablation started at concrete temp. 1673 K.
References: [1] Thompson D.H., Fink J.K., ""ACE MCCI Test L5, Post-Test Operations Information Package"", ACE-TR-C5, Argonne National Laboratory, October 1988.
[2] Thompson D.H., Fink J.K., ""ACE MCCI Test L5 Test Data Report"", ACE-TR-C7, Argonne National Laboratory, November 1988.
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Large containment-scale vessel at EPRI with controlled injection and monitoring of surrogate fission product aerosols in steam/air environments Test Identification: ACE L6 SA-Related Topics / Phenomena: n/a Measured Parameters: T, p, r.h., steam, aerosol concentration, size distribution and iodine Modelling: Test concrete slab composition corresponds to siliceous concrete used in BETA facility at Karlsruhe Nuclear Research Center with rebar. Core melt was partially oxidized PWR corium with 30% Zr oxidised (300 kg), including control rod materials. All metals were intially present in concrete/metal inserts located on top of the concrete basemat. The mass fractions of metals were: Zr+Zircaloy-4 (7.6 %), Type 304 SS+Ag+In (3.5%), FPs: Ba,La,Sr,Ce,Mo, as oxides (4.7%) and ZrTe2 (0.2%) and Ru (0.38%). Total mass of metal was 34 kg. Simulation Code: MELCOR, MAAP, COCOSYS, ASTEC Experimental Research Program: ACE, ACEX Link to PIRT: WP-1.5 ST-6
The ablation period was 41 minutes. Termination criterion was reaching ablation depth of 12.7 cm. Te, Ag and In release fractions were of the order 1E-1, Ba, Mo, Sr release fraction was of the order 1.E-3, Ru, La, Ce release fractions were between 2E-3 and 6E-6.
References: [1] Thompson D.H., Fink J.K., ""ACE MCCI Test L6, Posttest Operations Information Package"", ACE TR-C15, Argonne National Laboratory, July 1990.
[2] Thompson D.H., Fink J.K., ""ACE MCCI Test L6, Test Data Report Volume I, Thermal Hydraulics"", ACE TR-C26 Vol. I, Argonne National Laboratory, August 1991.
[3] Fink J.K., Thompson D.H., "" ACE MCCI Test L6. Test Data Report, Volume II, Aerosol Analysis"", ACE-TR-C26 Vol. II, Argonne National Laboratory, November 1991.
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Large containment-scale vessel at EPRI with controlled injection and monitoring of surrogate fission product aerosols in steam/air environments Test Identification: ACE L7 SA-Related Topics / Phenomena: n/a Measured Parameters: T, p, r.h., steam, aerosol concentration, size distribution and iodine Modelling: The core melt material represented partially (70% of Zr) oxidised BWR corium. The corium mass was 300 kg. The concrete basemat was limestone-common sand (LCS) type with similar fission product and core structural material inserts as for the Test L4. The test L7 had no rebar in the concrete. Simulation Code: MELCOR, MAAP, COCOSYS, ASTEC Link to PIRT: WP-1.5 ST-6
The concrete ablation time in L7 lasted 30 min during whcih time concrete eroded 3 cm. During the melting phase of the corium inserts significant foaming of the melt was oberserved that continued during the ablation phase. Foamed melt plugged the aerosol measurement lines. Eventually the whole off gas line with filters was plugged by aerosols (mainly from concrete and control rod material: SiO2 and B2O3) with the result that off-gass entered the test apparatus enlosure and the test was terminted before reaching the normal ablation criterion. The release fraction of fission product simulants were low, less than 2.8E-3. Te release was 0.23.
References: [1] Thompson D.H., Fink J.K., "" ACE MCCI Test L7 Posttest Information Package"", ACE TR-C22, Argonne National Laboratory, March 1991.
[2] Thompson D.H., Fink J.K., ""ACE MCCI Test L7 Test Data Report Volume I - Thermal Hydraulics, ACE-TR-C31 vol I, Argonne National Laboratory, November 1991.
[3] Fink J.K., Thompson D.H. ""ACE MCCI Test L7 Test Data Report Volume II - Aerosol Analysis, ACE-TR-C31 Vol. II, Argonne National Laboratory, February 1992.
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Large containment-scale vessel at EPRI with controlled injection and monitoring of surrogate fission product aerosols in steam/air environments Test Identification: ACE L8 SA-Related Topics / Phenomena: n/a Measured Parameters: T, p, r.h., steam, aerosol concentration, size distribution and iodine Modelling: Core melt of L8 was partially (70% of Zr) oxidised PWR corium. The concrete basemat was of limestone aggregate-limestone sand concrete. Fission product simulants in the test were BaO, La2O3, SrO, CeO2, MoO2 and ZrTe2, Ag and In were control rod materials and small amount of additional concrete constituents CaO and SiO2. CaO and SiO2 to embed metal (Zr,Zry-4 and ZrTe2) with oxidic material to preclude immediate oxidation of metal during the melt generation phase. Simulation Code: MELCOR, MAAP, COCOSYS, ASTEC Link to PIRT: WP-1.5 ST-6
The ablation started when core melt temperature exceeded 2500 K. The L-L concrete has gas content of 40% of mass. The maximum ablation rate was 5 mm/s and the peak superficial gas velocity was ca. 50 cm/s. The FP releases were highest of all ACE phase C tests. Release of Ag, In and Te were near 1. However, the release fractions of Ba, Sr and Mo were low, of the order of 1E-2, and the release fractions of U, Zr, Ce and La even lower, of the order of 1E-4.
References: [1] Thompson D.H., Fink J.K., ""ACE MCCI Test L8 Posttest Operations Information Package, ACE-TR-C25, Argonne National Laboratory, July 1991.
[2] Thompson D.H., Fink J.K., ""ACE MCCI Test L8 Test Data Report Volume I - Thermal Hydraulics, ACE-TR-C32 vol I, Argonne National Laboratory, December 1991.
[3] Fink J.K., Thompson D.H. ""ACE MCCI Test L8 Test Data Report Volume II - Aerosol Analysis, ACE-TR-C32 Vol. II, Argonne National Laboratory, June 1992.
References: [1] Thompson D.H., Fink J.K., ""Advanced Containment Experiments, System Design and Operations Description"", ACE TR-C3, Argonne National Laboratory, , October 1988.
[2] Thompson D.H., Fink J.K., Spencer B. W., ""Investigation of Molten Corium Concrete Interaction Phenomena and Aerosol Release in Small and Intermediate-Scale Tests, ACE-TR-C1, Argonne National Laboratory, December 1987.
[3] Thompson D.H., Farmer M.T., Fink J.K., Armstrong D.R., Spencer B.W., ""ACE Phase C Final Report: Volume I - MCCI Thermalhydraulic Results"", ACE TR-C42 Vol I, Argonne National Laboratory, September 1997.
[4] Fink J.K. Thompson D.H., ""ACE Phase C Final Report: MCCI Aerosol Results"", ACE TR-C42 vol II, Argonne National Laboratory, March 1997.
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Both, piping system connected to an 852 m3 volume used variously to simulate an auxiliary building or a reactor containment building Test Identification: LACE: LA-1 SA-Related Topics / Phenomena:The LA-1 test was performed to demonstrate aerosol behavior during simulated containment bypass accident conditions (V-sequence) in a PWR. CSTF used to simulate an auxiliary or safeguards building in which rupture of the interface piping was postulated to occur. The test auxiliary building was vented to the atmosphere through a scrubber. Measured Parameters: T, p, steam, aerosol concentration and depositon in containment and pipes Modelling: The test pipe representing the interface piping was 63-mm inside diameter, 30-m long and contained a total of six (6) 90° bends. At the test pipe inlet, there was a 1.5-m long and 300-mm diameter horizontal pipe section attached for the aerosol characterization measurements. The open-ended outlet nozzle terminated in a horizontal orientation within the auxiliary building. In the test the aux building atmosphere was brought to a 50/50 mixture of steam and air at 115 °C. Aerosol fed with gas 50/50 air and nitrogen, the pipe inlet pressure was 2 atm and the pipe outlet was at 1 atm. The aerosol feed lasted 60 min and the pipe was isolated and cooldown-phase of approximately 1 day began. The injected aerosol was CsOH (soluble) and MnO (in-soluble). Aerosol concentration, particle size and deposition rate and the T/H conditions were measured throughout the 2-day test. Simulation Code: MELCOR, ASTEC, AC2 Experimental Research Program: LACE Link to PIRT: WP-1.5 ST-12, ST-30, ST-55
LA-1 data was used for benchmark calulations of the simulation codes: AEROSIM-M, RETAIN-2C, TRAP-MELT2, AUX2.9
References: [1] G.R. Bloom, Aerosol behavior under LWR containment bypass conditions, Results of LACE test LA1, Report LACE TR-005, March 1990, Westinghouse Hanford Company, Richland, Washington 99352, USA.
[2] Albiol T. J., McCormack J. D., Muhlestein L. D., ""Instrumentation and measurement techniques used in the LACE program"", LACE TR-006, July 1987.
[3] Wright A.L., Arwood P.C., Wilson J.H., ""Summary of Posttest Aerosol Code Comparisons for LWR Aerosol Containment Experiment (LACE) LA1"", LACE-TR22 (ORNL/M-365), October 1987, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, USA.
[4] LACE TR-014, ""Analysis of samples from LA1 (SEM/EDAX, XRF, XRD)""
[5] LACE TR-0040, ""Chemical and phase analysis of solid samples from LA1""
[6] J. Jokiniemi (1990) Effect of Selected Binary and Mixed Solutions on Steam Condensation and Aerosol Behavior in Containment, Aerosol Science and Technology, 12:4, 891-902, DOI: 10.1080/02786829008959401. IP/Copyright Situation: signatories to LACE consortium
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Both, piping system connected to an 852 m3 volume used variously to simulate an auxiliary building or a reactor containment building Test Identification: LACE: LA-2 test (HEDL) SA-Related Topics / Phenomena:Test facility CSTF as for LA-1 but purposed to study situation of failure to isolate containment Measured Parameters: T, p, steam, aerosol concentration and depositon in containment and pipes Modelling: aerosol behaviour in free volume, pipes, deposition and leackage Simulation Code: MELCOR, ASTEC, AC2 Experimental Research Program: LACE Link to PIRT: WP-1.5 ST-12, ST-30, ST-55
References: [1] Hilliard R.K., Muhlestein L.D. Albiol T.J., ""Final report of Experimental results of LACE test LA2 - Failure to isolate containment"", LACE TR-007, June 1987.
[2] Wilson J. H., Arwood P. C., ""Summary of posttest aerosol code-comparison results for LWR aerosol containemtn experiment (LACE) LA2"", LACE TR-009, September 1988, Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA. IP/Copyright Situation: signatories to LACE consortium
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Both, piping system connected to an 852 m3 volume used variously to simulate an auxiliary building or a reactor containment building Test Identification: LACE: LA-3 test (HEDL) SA-Related Topics / Phenomena:Test facility CSTF as for LA-1 but purposed to study situation of containment bypass through piping (withpout aux building) Measured Parameters: T, p, steam, aerosol concentration and depositon in containment and pipes Modelling: aerosol behaviour in free volume, pipes, deposition and leackage Simulation Code: MELCOR, ASTEC, AC2 Experimental Research Program: LACE Link to PIRT: WP-1.5 ST-12, ST-30
References: [1] Dickinson S. R., Hilliard R. K., Muhlestein L. D., Mecham D. C., Carraro G., ""Aerosol behavior in LWR containment bypass piping - results of LACE test LA 3"", LACE TR-011, July 1987.
[2] Wright A. L., Arwood P. C., ""Summary of posttest aerosol code-comparison results for LWR aerosol containment experiment (LACE) LA3"", LACE TR-011, June 1988.
[3] LACE TR-041, ""Analysis of samples from LA3""
[4] LACE TR-058, "" Analysis of solid samples from LA3"" IP/Copyright Situation: signatories to LACE consortium
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Both, piping system connected to an 852 m3 volume used variously to simulate an auxiliary building or a reactor containment building Test Identification: LACE: LA-4 test (HEDL) SA-Related Topics / Phenomena:Test facility CSTF as for LA-1 but purposed to study situation of late containment failure with overlapping aerosol injection periods Measured Parameters: T, p, steam, aerosol concentration and depositon in containment and pipes Modelling: aerosol behaviour in free volume, pipes, deposition and leackage Simulation Code: MELCOR, ASTEC, AC2 Experimental Research Program: LACE Link to PIRT: WP-1.5 ST-12, ST-30, ST-55
References: [1] McCormack J. D., Hilliard R. K., Salgado J. M., ""Final Report of experimantal results of LACE test LA4 - Late containment failure with overplapping aerosol injection periods"", LACE-TR-025, October 1987.
[2] Slaughterbeck D., ""Pre- and post-test thermal-hydraulic comparisons of LACE test LA4"", LACE TR-027, March 1988. IP/Copyright Situation: signatories to LACE consortium
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Both, piping system connected to an 852 m3 volume used variously to simulate an auxiliary building or a reactor containment building Test Identification: LACE: LA-5 test (HEDL) SA-Related Topics / Phenomena:Test facility CSTF as for LA-1 but purposed to study situation of rapid containment depressurization with spiked pool Measured Parameters: T, p, steam, aerosol concentration and depositon in containment and pipes Modelling: aerosol behaviour in free volume, pipes, deposition and leackage Simulation Code: MELCOR, ASTEC, AC2, GOTHIC Experimental Research Program: LACE Link to PIRT: WP-1.5 ST-12, ST-30, ST-35, ST-55
References: [1] Dickinson S. R., Mecham D. C., Slaughterbeck D. C., ""Results of LACE tests LA5 and LA6 - Rapid containment depressurization"", LACE TR-026, September 1988.
[2] Wright A. L., Wislon J. H., Arwood P. C., ""Summary of posttest aerosol code-comparison results for LWR aerosol containment experiment (LACE) LA6"" , LACE TR-068, ORNL, Tennessee, USA, March 1989.
[3] Rahn F. J., ""The LWR Aerosol Containment Experiments (LACE) Project Summary Report, Final Report"" , LACE TR-012, EPRI, California, USA, November 1988. IP/Copyright Situation: signatories to LACE consortium
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Facility Description: Both, piping system connected to an 852 m3 volume used variously to simulate an auxiliary building or a reactor containment building Test Identification: LACE: LA6-test (HEDL) SA-Related Topics / Phenomena:Test facility CSTF as for LA-1 but purposed to study situation of rapid containment depressurization with aerosol injection Measured Parameters: T, p, steam, aerosol concentration and depositon in containment and pipes Modelling: aerosol behaviour in free volume, pipes, deposition and leackage Simulation Code: MELCOR, ASTEC, AC2, GOTHIC Experimental Research Program: LACE Link to PIRT: WP-1.5 ST-12, ST-30, ST-35, ST-55
References: [1] Dickinson S. R., Mecham D. C., Slaughterbeck D. C., ""Results of LACE tests LA5 and LA6 - Rapid containment depressurization"", LACE TR-026, September 1988.
[2] Wright A. L., Wislon J. H., Arwood P. C., ""Summary of posttest aerosol code-comparison results for LWR aerosol containment experiment (LACE) LA6"" , LACE TR-068, ORNL, Tennessee, USA, March 1989.
[3] Rahn F. J., ""The LWR Aerosol Containment Experiments (LACE) Project Summary Report, Final Report"" , LACE TR-012, EPRI, California, USA, November 1988. IP/Copyright Situation: partially published
Organization / Localization: Hanford Engineering Development Laboratory (HEDL) Country: USA Facility Description: Large containment-scale vessel at EPRI with controlled injection and monitoring of surrogate fission product aerosols in steam/air environments Facility Status: Closed Test Identification: ACE Phase A SA-Related Topics / Phenomena:Particulate FP retention by FCVS Experimental Research Program: ACE Link to PIRT: WP-1.5 ST-55
References: [1] M. Merilo, I.B. Wall “Containment Filtration Systems Tests, Summary Report” Electric Power Research Institute, ACE Phase A, TR-A22, February 1992
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