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Experiment data report for 1-1/2-loop semiscale system isothermal Test 1011

Description: Recorded test data are presented for Test 1011 of the isothermal portion of the Semiscale Blowdown and Emergency Core Cooling (ECC) Project. The data represent the results of a test in the isothermal test series in which a break nozzle area 80% that of other test configurations was used with no simulated ECC injection. The data, presented in the form of graphs in engineering units, have been analyzed only to the extent necessary to assure that they are reasonable and correct. Uninterpreted data from Test 1011 for use by others and for support of subsequent interpretive reports and analyses are presented. (auth)
Date: March 1, 1974
Creator: Alder, R.S.; Feldman, E.M. & Pinson, P.A.
Partner: UNT Libraries Government Documents Department

Experiment data report for 1-1/2-loop semiscale system isothermal Tests 1004 and 1006

Description: isothermal portion of the Semiscale Blowdown and Emergency Core Cooling (ECC) Project. These data represent the results of the first tests in the isothermal test series tn which simulated ECC injection during blowdown was inveatigated. The data, presented in the form of composite graphs in engineering units, have been analyzed only to the extent necessary to assure that they are reasonable and correct. The intent of this report is to make available the uninterpreted data from Tests 1004 and 1006 for use by others and for support of subsequent interpretative reports and analyses. (auth)
Date: March 1, 1974
Creator: Alder, R.S.; Feldman, E.M. & Pinson, P.A.
Partner: UNT Libraries Government Documents Department

Experiment data report for 1-1/2-loop semiscale system isothermal tests 1008 and 1010

Description: Recorded test data are presented for Tests 1008 and 1010 of the isothermal portion of the Semiscale Blowdown and Emergency Core Cooling (ECC) Project. These data represent the results of the first isothermal tests utilizing an enlarged downcomer gap (1.0 inch) in the pressure vessel to investigate general system hydraulic response both with and without simulated ECC injection. The data, presented in the form of composite graphs in engineering units, have been analyzed only to the extent necessary to assume that they are reasonable and correct. (auth)
Date: March 1, 1974
Creator: Alder, R.S.; Feldman, E.M. & Pinson, P.A.
Partner: UNT Libraries Government Documents Department

Experiment data report for Semiscale Mod-1 tests S-05-6 and S-05-7 (alternate ECC injection tests). [PWR]

Description: Recorded test data are presented for Tests S-05-6 and S-05-7 of the Semiscale Mod-1 alternate ECC injection test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Tests S-05-6 and S-05-7 were conducted from initial conditions of 2263 psia and 550/sup 0/F and 2253 psia and 551/sup 0/F, respectively, to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood transient following a simulated double-ended offset shear of the cold leg broken loop piping. The specific objective for these tests was to investigate the effectiveness of low pressure injection system (LPIS) coolant injection into the upper plenum when combined with cold leg intact loop injection.
Date: June 1, 1977
Creator: Feldman, E. M. & Sackett, K. E.
Partner: UNT Libraries Government Documents Department

Experiment data report for Semiscale Mod-1 Test S-05-2 (alternate ECC injection test)

Description: Recorded test data are presented for Test S-05-2 of the Semiscale Mod-1 alternate emergency core coolant (ECC) injection test series. This test is one of several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Test S-05-2 was conducted from an initial cold leg fluid temperature of 545/sup 0/F and an initial pressure of 2263 psia. A simulated double-ended offset shear cold leg break was used to investigate core and system response to a depressurization and reflood transient with ECC injection at the intact loop pump suction and broken loop cold leg. A reduced lower plenum volume was used for this test to more accurately represent the lower plenum of a PWR, based on system volume scaling. System flow was set to achieve a core fluid temperature differential of 65/sup 0/F at a core power level of 1.44 MW. The flow resistance of the intact loop was based on core area scaling. An electrically heated core with a slightly peaked radial power profile was used in the pressure vessel to simulate the predicted surface heat flux of nuclear fuel rods during a loss-of-coolant accident.
Date: February 1, 1977
Creator: Feldman, E. M.; Collins, B. L. & Sackett, K. E.
Partner: UNT Libraries Government Documents Department

Experiment data report for Semiscale Mod-1 Test S-05-1 (alternate ECC injection test)

Description: Recorded test data are presented for Test S-05-1 of the Semiscale Mod-1 alternate ECC injection test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Test S-05-1 was conducted from initial conditions of 2263 psia and 544/sup 0/F to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood transient following a simulated double-ended offset shear of the cold leg broken loop piping. During the test, cooling water was injected into the vessel lower plenum to simulate emergency core coolant injection in a PWR, with the flow rate based on system volume scaling.
Date: February 1, 1977
Creator: Feldman, E. M.; Patton, Jr., M. L. & Sackett, K. E.
Partner: UNT Libraries Government Documents Department

System to control contamination during retrieval of buried TRU waste

Description: Between 1950 and 1970 the Department of Energy`s Rocky Flats Plant generated transuranic (TRU) contaminated waste, which was buried at the Idaho National Engineering Laboratory. This waste must now be retrieved and sent to a permanent disposal site. During retrieval the main contaminates to be controlled are compounds of plutonium and americium. Since these substances are small sized, and extremely mobile, airborne concentrations must be kept to a minimum to effectively eliminate personnel uptake during retrieval operations. This report describes an invention that relates to a system to control contamination due to TRU airborne particles and was developed consisting of an outer containment building, an inner containment area, a dust suppression system including an electrostatic contaminate capture subsystem, a contamination control system including a moisture control subsystem, a rapid monitoring subsystem, and a lifting and moving system including recovery and repackaging subsystems, and a lifting and moving system including recovery and repackaging subsystems.
Date: December 31, 1991
Creator: Menkhaus, D. E.; Loomis, G. G.; Feldman, E. M.; Scott, D. W.; Mullen, C. K. & Meyer, L. C.
Partner: UNT Libraries Government Documents Department