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; ; Ohno, Shuji;
JNC TN9400 2000-092, 247 Pages, 2000/08
Small-scale sodium pool combustion tests Run-F7-3 and Run-F8-1 were performed to investigate the corrosion of floor liner under high moisture condition. ln the both tests, which were performed using the 3m FRAT-1 vessel at the SAPFIRE facility, the sodium of 507deg-C was leaked on the carbon steel catch pan about for 25 minutes with the flow rate of around 25 kg/h. The air in the vessel was ventilated with the flow rate of 5m/min containing the moisture of 25000-28000 vol.ppm. The duration of combustion was different in two tests by changing the starting time of argon gas injection into the vessel. As the results of post-test analysis such as observation of catch pan surface and chemical analysis of the deposits, it was confirmed that 'Na-Fe double oxidization type corrosion' was dominant in the both tests and that the catch pan and deposits were not under the condition leading to the occurrence of 'molten salt type corrosion.'
;
PNC TN9410 94-061, 126 Pages, 1994/02
The computer code TRACER has been developed to evaluate the species and quantities of fission products (FPs) released into the cover gas in an LMFBR during the fuel pin failure accidents (In-vessel source term). In this fiscal year, analytical models for the following key phenomena were developed and were coded in the code, which had been proposed from the results of sample calculations in last fiscal year. (a)Aerosol behavior in a bubble, (b)bubble behavior near the surface between cover gas and coolant, and (c)behavior of coolant temperature change. The fundamental functions of these models were validated by conducting sample calculations for the analyses of MOL7C/6 in-pile source term experiment and out-of-pile experiment for xenon-iodine mixed gas bubble behavior in liquid sodium. However, the calculational results by the above models could not reproduce the iodine decrease behavior within the bubble during the bubble rising in the out-of-pile experiment. Therefore, it is necessary to consider another mechanism in transport phenomena of iodine from the xenon-iodine mixed gas bubble into the sodium.
; ; Takahashi, Takeshi;
PNC TN8410 91-026, 27 Pages, 1991/02
High level liquid waste originates from the reprocessing of spent fuel. The high level liquid waste is mixed and melted with borosilicate glass in the melter. During melting, radio-active aerosol is generated from the melter off-gas. Power Reactor and Nuclear Fuel Development Corporation is developing a vitrification process. The off-gas treatment system has been improved to reduce the release of radionuclides from the vitrification process to the atmosphere.
; Ishida, Junichiro; Koizumi, Katsuzo; ; ; Nomura, Norio
PNC TN9080 91-002, 31 Pages, 1990/12
None
; Matsuki, Takuo*; Hiroi, Hiroshi*; Himeno, Yoshiaki
PNC TN9410 88-092, 82 Pages, 1988/08
Post-test calculations of the large-scale sodium leak demonstration test, Run-D2, were performed using the ASSCOPS code in order to validate the applicability of the code to the evaluation of the fire suppression function of the PNC-type smothering tank. In the analysis, radiation coefficients between aerosols in the gas phase and structures and a pool surface in the smothering tank defined in the code were varied as parameter. The following three cases were calculated. (a)No aerosols suspending was assumed in the gas phase and thus, 1.0 was used as the coefficient between the structures and the pool surface. (b)The coefficient between the aerosols and the pool surface was 0.65, and that between structures and the aerosols was 0.73. (c)The coefficient between the aerosols and the pool surface was the same as case (b) and 0.5 was used as that between structures and the aerosols. The comparison between analysis and experiment with regard to the temperature of the various parts showed that the agreement was within +30% and -20%. From these results, it was concluded that the code was available for the evaluation of the fire suppression function of the smothering tank.
Kawada, Koji*; ; Hiroi, Hiroshi*; Himeno, Yoshiaki
PNC TN9410 88-004, 44 Pages, 1988/01
Since sodium leak and fire researches have been performed at high-temperatures simulating an accident during the rated reactor operation knowledge of sodium leak and fire at low-temperatures which may happen at Ex-vessel Storage Tank or during the partial power operation of the reactor was very li,ited. Therefore, the present test was carried out to clarify the ignition temperatures and the temperature at which aerosol starts to release during sodium spray, column, and pool fires. Sodium spray and column tests were conducted at Sodiu Fire Test Rig (SOFT-1), while sodium pool test was carried out at Sodium Leak Fire and Aerosol Test Rig (SOLFA-1). The following test results were obtained from these tests. (1)Sodium Spray Test. The ignition temperature was 160C depending upon the droplet diameter of sprayed sodium. (2)Sodium Column Test. (a)Sodium main flow did not ignite, while the scattered sodium droplets ignited. (b)The ignition temperature of the main flow rebounded on a pan was 180C. (c)The ignition temperature of deposits on a pan was 160 C. (3)Sodium Pool Test. (a)The ignition temperature of the static pool ranged from 280 to 315C. (b)Temperature at which aerosol starts to release was determined to be 140 to 160C by visual in spection. (c)After extinguished artificially by closing a lid, sodium reignited at temperatures higher than 80 C when the lid was reopend.
Morii, Tadashi*; *; *
PNC TN9410 86-124, 61 Pages, 1986/12
On Sept. 27, 1985, a large scale sodium spray fire test (RUN-E1) has been conducted in an air atmosphere using the SOLFA-2 test vessel (100m made from SUS) of the SAPFIRE facility. The major test conditions are as follows. (Spray Rate : 510 g/sec) (Spray Period : 1800 sec) (Spray Inlet Temperature : 505 C) (Spray Falling Height : 4 m) As a sodium spray started, the gas pressure and temperature rose rapidly and reached to the maximum values 1.24kg/cm-g and 700C, respectively, after about 1.2 minutes. The oxygen in the test vessel was consumed completely after 4 minutes. From oxygen consumption rate during this time, burning rate of sodium was calculated to be 160g-Na/sec that was equivalent to about 30% of the sodium spray rate (under the assumption of 100% NaO production). Many thermo-couples installed in a spray corn region have been failed due to their exposure to the high temperature above 1000 C, which suggested the existence of a burning zone around the sodium droplets. No remarkable distribution of oxygen concentration was observed in the vertical direction of the vessel during a spray, indicating that the gas within the vessel was well mixed by natural convection due to gas temperature difference between the outside and the inside of a spray corn. Aerosol concentratian has reached the maximum value of 17.5g-Na/m after 5 min and decreased below 1 g-Na/m after 20 min.
*;
Nihon Genshiryoku Gakkai-Shi, 28(8), p.701 - 709, 1986/00
Times Cited Count:1 Percentile:20.71(Nuclear Science & Technology)no abstracts in English
Kanamori, Masashi; Ebana, Minoru*; Seki, Akio
PNC TN841 83-48, 84 Pages, 1983/07
no abstracts in English
Murakami, Hiroyuki*; Kanamori, Masashi; Nakamoto, Athushi*; Seki, Akio
PNC TN841 81-57, 19 Pages, 1981/10
no abstracts in English