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Kawata, Koji; Matsuki, Takuo*; Miyahara, Shinya
JAEA-Review 2011-046, 42 Pages, 2012/02
JAEA-Review-2011-046.pdf:2.41MB
Sodium spray fire tests at an initial sodium temperature of 250
C were conducted under the atmospheric conditions of air and 3% oxygen containing nitrogen to determine both the sodium burning rate and the aerosol release fraction.
Kawada, Koji; Matsuki, Takuo*; Miyahara, Shinya
JNC TN9400 2005-043, 48 Pages, 2005/08
JNC-TN9400-2005-043.pdf:1.37MB
Sodium spray fire tests at the initial sodium temperature of 250 deg-C were conducted under the atmospheric conditions of air and 3% oxygen containing nitrogen to determine the sodium burning rate and the aerosol release fraction and compare them with the test results at the initial sodium temperature of 500 deg-C in air atmosphere.In the tests, sodium was supplied using a commercial spray nozzle into a stainless steel vessel of 100 m
volume (SOLFA-2). The sodium burning rate was calculated from two independent methods : the consumption rate of oxygen in the vessel and the enthalpy change of vessel components during the test. The aerosol release fraction was determined from the comparison between the measured aerosol concentrations and the calculated ones by the ABC-INTG code. The main conclusions were as follows, (1) In air atmosphere, (a) sodium droplets ignited instantaneously and the spray fire was observed, (b) the sodium burning rate was about 440 g-Na/s and the fraction of supplied sodium was about 70%. (2) In 3% oxygen containing nitrogen, (a) ignition of sodium droplets was not observed, and (b) the sodium burning rate was about 44 g-Na/s and the fraction of supplied sodium was less than 10%.
Toyohara, Daisuke*; Ohno, Shuji; Matsuki, Takuo*; Hamada, Hirotsugu; Miyahara, Shinya
JNC TN9520 2004-004, 151 Pages, 2005/01
JNC-TN9520-2004-004.pdf:139.32MB
A computer code TRACER (Transport Phenomena of Radionuclides for Accident Consequence Evaluation of Reactor) version 2.3 has been developed to evaluate the species and the quantities of fission products (FPs) released into cover gas during fuel pin failure accident in an LMFBR. TRACER version 2.3 includes new and modified models shown below. a) Booth model, a new model for FPs release from fuel. b) Modified model for FPs transfer from fuel to bubble or sodium coolant. c) Modified model for bubbles dynamics in coolant. Computer models, input data and output data of TRACER Version 2.3 are described in this user's manual.
Ohno, Shuji; Matsuki, Takuo*
Saikuru Kiko Giho, (11), p.93 - 104, 2001/06
None
Ohno, Shuji; Matsuki, Takuo*
JNC TN9400 2000-106, 132 Pages, 2000/12
Sodium fire analyses were performed on 7 kinds of sodium leak tests using a computer code ASSCOPS which has been developed to evaluate thermal consequences of sodium leak accident in an FBR plant. By the comparison between the calculated and the test results of gas pressure, gas temperature, sodium catch pan temperature, wall temperature, and of oxygen concentration, it was confirmed that the ASSCOPS code and the parameters used in the analysis give valid or conservative results on thermal consequences of sodium leak and fire.
Ohno, Shuji; Matsuki, Takuo*; ; Miyake, Osamu
JNC TN9520 2000-001, 196 Pages, 2000/01
JNC-TN9520-2000-001.pdf:5.13MB
ASSCOPS (Analysis of Simultaneous Sodium Combustion in Pool and Spray) has been developed for analyses of thermal consequences of sodium leak and fire accidents in LMFBRs. This report presents a description of the computational models, input and output data as the user's manual of ASSCOPS version 2.1. ASSCOPS is an integrated computational code based on the sodium pool fire code SOFIRE II developed by the Atomics International Division of Rockwell International, and on the sodium spray fire code SPRAY developed by the Hanford Engineering Development Laboratory in the U.S. The users of ASSCOPS need to specify the sodium leak conditions (leak flow rate and temperature, etc.), the cell geometries (cell volume, surface area and thickness of structures, etc.), and the atmospheric initial conditions such as gas temperature, pressure, and composition. ASSCOPS calculates the time histories of atmospheric temperature, pressure and of structural temperature.
Hamada, Hirotsugu; *; Matsuki, Takuo*
PNC TN9410 90-089, 150 Pages, 1990/05
A computer code SWACS (Sodium-Water Reaction Analysis Code System) was developed to analyze the pressure/fluid-flow phenomena during a large scale sodium-water reaction accident. Since the code was closely related with the prototype Monju SGs (steam generators) having a cover-gas space at their top, it didn't possess sufficient analytical functions for the specific phenomane of noncover-gas type SGs. In order to improve the accuracy of propagated pressure calculations and to make the code applicable to noncover-gas type SGs, some modifications related to new analytical models of pressure relief system, such as a dynamic response model of in-sodium RD (rupture disk) and a fluid-flow model in the piping connected to dump thak, were added to the calculation module of initial pressure spike and its propagation. The new version was named SWAC 57R. This report includes the results of analyses to verify the code functions and expermental validation to confirm code applicability to noncover-gas type SGs. The verification indicated the qualitative effects of calculation parameters (R
, R
, t-t, GAR, GVE) and the importance of dynamic fracture process of the RD as a moving variable orifice. The experimental validation using test date from PEPT series II showed that SWAC57R could accurately calculate propagated pressure (+20% at RD and +10% at IHX for the peak of pressure) by using property parameters (R = 0, R = 1, t-t = 0.004, GAR = 0.8, GVE = 0.5) Since the magnitude of the errors are comparable to that in the analysis of cover-gas type SGs conducted previously, it is concluded that the code can also be applied to noncover-gas type SGs.
Matsuki, Takuo*; ; *; Himeno, Yoshiaki
PNC TN9520 88-020, 179 Pages, 1988/09
In an LMFBR, the consequences of a sodium spill in the heat transport system need to be determined. Snalyses of sodium fires in such accidents have been performed in use of various computer codes. At PNC, two computer codes, SPRAY-III M and SOFIRE-M II, had been utilized separately for the spray fire and for the pool fire, respectively. To provide the combined spray-pool fire calculation, ASSCOPS (Analysis of Simultaneous Sodium COmbustions in pool and Spray), which is described in this report, has been developed as an integrated code of those codes for the computation of the pressure and temperature. This report consists of descriptions of the input and output formats and the Job control procedures of ASSCOPS Ver.1.1 H.
; 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.
Hiroi, Hiroshi*; Matsuki, Takuo*; Miyake, Osamu; *; Himeno, Yoshiaki
PNC TN9410 88-078, 105 Pages, 1988/07
Following the study in JFY86, parametric calculations of a sodium leak accident in the plant were conducted using the CONTAIN code. This is to clarify influences of the design conditions and assumptions of the accident and to study characteristics of the "hot cell" concept and the "confinement united with the building" system. In addition, a model of heat transfer from bare pipes and components was incorporated into the code. The major conclusions are as follows: (1)Incorporation of the model of heat transfer from bare pipes to the cell atmosphere reduced the release of fission products (FP) to 20
30% of that obtained in the previous calculations in JFY86. (2)The most influential parameter on the FP release was the leak rates of cell to the confinement or the atmosphere. (3)Location of sodium leak, oxygen concentration in the cell, and capacity of the normal off-gas system scarcely affected the FP release. (4)The FP release in all calculational cases were far below the target values which are assumed for a site evaluation of a large FBR.
