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JAEA Reports

JOYO MK-II core plant characteristics test data

JNC TN9410 2000-010, 72 Pages, 2000/03

JNC-TN9410-2000-010.pdf:2.14MB

The experimental fast reactor JOYO served as the MK-II irradiation bed core for testing fuel and material for FBR development for 16 years from 1982 to 1997. During the MK-II core operation, extensive data were accumulated from the plant characteristic tests. Tests conducted at JOYO included operating characteristic tests for confirming operational safety, performance tests for confirming design performance of the MK-II core, and special tests for research and development ofthe plant. In this report, the outline and the results of each test item are shown. These test data can be provided by the magnet-optical disk.

JAEA Reports

None

;

PNC TN2410 95-035, 53 Pages, 1995/05

PNC-TN2410-95-035.pdf:4.98MB

None

JAEA Reports

Crossflow between interconnected subchannels in a multiple channel 3.Effect of pressure differential between subchannels on flow redistribution process

*; *; *

PNC TJ9614 94-001, 59 Pages, 1994/03

PNC-TJ9614-94-001.pdf:1.34MB

Crossflow of a two-phase mixture between vertical subchannels is subdivided into three components in the literature; turbulent mixing, void drift and diversion crossflow. Of these, turbulent mixing alone occurs in an equiliblium flow, in which flow rates of both phases in each subchannel do not change in the axial direction. In a general non-equilibrium flow, however, all three components occur simultaneously. In this report, effect of pressure differential between subchannels on flow redistribution process along the channel axis has been studied experimentally. In the experiment, a multiple channel, consisting of two identical circular subchannels of 16 mm I.D., were used as a test channel. And, air and water were introduced unevenly into the two subchannels at the inlet to get several non-equilibrium flows with and without the pressure differential between subchannels. For each flow, we have obtained the axial distributions data of pressure differential between the subchannels, the air and water flow rates, the void fractions, and the tracer concentrations for both phases when gas and liquid tracers were injected into one of the two subchannels. From these experimental data, we have estimated lateral velocities of the air and water corresponding to each crossflow component, and analyzed the effect of the pressure differential on the lateral velocities.

JAEA Reports

In-vessel thermohydraulic analysis of MONJU with AQUA code (II) set-up of standard analytical models for MONJU and pre-analysis of natural circulation phenomena

Muramatsu, Toshiharu

PNC TN9410 90-095, 236 Pages, 1990/07

PNC-TN9410-90-095.pdf:7.81MB

Three and two dimensional standard analytical models were to analyze in-vessel thermohydraulic phenomena of prototype fast reactor MONJU using multi-dimensional thermohydraulic analysis code AQUA. The non-structured cells, which are defined as those without solid structure inside the cell, count up tp 23270 and 2004, respectively. Pre-analysis of in-vessel natural circulation phenomena was conducted for transient simulating a pump coast down and reactor scram to a full-power operation condition (End of 10th equilibrium cycle) with the above standard models. From the analyses, the following results have been obtained: (1)Calculated flow distribution in the core on a steady-state condition agreed within the maximum error 10% and 20% compared with a design value for 3D and 2D analytical models, respectively. (2)Rising speed of thermal stratification interface predicted by the 2D analytical model was delayed for the case using the 3D model. (3)In the result using the 3D analytical model, a maximum temperature at center of a fuel pin clad not exceeded the limit value 675$$^{circ}$$C.

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