Reliability evaluation of simulation models for nearfield groundwater flow and radionuclide transport computation

*; *; *; *

JNC TJ8400 2000-006, 232 Pages, 2000/05

JNC-TJ8400-2000-006.pdf:7.75MB

In this research, simulations with some parameters which characterize ground water flow and the reliability evaluation for the expansion of the calculation method of groundwater flow were carried out by using the radionuclide transport computations in nearfield heterogeneous porous media. Concretely contents are follows: (1)With the series of calculation method for three-dimensional saturated/unsaturated groundwater flow and one-dimensional radionuclide transport. the computational analyses with the parameters used in JNC report in 2000 was carried out and the influence of the different input flux was evaluated. (2)The examination of the application for the different ways of inverse laplace transformation which is used in one-dimensional radionuclide tansport analysis code "MATRICS" was carried out. (3)The examination of the application of multi-element "MATRICS" (m-MATRICS) for radionuclide transport computations in nearfield heterogeneous porous media was carried out. (4)The series of calculation methods from three-dimensional saturated/unsaturated ground water flow simulation code to one-dimensional radionuclide transport simulation code was integrated.

Development of cross-flow type mercury target, 1; Hydraulic analyses and fabrication of verification model

Terada, Atsuhiko*; Kaminaga, Masanori; Kinoshita, Hidetaka; Hino, Ryutaro; *; *

JAERI-Tech 99-073, p.42 - 0, 1999/11

JAERI-Tech-99-073.pdf:1.67MB

no abstracts in English

Experimental study on coolant flow distribution in a fuel element of a helium-cooled particle-bed burner reactor

Haga, Katsuhiro; Hino, Ryutaro; Sudo, Yukio; Takizuka, Takakazu; Mukaiyama, Takehiko; Ogawa, Toru

Proc. of Int. Conf. on Future Nuclear Systems (Global'97), 2, p.1291 - 1294, 1997/00

no abstracts in English

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.

Test apparatus for ITER blanket cooling water distributor design

Yoshida, Hiroshi; Enoeda, Mikio; Hirata, Shingo*; Ito, H.*

JAERI-M 92-070, 45 Pages, 1992/05

JAERI-M-92-070.pdf:1.34MB

no abstracts in English

Experimental test results of multi-channel test rig of T test section, V; Channel blockage test result on HTTR fuel column

Hino, Ryutaro; Takase, Kazuyuki;

JAERI-M 90-163, 45 Pages, 1990/09

JAERI-M-90-163.pdf:1.16MB

no abstracts in English

Experimental test results of multi-channel test rig of T test section, III; Test results in helium gas conditions heated to 1000C

Hino, Ryutaro; Takase, Kazuyuki; Maruyama, So;

JAERI-M 90-033, 37 Pages, 1990/03

JAERI-M-90-033.pdf:0.96MB

no abstracts in English

Experimental studies on thermal and hydraulic performance of fuel stack of VHTR, V; Test results of HENDEL multi-channel test rig when helium gas was heated up to 1000C

Hino, Ryutaro; Maruyama, So; Takase, Kazuyuki; ; Shimomura, Hiroaki

Nihon Genshiryoku Gakkai-Shi, 31(4), p.470 - 476, 1989/04

https://doi.org/10.3327/jaesj.31.470

no abstracts in English

Hydraulics of a coolant flow through a control rod channel in the very high temperature gas cooled reactor

Ogawa, Masuro; Akino, Norio; ; ; ; Emori, Kouichi; Ouchi, Mitsuo; ;

Journal of Nuclear Science and Technology, 24(1), p.75 - 83, 1987/01

https://doi.org/10.3327/jnst.24.75

no abstracts in English

TRANTHAC-1:Transient Thermal-Hydraulic Analysis Code for HTGR Core of Multi-Channel Model

;

JAERI-M 8972, 71 Pages, 1980/08

JAERI-M-8972.pdf:1.76MB

no abstracts in English