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JAEA Reports

Development of MIG2DF Version 2

Takai, Shizuka; Kimura, Hideo*; Uchikoshi, Emiko*; Munakata, Masahiro; Takeda, Seiji

JAEA-Data/Code 2020-007, 174 Pages, 2020/09

JAEA-Data-Code-2020-007.pdf:4.23MB

The MIG2DF computer code is a computer program that simulates groundwater flow and radionuclide transport in porous media for the safety assessment of radioactive waste disposal. The original version of MIG2DF was released in 1992. The original code employs a two-dimensional (vertical or horizontal cross-section, or an axisymmetric configuration) finite-element method to approximate the governing equations for density-dependent saturated-unsaturated groundwater flow and radionuclide transport. Meanwhile, for geological disposal of radioactive wastes, landscape evolution such as uplift and erosion needs to be assessed as a long-term geological and climate events, considering site conditions. In coastal areas, the impact to groundwater flow by change of salinity distribution to sea level change also needs to be considered. To deal with these events in the assessment, we have revised the original version of MIG2DF and developed the external program which enables MIG2DF to consider unsteady landscape evolution. In these developments, this report describes an upgrade of MIG2DF (Version 2) and presents the configuration, equations, methods, and verification. This reports also give the explanation external programs of MIG2DF: PASS-TRAC (the particle tracking code), PASS-PRE (the code for dataset preparation), and PASS-POST (the post-processing visualization system).

Journal Articles

Improvement of accuracy and stability in numerically solving hyperbolic equations by IDO (Interpolated Differential Operator) scheme with Runge-Kutta time integration

Yoshida, Hiroshi*; Aoki, Takayuki*; Utsumi, Takayuki*

Denshi Joho Tsushin Gakkai Rombunshi, A, 86(3), p.223 - 231, 2003/03

no abstracts in English

Journal Articles

3-D analysis of tritium and chloride transport in sandy aquifer

Takeda, Seiji; Kimura, Hideo

KURRI-KR-53, p.14 - 17, 2000/09

no abstracts in English

JAEA Reports

Development and validation of Multi-DimensionaI sodium combustion analysis code AQUA-SF

Takata, Takashi; Yamaguchi, Akira

JNC-TN9400 2000-065, 152 Pages, 2000/06

JNC-TN9400-2000-065.pdf:6.26MB
JNC-TN9400-2000-065(errata).pdf:0.12MB

ln the liquid metal fast reactor (LMFR) using liquid sodium as a coolant, it is important to evaluate the effect of the sodium combustion on the structure, etc. Most of the previous analytical works are based on a zone model, in which the principal variables are treated as volume-average quantities. Therefore spatial distribution of gas and structure temperatures, chemical species concentration are neglected. Therefore, a multi-dimensional sodium combustion analysis code AQUA-SF (Advanced simulation using Quadratic Upstream differencing Algorithm - Sodium Fire version) has been developed for the purpose of analyzing the sodium combustion phenomenon considering the multi-dimensional effect. This code is based on a multi-dimensional thermal hydraulics code AQUA that employs SIMPLEST-ANL method. Sodium combustion models are coupled with AQUA; one is a liquid droplet model for spray combustion, and the other is a flame sheet model for pool combustion. A gas radiation model is added for radiation heat transfer. Some other models necessary for the sodium combustion analysis, such as a chemical species transfer, a compressibility, are also added. ln AQUA-SF code, bounded QUICK method in space scheme and bounded three-point implicit method in time scheme are implemented. Verification analyses of sodium combustion tests shown in the following have been carried out. (1)pool combustion test (RUN-D1) (2)spray combustion test (RUN-E1) (3)sodium leakage combustion test (Sodium Fire Test-II) (4)smaII-scale leakage combustion test (RUN,F7-1) ln each verification analysis, good agreements are obtained and the validity of AQUA-SF code is confirmed.

Journal Articles

Estimation of $$^{222}$$Rn flux from ground surface based on the variation analysis of $$^{222}$$Rn concentration in a closed chamber

Koarashi, Jun*; Amano, Hikaru; Atarashi-Andoh, Mariko; Iida, Takao*

Radiation Protection Dosimetry, 87(2), p.121 - 131, 2000/01

 Times Cited Count:19 Percentile:22.42(Environmental Sciences)

no abstracts in English

JAEA Reports

None

Oyamada, Kiyoshi*

JNC-TJ1440 99-001, 82 Pages, 1999/03

JNC-TJ1440-99-001.pdf:2.52MB

no abstracts in English

JAEA Reports

Three-dimensional thermofluid computer code CELVA-3D to evaluate the safety of hypothetical explosion in fuel reprocessing plants (Contract research)

Nishio, Gunji*; *; Kono, Koji*; *; Murazaki, Minoru*

JAERI-Data/Code 98-033, 235 Pages, 1998/11

JAERI-Data-Code-98-033.pdf:9.87MB

no abstracts in English

JAEA Reports

None

Takase, Hiroyasu*; IMPEY*; EINCHCO*; *

PNC-TJ1281 96-003, 163 Pages, 1996/03

PNC-TJ1281-96-003.pdf:6.76MB

None

JAEA Reports

None

Takase, Hiroyasu*; IMPEY*; EINCHCO*; *

PNC-TJ1281 96-001, 158 Pages, 1996/03

PNC-TJ1281-96-001.pdf:10.72MB

None

JAEA Reports

None

Aoki, Kenji*; Hibiya, Keisuke*; Shiogama, Yukihiro*; Toida, Masaru*; Fukazawa, E.*; Okutsu, Kazuo*; *

PNC-TJ1100 95-002, 195 Pages, 1995/03

PNC-TJ1100-95-002.pdf:16.41MB

None

JAEA Reports

None

*; *; *; Iida, Takao*; *; *

PNC-TJ1545 94-003, 39 Pages, 1994/03

PNC-TJ1545-94-003.pdf:1.02MB

no abstracts in English

JAEA Reports

Integration study (V) for performance assessment system of geological disposal

Yanagisawa, Ichiro*; Fusaeda, Shigeki*; Uzawa, Masayuki*; Kasai, Masao*; Ishihara, Yoshinao*; Ikeda, Yasuhiro*; Ezaki, Masahiro*

PNC-TJ1214 94-007, 92 Pages, 1994/03

PNC-TJ1214-94-007.pdf:2.71MB

no abstracts in English

JAEA Reports

Integration study (V) for performance assessment system of geological disposal

Yanagisawa, Ichiro*; Fusaeda, Shigeki*; Uzawa, Masayuki*; Kasai, Masao*; Ishihara, Yoshinao*; Ikeda, Yasuhiro*; Ezaki, Masahiro*

PNC-TJ1214 94-006, 542 Pages, 1994/03

PNC-TJ1214-94-006.pdf:12.82MB

None

JAEA Reports

None

*

PNC-TJ1604 93-003, 46 Pages, 1993/03

PNC-TJ1604-93-003.pdf:1.84MB

no abstracts in English

JAEA Reports

Radionuclide transfer onto ground surface in surface water flow, 1; Disturbed loamy soil

Mukai, Masayuki; Takebe, Shinichi; Komiya, Tomokazu; Kamiyama, Hideo

JAERI-M 91-100, 17 Pages, 1991/07

JAERI-M-91-100.pdf:0.69MB

no abstracts in English

Journal Articles

Numerical analysis of transient behavior of molten metals heated by electron beam

; Yokokawa, Mitsuo; Seki, Masahiro; Arisawa, Takashi

Heat Transfer in High Energy/High Heat Flux Applications, p.43 - 49, 1989/00

no abstracts in English

Journal Articles

Effects of entrance configuration on pressure loss and heat transfer of transitional gas flow in a circular tube

Ogawa, Masuro;

Nippon Kikai Gakkai Rombunshu, B, 52(477), p.2164 - 2169, 1986/00

no abstracts in English

Oral presentation

A Study on the water purification mechanism in the mill tailings pond in Ningyo-toge Environmental Engineering Center

Masunaga, Kosuke; Tokoro, Chiharu*; Ohara, Yoshiyuki

no journal, , 

In Ningyo-toge Environmental Engineering Center, water level of mill tailings pond is planned to be lowered to reduce overflow risks caused by heavy rain etc., as a part of remediation activities of the Uranium Mine. It is known that the concentration of Fe and As and other elements in the mine drainage are decreased by retaining in the pond. The aims of this study are to reduce the load of water treatment facility and to determine the efficient countermeasure method for remediation of the mill tailings pond. To accomplish these, purification mechanisms of Fe and As in the pond were investigated, referring other studies. Chemical composition of water drainage in the pond was estimated by the chemical equilibrium analysis with advection using PHREEQC. The result of the simulation was almost reproducible for Fe. For As, it was reproducible when taking into account of surface complexation to ferrihydrite in sediment in the bottom of the pond.

Oral presentation

Modeling of solutes transport at the Horonobe URL, 2; Characterization of solutes transport in fractures based on data from in-situ tracer tests

Ono, Hirokazu; Takeda, Masaki; Ishii, Eiichi; Tachi, Yukio

no journal, , 

It is necessary to clarify the mass transport behavior in a deep underground natural barrier, for improving the reliability of safety assessment of high-level radioactive waste disposal. This study reports an analysis using data from in situ tracer tests for fractures in mudstone at Horonobe Underground Research Laboratory (URL).

19 (Records 1-19 displayed on this page)
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