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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


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

Prediction method of improved residual stress distribution by shot peening using large scale analysis method

Ikushima, Kazuki*; Shibahara, Masakazu*; Nishikawa, Satoru*; Furukawa, Takashi*; Akita, Koichi; Suzuki, Hiroshi; Morooka, Satoshi

E-Journal of Advanced Maintenance (Internet), 9(3), p.NT87_1 - NT87_5, 2017/11

Journal Articles

Thermal-hydraulics analysis of fuel assembly with inner duct structure of a sodium-cooled fast reactor

Kikuchi, Norihiro; Imai, Yasutomo*; Yoshikawa, Ryuji; Tanaka, Masaaki; Ohshima, Hiroyuki

Nippon Kikai Gakkai Kanto Shibu Ibaraki Koenkai 2017 Koen Rombunshu (CD-ROM), 4 Pages, 2017/08

A specific fuel assembly named FAIDUS (Fuel Assembly with Inner Duct Structure) has been developed as one of the measures to enhance safety of the reactor in the core disruptive accident (CDA) in JAEA. Thermal-hydraulics evaluations in FAIDUS under various operation conditions including the CDA are required to confirm its design feasibility. Therefore, numerical simulations by using thermal-hydraulics analysis program named SPIRAL developed in JAEA are conducted to analyze the thermal-hydraulics in the FAIDUS. Through the numerical simulation in the FAIDUS under tentative rated operation condition of an Advanced SFR, it was indicated that the flow and temperature distribution in the FAIDUS showed the same tendency as that in ordinary FA and specific characteristics was not observed.

JAEA Reports

Preliminary 3-dimensional analysis of groundwater flow in the surrounding environment of near surface disposal facility

Sakai, Akihiro; Kurosawa, Ryohei*; Totsuka, Masayoshi; Nakata, Hisakazu; Amazawa, Hiroya

JAEA-Technology 2016-032, 117 Pages, 2017/02


JAEA has been planning to implement near surface disposal of low level waste generated from research, medical, and industrial facilities. JAEA plans to carry out 3d analysis of groundwater flow in geological model around the disposal site because of development of migration assessment modeling of radioactivity materials in the site. In the safety demonstration test in JAEA, 3d analysis of groundwater flow was carried out on 1999. The analysis was calculated by using the code "3D-SEEP". But it is necessary to improve the conditions of the model in the analysis. Therefore, we improved the geological model which had been developed carried out 3d analysis of groundwater flow by using the current 3D-SEEP for the specified disposal site in the future. From the result, we expect that 3d analysis of groundwater flow in the environment around the specified near surface disposal site will be able to be sufficiently conducted by developing an appropriate model for the disposal site.

Journal Articles

An Illustration by the next generation numerical simulator for quake-proofing on the K

Nakajima, Norihiro; Suzuki, Yoshio; Miyamura, Hiroko; Nishida, Akemi; Kawakami, Yoshiaki; Guo, Z.; Tomiyama, Eiji*

Keisan Kogaku, 20(4), p.3338 - 3340, 2015/12

The issue 5 in the field 4 of "Monodukuri" in the HPCI strategy project is introduced. The title of the issue 5 is "research and development for the next-generation earthquake-resistant simulation of the large plants such as nuclear energy facilities". The illustration intends for a high temperature engineering examination research reactor. Implementation of FIESTA (Finite Element Analysis for Structure of Assembly) on K is described by reporting its efficiency and performance. To show a result of the numerical analysis, a visualization technique for the big data was described.

Journal Articles

Numerical analysis of flow field around simulated wire-wrapped fuel pins of fast reactor

Kikuchi, Norihiro; Ohshima, Hiroyuki; Imai, Yasutomo*; Hiyama, Tomoyuki; Nishimura, Masahiro; Tanaka, Masaaki

Nippon Kikai Gakkai Kanto Shibu Ibaraki Koenkai 2015 Koen Rombunshu, p.179 - 180, 2015/08

In an economically improved sodium-cooled fast reactor, a narrower gap is considered among the fuel pins so as to achieve a high burn-up. Therefore, it is needed to evaluate thermal-hydraulic characteristics in case of a change of the gap geometry due to deformation of fuel pin caused by such as a swelling and a thermal bowing. For this purpose, a FEM analysis code, SPIRAL has been being developed in JAEA and the code validations using water or sodium experimental results have also being performed. In this study, a numerical analysis of a flow field around wire-wrapped fuel pins based on a 3-pin bundle water experiment was carried out as a validation study of SPIRAL. As a result, it was demonstrated that the hybrid-type turbulent model incorporated in SPIRAL has a high applicability to investigate the flow structure of the narrow gap in the fuel assembly.

Journal Articles

Fracture evaluation of reactor pressure vessel steel based on local approach

Takamizawa, Hisashi; Katsuyama, Jinya; Yamaguchi, Yoshihito; Nishiyama, Yutaka; Li, Y.; Onizawa, Kunio

Yosetsu Kozo Shimpojiumu 2014 Koen Rombunshu, p.97 - 100, 2014/12

no abstracts in English

Journal Articles

Atomistic and continuum comparative studies on the stress distribution around a nano-crack on the grain boundary for modeling hydrogen embrittlement of iron

Ebihara, Kenichi; Kaburaki, Hideo; Itakura, Mitsuhiro

"Hagane No Kikaiteki Tokusei Ni Oyobosu Suiso No Koka To Sono Hyoka" Shimpojium Yokoshu (USB Flash Drive), 6 Pages, 2014/09

Since hydrogen(H) embrittlement is one factor causing degradation and/or fracture of steel, understanding its mechanism is required. The grain-boundary(GB) decohesion due to segregation of H is considered to cause the delayed fracture of high strength steels and the cold cracking in welding. In the model based on GB decohesion, information of strength of GBs estimated in the atomic scale is used for the estimation of strength or crack propagation in the macroscopic scale. However the modeling between the atomic and the macroscopic scales is not clear. In particular, the validity of the model using the elastic continuum around nano-cracks for stress concentration at the crack tip is not clear. Thus, we examined the difference of the stress distribution around the nano-crack which was estimated by molecular dynamics and by a continuum calculation. As a result, the discrepancy became remarkable at high strain. The stress concentration was not simulated by the elastic continuum model.

Journal Articles

Numerical simulation of in-line and cross-flow oscillations of a cylinder

Watanabe, Tadashi; Kondo, Masaya

JSME International Journal, Series B, 49(2), p.296 - 301, 2006/05

no abstracts in English

Journal Articles

Branching mechanism of intergranular crack propagation in three dimensions

Itakura, Mitsuhiro; Kaburaki, Hideo; Arakawa, Chuichi

Physical Review E, 71(5), p.055102_1 - 055102_4, 2005/05

 Times Cited Count:8 Percentile:58.04(Physics, Fluids & Plasmas)

The process of slow intergranular crack propagation was investigated by the finite element method model and it was found that branching is induced by partial arresting of a crack front owing to the geometrical randomness of grain boundaries. A possible scenario for the branching instability of crack propagation in a disordered continuous medium is also discussed.

Journal Articles

Design of the anchor wall using 3D finite element method

Iha, Akane*; Matsubara, Hitoshi; Iraha, Shigeo*; Kanda, Yasuyuki*

Konkurito Kogaku Nenji Rombunshu (DVD-ROM), 27(2), p.1663 - 1668, 2005/00

The concrete structures such a reactor building are able to resist external forces by interaction behavior such as concrete, reinforcements, steel frames and the foundation. Therefore, it is a very important subject to solve analytically the displacement behavior and the stress distribution because the safety of structures and safe security can be offered by it. In general, such a problem is solved by using the beam theory. However, it is impossible to evaluate the different behavior or stress distribution on every component. In this paper, 3-dimensional finite element analysis of full-scale anchor wall is performed. In addition, all composition material is taken into consideration in this analysis. Consequently, concrete interaction behavior with many components is solved, and the displacement behavior and concentration of stress also is elucidated.

Journal Articles

Inverse problem on indentation load and depth curve; Identification of material constants by using a spherical indenter

Futakawa, Masatoshi; Wakui, Takashi*; Naoe, Takashi*; Ioka, Ikuo

Jikken Rikigaku, 4(3), p.222 - 227, 2004/09

no abstracts in English

Journal Articles

Structural integrity of cross-flow type mercury target

Kogawa, Hiroyuki; Ishikura, Shuichi*; Haga, Katsuhiro; Kinoshita, Hidetaka; Kaminaga, Masanori; Hino, Ryutaro

Proceedings of ICANS-XVI, Volume 3, p.1295 - 1304, 2003/07

no abstracts in English

Journal Articles

Mechanical property evaluation of surface layer corroded in thermochemical-hydrogen-production process condition

Futakawa, Masatoshi; Kubo, Shinji; Wakui, Takashi*; Onuki, Kaoru; Shimizu, Saburo; Yamaguchi, Akihisa*

Jikken Rikigaku, 3(2), p.109 - 114, 2003/06

Micro-indentation technique was applied to evaluate the mechanical properties of corroded surface layers of Ni-alloy, 316SS, Ti and Ta, which were exposed into the corrosive gaseous environment consisting of HI+I$$_{2}$$+H$$_{2}$$O+H$$_{2}$$. The corrosion condition was chosen so as to simulate one of the environments in the thermochemical hydrogen production, IS process, where the degradation due to the corrosion attack by HI and the hydrogen embrittlement is a key issue from the viewpoint of material integrity. The micro-indentation tests using a spherical indenter and the inverse analysis with Kalman filter were performed to quantitatively estimate material constants of corroded surface layer. Ni-alloy exhibited good corrosion resistance and Ta was remarkably influenced by the hydrogen embrittlement.

JAEA Reports

Environmental equipment for usages of FEM software; ADVENTURE system user's guide

Yamasaki, Ichiro*; Yoshimura, Shinobu*

JAERI-Tech 2003-050, 58 Pages, 2003/05


no abstracts in English

Journal Articles

Coupled behavior between structural body and liquid under impact loading

Kogawa, Hiroyuki; Ishikura, Shuichi*; Futakawa, Masatoshi; Hino, Ryutaro

Jikken Rikigaku, 2(2), p.122 - 127, 2002/06

no abstracts in English

Journal Articles

Fatigue behavior on weldment of austenitic stainless steel for ITER vacuum vessel

Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Koizumi, Koichi; Nakahira, Masataka; Takahashi, Hiroyuki*

Fusion Engineering and Design, 58-59, p.869 - 873, 2001/11

 Times Cited Count:1 Percentile:87.09(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Fatigue strength reduction factor of partial penetration weldments for ITER vacuum vessel

Nishi, Hiroshi; Eto, Motokuni; Tachibana, Katsumi; Nakahira, Masataka

Transactions of 16th International Conference on Structural Mechanics in Reactor Technology (SMiRT-16) (CD-ROM), 8 Pages, 2001/08

Fatigue test of the weldments was performed to investigate their fatigue behavior and the effect of the incomplete penetrations on the fatigue strength. Fatigue crack propagation test of their weld metals was also carried out using CT specimen. By calculating stress intensity factors of the weldments contained the incomplete penetrations and cracks using FEM analysis, the fatigue crack propagation rates of weldments were evaluated and compared those of their weld metals. Fatigue life of the weldments was evaluated based on fracture mechanics to discuss the effect of incomplete penetrations on the fatigue strength. As the results, the incomplete penetration behaved as a crack and most of total fatigue life for the weldment was crack propagation life. The crack propagation rates of weldment were in accordance with those of the weld metals. The fatigue strength of the weldment was considerably lower than that of smoothed specimen. The incomplete penetrations affected greatly the fatigue strength of the weldments even if the depth of incomplete penetrations was small.

Journal Articles

Neutron diffraction experience at RESA for engineering-aided application

Tsuchiya, Yoshinori; Kikuchi, Kenji; Minakawa, Nobuaki; Morii, Yukio; Kato, Takashi; Nakajima, Hideo; Tsuji, Hiroshi

Journal of the Physical Society of Japan, Vol.70, Supplement A, p.520 - 522, 2001/05

no abstracts in English

Journal Articles

Evaluation of residual stress redistribution behavior with crack extension

Okido, Shinobu*; Hayashi, Makoto*; Morii, Yukio; Minakawa, Nobuaki

Materials Science Research International, Special Technical Publication, 1, p.435 - 438, 2001/05

no abstracts in English

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