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Yoshikawa, Ryuji; Tanaka, Masaaki; Ohshima, Hiroyuki; Imai, Yasutomo*
Proceedings of 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11) (USB Flash Drive), 12 Pages, 2016/10
A sodium-water coupled thermal-hydraulics simulation code TSG has been developed for numerical estimation of three-dimensional thermal-hydraulic phenomena in the straight-tube steam generator. The water analysis module was developed by using the parallel channel model of heat transfer tubes, and the sodium analysis module was developed by using porous body approach. As the first step of validation, simulation results by TSG were compared with the measured data of 1MWt SG experiments under steady state conditions. Through the numerical simulation, the coupled simulation method used in TSG was validated and applicability of TSG to simulate thermal-hydraulics of the straight tube SG in the steady state was confirmed.
Takayama, Yusuke; Sato, Toshinori; Onoe, Hironori; Iwatsuki, Teruki; Saegusa, Hiromitsu; Onuki, Kenji
Dai-43-Kai Gamban Rikigaku Ni Kansuru Shimpojiumu Koenshu (CD-ROM), p.313 - 318, 2015/01
In the Mizunami Underground Research Laboratory, groundwater recovery experiment is being conducted to construct the method to understand the transition of geological environment due to groundwater recovery at the -500m access and research gallery-north. As a part of this experiment, backfill test is planned using drilling pits filled with artificial materials (clay and concrete) to evaluate the influence on the surrounding rock mass due to the interaction of rock and artificial materials. In this study, numerical simulation of the backfill test has been carried out to predict the qualitative hydro-mechanical behavior.
Guo, Z.; Hazama, Osamu; Yamagiwa, Mitsuru; Hirayama, Toshio; Matsuzawa, Teruo*
Advances in computational & experimental engineering & sciences (CD-ROM), 6 Pages, 2003/07
no abstracts in English
Tamura, Itaru; Aizawa, Kazuya; Harada, Masahide; Shibata, Kaoru; Maekawa, Fujio; Soyama, Kazuhiko; Arai, Masatoshi
Proceedings of ICANS-XVI, Volume 1, p.529 - 539, 2003/07
Moderator components of the McStas code have been created for the design of the spectrometers of JSNS. Three cryogenic moderators are adopted in JSNS, One is a coupled H
moderator for high intensity experiments and other two are decoupled H with poisoned or unpoisoned for high resolution moderators. Monte Carlo simulations have turned out to be useful for design of neutron scattering instruments with high complexity. The software package McStas is selected for its own flexibility. Since the characteristics of neutron beams generated from moderators make influence on the performance of pulse neutron spectrometers, it is important to perform the simulation with neutron source component written precisely. Both Energy dependence of neutron spectrum and time structure of neutrons were calculated using NMTC/JAERI97 and MCNP4a codes.The simulation parameters, which describe the pulse shape as a function of time, are optimized. The creation of neutron source components viewed to coupled H moderator and viewed to decoupled H moderator of JSNS are reported.
Tamura, Itaru; Aizawa, Kazuya; Harada, Masahide; Shibata, Kaoru; Maekawa, Fujio; Soyama, Kazuhiko; Arai, Masatoshi
JAERI-Research 2003-008, 34 Pages, 2003/03
JAERI-Research-2003-008.pdf:1.62MB
Moderators components of the McStas code have been created for the design of JSNS instruments. Three cryogenic moderators are adopted in JSNS, One is coupled H moderators for high intensity experiments and other two are decoupled H with poisoned or unpoisoned for high resolution moderators. Since the characteristics of neutron beams generated from moderators make influence on the performance of pulse neutron spectrometers, it is important to perform the Monte Carlo simulation with neutron source component written recisely. The neutron spectrum and time structure were calculated using NMTC/JAERI97 and MCNP4a codes. The simulation parameters, which describe the pulse shape over entire spectrum as a function of time, are optimized. In this paper, the creation of neutron source components for port No.16 viewed to coupled H moderator and for port No.11 viewed to decoupled H moderator of JSNS are reported.
; Onishi, Ryoichi*; *; Guo, Z.*
Parallel Computational Dynamics, p.267 - 274, 1999/00
no abstracts in English
; Takemiya, Hiroshi*; Onishi, Ryoichi*
Proc. of 14th AIAA Computational Fluid Dynamics Conf., 11 Pages, 1999/00
no abstracts in English
*; *;
JAERI-Data/Code 96-031, 53 Pages, 1996/11
JAERI-Data-Code-96-031.pdf:1.82MB
no abstracts in English
Ozaki, Yusuke; Ishibashi, Masayuki; Onoe, Hironori; Iwatsuki, Teruki
no journal, ,
We perform a prediction analysis of the Groundwater Recovery Experiment in Tunnel (GREET) that is an ongoing experiment project in Mizunami Underground Research Laboratory for undearstanding of geoenvironmental recovery after closure of subsurface facility. The hydro-mechanical-chemical coupled behavior of subsurface environment during the excavation of research tunnel for GREET is simulated. For this prediction study, we build a hydrogeological model based on information of fracture with Discrete Fracture Network model. The model is converted to equivalent continuous porous model (ECPM) for Finite Element modelling. We compare the predicted results of drawdown of hydraulic pressure, inflow into tunnel and variation of Cl concentration during excavation.
Ozaki, Yusuke; Onoe, Hironori; Iwatsuki, Teruki
no journal, ,
In the Mizunami Underground Research Laboratory, Groundwater REcovery Experiment in Tunnel (GREET) is performed as a part of development of backfilling technologies. In GREET, water pressure, displacement of bedrock, water quality, etc. are monitored in and around the test drift to capture the disturbance and recovery process of geological environment by excavation and closure of the test drift. In addition to in-situ data acquisition, numerical simulation is performed to enhance the understanding of the coupled process. In this study, we demonstrate the results of coupled simulation of excavation of the test drift.