Study of hydrogeology in the Mizunami Underground Research Laboratory Project; Hydrogeological modeling at site scale in Phase II

Onoe, Hironori; Kosaka, Hiroshi*; Takeuchi, Ryuji; Saegusa, Hiromitsu

JAEA-Research 2015-008, 146 Pages, 2015/08

JAEA-Research-2015-008.pdf:76.46MB

Mizunami Underground Research Laboratory (MIU) Project is being carried out by Japan Atomic Energy Agency (JAEA) in the Cretaceous Toki granite in the Tono area, central Japan. The MIU Project has three overlapping phases: Surface-based Investigation (Phase I), Construction (Phase II) and Operation (Phase III). In this study, calibration of hydrogeological model and groundwater flow simulation using the data obtained by the Phase I and Phase II were carried out in order to develop the methodology for construction and update of hydrogeological model on Site Scale. As a result, hydrogeological model on Site Scale, which is able to simulate comprehensively the obtained data regarding groundwater pressure distribution before excavation of the MIU facilities, hydraulic responses and inflow volume during excavation of the MIU facilities, was constructed.

Applications of ultrasound technique to flow velocity measurement in water experiment of inter-wrapper flow; Comparison with particle image velocimetry

Kimura, Nobuyuki; ; ; ; Kamide, Hideki; Tokuhiro, Akira; Hishida, Koichi

JNC TN9400 2000-057, 60 Pages, 2000/05

JNC-TN9400-2000-057.pdf:2.11MB

ln experimental study for the thermohydraulics of fast reactor, a simple experiment with fine measurement has been desired for understanding of phenomena and for verification of computer code rather than mockup experiments of large scale. For such purposes quality of experimental data must be improved. ln the velocity measurement, instantaneous velocity profile will have great advances for the understanding of phenomena and for the verification of computer code. ln this report two methods of the velocity profile measurement are discussed; one is ultrasound Doppler velocimetry (UDV) and the other is particle image velocimetry (PIV). These methods were applied to water experiments. The UDV was applied to pipe flow, planer jet, and the inter-wrapper flow which is seen in the gap region between subassemblies of fast reactor core. Cross check with laser Doppler velocimetly showed proper measurement of the UDV. Problems including the application to sodium experiments are also discussed. The PIV was also applied to the inter-wrapper flow. For the application to complex flow geometry, noise reduction method was developed to improve the measurement accuracy.

None

PNC TN1430 97-001, 28 Pages, 1997/01

PNC-TN1430-97-001.pdf:1.3MB

no abstracts in English

Two-Block Crossflow Experimets,I; Experimetal Apparatus and Conditions

Takizuka, Takakazu; ; ; Sanokawa, Konomo

JAERI-M 84-222, 20 Pages, 1984/12

JAERI-M-84-222.pdf:0.71MB

no abstracts in English

Evaluation of Symbiotic Energy System Between Gas-Cooled Fast Breeder Reactor and Multipurpose Very High Temperature Reactor(III); Reference GCFR Core Configuration and It's Thermo-Hydraulic Characteristics

; ; *; *; *

JAERI-M 82-183, 68 Pages, 1982/12

JAERI-M-82-183.pdf:1.92MB

no abstracts in English

Establishment of comprehensive techniques for investigation, modeling and assessment to estimate long-term evolution of groundwater flow characteristics on geological time scale, 1; Overview

Saegusa, Hiromitsu; Oyama, Takuya; Onoe, Hironori

no journal, , 

no abstracts in English

Case study on the development of methodologies for validation of groundwater flow and mass transport model, 2; Effects of the modeling methods of low permeability fractures on groundwater flow characterization

Ishibashi, Masayuki*; Onoe, Hironori*; Esaki, Taichi*; Tagawa, Yoichi*; Tabei, Kazuto*; Namikawa, Tadashi*; Hane, Koji*; Saegusa, Hiromitsu*; Ishida, Keisuke*; Sawada, Atsushi

no journal, , 

no abstracts in English

Case study on the development of methodologies for validation of groundwater flow and mass transport model, 4; Construction of the ECPM model based on the DFN model

Tagawa, Yoichi*; Onoe, Hironori*; Esaki, Taichi*; Hane, Koji*; Ishibashi, Masayuki*; Namikawa, Tadashi*; Tabei, Kazuto*; Saegusa, Hiromitsu*; Ishida, Keisuke*; Sawada, Atsushi

no journal, , 

no abstracts in English

Conceptual design of high-performance moderator vessel for JRR-3 cold neutron source, 3; Evaluation of optimum geometry by flow analysis

Tokunaga, Sho; Nakamura, Takemi; Kikuchi, Masanobu

no journal, , 

Research reactor JRR-3 on Japan Atomic Energy Agency plans to replace the cold neutron source moderator vessel. Conceptual design for high-performance moderator vessel was carried out for the purpose of increasing the cold neutron source. The optimum geometry determined by the nuclear characteristic analysis was evaluated by flow analysis. Its characteristics are reported.