K. Takase

发表

Large-Scale Simulations on Thermal-Hydraulics in Fuel Bundles of Advanced Nuclear Reactors

E. Merzari, K. Takase, H. Yoshida, 2007 .

A Large-Scale Simulation on Two-Phase Flow Characteristics Around Duel Rods in a Tight-Lattice Core

K. Takase, H. Yoshida, Y. Ose, 2006 .

Condensation Heat Transfer

K. Takase, H. Yoshida, H. Akimoto, 2016 .

DNS of MHD turbulent flow via the HELIOS supercomputer system at IFERC-CSC

T. Kunugi, K. Takase, S. Satake, 2014, ICS 2014.

DNS of turbulent heat transfer under a uniform magnetic field at high Reynolds number

T. Kunugi, K. Takase, Y. Ose, 2008 .

DNS of Turbulent Channel Flow at High Reynolds Number under a Uniform Magnetic Field(Fluids Engineering)

T. Kunugi, K. Takase, Y. Ose, 2007 .

Direct numerical simulation of turbulent channel flow under a uniform magnetic field for large-scale structures at high Reynolds number

T. Kunugi, K. Takase, Y. Ose, 2006 .

Effect of Seawater on Heat Transfer without Boiling in Internally Heated Annulus

Wei Liu, K. Takase, H. Yoshida, 2016 .

Bubble behavior in horizontal two-phase flow under flow rate fluctuation

H. Monji, K. Takase, H. Yoshida, 2014 .

Numerical Analysis of Heat Transfer Test of Supercritical Water in a Tube Using the Three-Dimensional Two-Fluid Model Code

K. Takase, H. Yoshida, H. Tamai, 2009 .

Numerical Simulations on Dust-Air Two-Phase Flows in Fusion Experimental Reactors During Loss-of-Vacuum-Accident Events

K. Takase, 2001 .

ICONE23-1914 DEVELOPMENT OF POPCORN CODE FOR SIMULATING MELTING BEHAVIOR OF FUEL ELEMENT : FUNDAMENTAL VALIDATION AND SIMULATION FOR MELTING BEHAVIOR OF SIMULATED FUEL ROD

K. Takase, H. Yoshida, M. Kurata, 2015 .

Experimental results of heat transfer coefficients and friction factors in a 2D/3D rib-roughened annulus

K. Takase, 1996 .

Large Scale Computations in Nuclear Engineering: CFD for Multiphase Flows and DNS for Turbulent Flows with/without Magnetic Field

T. Kunugi, K. Takase, H. Yoshida, 2010 .

Investigation of Water-Vapor Two-Phase Flow Characteristics in a Tight-Lattice Core by Large-Scale Numerical Simulation, (IV) Large-Scale Analysis of Water-Vapor Two-Phase Flow in Rod Bundles with TPFIT code using Earth Simulator

K. Takase, M. Kureta, T. Nagayoshi, 2009 .

A Large-Scale Parallel Computing of Boiling Two-Phase Flow Behavior in Advanced Light Water Reactors

K. Takase, H. Yoshida, T. Misawa, 2008 .

Numerical Analysis Of Three-dimensionalTwo-phase Flow Behavior In A Fuel Assembly

K. Takase, H. Yoshida, Y. Ose, 2005 .

A Large-Scale Simulation on Water-Vapor Two-Phase Flow Dynamics in Fuel Bundles of Advanced Nuclear Reactors

K. Takase, H. Yoshida, Y. Ose, 2005 .

Three-dimensional electronic structures and the metal-insulator transition in Ruddlesden-Popper iridates

H. Takagi, K. Takase, K. Yamagami, 2016, 1610.04361.

Assessment of Applicability of Two-Fluid Model Code ACE-3D to Heat Transfer Test of Supercritical Water Flowing in an Annular Channel

K. Takase, H. Yoshida, M. Enoeda, 2010 .

R&D on thermal hydraulics of core and core–bottom structure

Kazuhiko Kunitomi, Kazuyuki Takase, Yoshiyuki Inagaki, 2004 .

Numerical prediction of augmented turbulent heat transfer in an annular fuel channel with repeated two-dimensional square ribs

Kazuyuki Takase, K. Takase, 1996 .

Pressure Drop and Void Fraction in Steam-Water Two-Phase Flow at High Pressure

Wei Liu, K. Takase, H. Tamai, 2013 .

Thermal Feasibility Analyses for the 1356MWe High Conversion-Type Innovative Water Reactor for Flexible Fuel Cycle

Wei Liu, K. Takase, H. Yoshida, 2008 .

ITER R&D: Auxiliary Systems: Safety Related R&D

Kazuyuki Takase, David A. Petti, B. N. Kolbasov, 2001 .

Experimental Research on the Effect of Axial Power Distribution on Critical Power

Wei Liu, K. Takase, M. Kureta, 2009 .

BASIC EXPERIMENTAL STUDY ON EFFECTIVENESS OF NUCLEAR WASTE LONG-TERM STORAGE CONTAINERS WITH PAR FOR REDUCING CONCENTRATION OF HYDROGEN GAS

K. Takase, Yoshinobu Matsumoto, Y. Hiraki, 2019, The Proceedings of the International Conference on Nuclear Engineering (ICONE).

Experimental and analytical studies on turbulent heat transfer performance of a fuel rod with spacer ribs for high temperature gas-cooled reactors

K. Takase, 1995 .

Results of Two-Phase Flow Experiments with an Integrated Ingress-of-Coolant Event (ICE) Test Facility for ITER Safety

Kazuyuki Takase, L. N. Topilski, Hajime Akimoto, 2001 .

Numerical study on pressure rise characteristics in simulated ITER structural components during ingress-of-coolant events

K. Takase, Y. Ose, H. Akimoto, 2000 .

Possibility of Volume Reduction of Blowdown Tank in Fusion Reactor Safety System

T. Kunugi, K. Takase, S. Fujii, 1998 .

Thermofluid experiments on ingress of coolant event

T. Kunugi, K. Takase, Y. Seki, 1998 .

Fundamental study of a water jet injected into a vacuum vessel of fusion reactor under the ingress of coolant event

Kazuyuki Takase, Tomoaki Kunugi, Yasushi Seki, 1996 .

Experimental verification of effectiveness of integrated pressure suppression systems in fusion reactors during in-vessel loss of coolant events

K. Takase, H. Akimoto, 2001 .

Experimental results of functional performance of a vacuum vessel pressure suppression system in ITER

Kazuyuki Takase, Hajime Akimoto, K. Takase, 2002 .

Analysis of Pressure Rise in an ITER-Like Fusion Reactor During In-Vessel LOCA by A Modified TRAC-PF1 Code

K. Takase, Y. Ose, H. Akimoto, 2001 .

A Preliminary Study on Direct-Contact Condensation Between Water and Vapor in A Suppression Tank for Fusion Reactor Safety

K. Takase, 2001 .

Experimental Verification of Integrated Pressure Suppression Systems in Fusion Reactors at In-Vessel Loss-of-Coolant Events

K. Takase, H. Akimoto, 2000 .

Safety scenario and integrated thermofluid test

T. Kunugi, K. Takase, Y. Seki, 1998 .

Analysis and experimental results on ingress of coolant event in vacuum vessel

T. Kunugi, K. Takase, Y. Seki, 1998 .

Three-dimensional analysis of water–vapor void fraction in a fusion experimental reactor under water ingress

K. Takase, Y. Ose, H. Akimoto, 2002 .

Temperature distributions in a Tokamak vacuum vessel of fusion reactor after the loss-of-vacuum events occurred

Kazuyuki Takase, Tomoaki Kunugi, Yasushi Seki, 1998 .

Proposal of Integrated Test Facility for in-Vessel Thermofluid Safety of Fusion Reactors

Kazuyuki Takase, Tomoaki Kunugi, Takashi Okazaki, 1997 .

Effects of Breach Area and Length to Exchange Flow Rates Under the Lova Condition in a Fusion Reactor

Kazuyuki Takase, Tomoaki Kunugi, Yasushi Seki, 1996 .

Experimental studies on the thermal and hydraulic performance of the fuel stack of the VHTR: Part I. HENDEL single-channel tests with uniform heat flux

Kazuyuki Takase, Makoto Hishida, Soh Maruyama, 1987 .

Experimental studies on the thermal and hydraulic performance of the fuel stack of the VHTR: Part II. HENDEL multi-channel test rig with twelve fuel rods

Kazuyuki Takase, Hiroshi Kawamura, Soh Maruyama, 1987 .

Steam Water Pressure Drop under 15 MPa

Wei Liu, K. Takase, N. Kisohara, 2011 .

Development of measurement technology for surface heat fluxes and temperatures

Wei Liu, K. Takase, 2012 .

Thermal-Hydraulic Experiments Under High Pressure Condition

Wei Liu, K. Takase, N. Kisohara, 2010 .