Ninokata, Hisashi: search on Z-Library

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1

Pioneering Role of IRIS in the Resurgence of Small Modular Reactors

Petrovic, Bojan, Ricotti, Marco, Monti, Stefano, Čavlina, Nikola, Ninokata, Hisashi

Journal:

Nuclear Technology

Year:

2012

Language:

english

File:

PDF, 1.63 MB

english, 2012

2

Challenges in reactor core thermal-hydraulics: subchannel analysis, CFD modeling and rod bundle CHF

Yang, Bao-Wen, Hassan, Yassin A., Ninokata, Hisashi, Shan, Jianqiang, Zhang, Yuxiang, Zhang, Bin

Journal:

Year:

2016

Language:

english

File:

PDF, 63 KB

english, 2016

3

Thermal Hydraulics of Sodium-Cooled Fast Reactors: Key Design and Safety Issues and Highlights

Ninokata, Hisashi, Kamide, Hideki

Journal:

Nuclear Technology

Year:

2013

Language:

english

File:

PDF, 813 KB

english, 2013

4

Evaluation Method for Flow Accelerated Corrosion of Components by Corrosion Analysis Coupled with Flow Dynamics Analysis

Naitoh, Masanori, Uchida, Shunsuke, Koshizuka, Seiichi, Ninokata, Hisashi, Minato, Akihiko, Saitoh, Hiroaki, Hotta, Koji, Akiyama, Minoru, Anahara, Naoki, Dozaki, Koji

Journal:

Heat Transfer Engineering

Year:

2008

Language:

english

File:

PDF, 1.93 MB

english, 2008

5

Safety characteristics of the multipurpose fast reactor (MPFR)

Alexandre Netchaev, Yuichi Hizume, Hiroshi Endo, Tetsuo Sawada, Hisashi Ninokata

Journal:

Annals of Nuclear Energy

Year:

2001

Language:

english

File:

PDF, 944 KB

english, 2001

6

In-Vessel Thermohydraulics Evaluation of an Unprotected Transient Overpower Accident and Delayed Neutron Precursor Concentration Transport Analysis Using a Multidimensional Code

Muramatsu, Toshiharu, Ninokata, Hisashi

Journal:

Nuclear Technology

Year:

1992

Language:

english

File:

PDF, 4.91 MB

english, 1992

7

The concept and neutronic characteristics of a multipurpose fast reactor (MPFR)

Alexandre Netchaev, Hiroshi Endo, Tetsuo Sawada, Hisashi Ninokata

Journal:

Annals of Nuclear Energy

Year:

2001

Language:

english

File:

PDF, 1.18 MB

english, 2001

8

AN EFFECTIVE, LOCALLY EXACT FINITE-DIFFERENCE SCHEME FOR CONVECTION-DIFFUSION PROBLEMS

Ninokata, Vladimir Kriventsev, Hisashi

Journal:

Numerical Heat Transfer Part B Fundamentals

Year:

1999

Language:

english

File:

PDF, 387 KB

english, 1999

9

Thermal Striping Temperature Fluctuation Analysis Using the Algebraic Stress Turbulence Model in Water and Sodium

MURAMATSU, Toshiharu, NINOKATA, Hisashi

Journal:

JSME international journal. Ser. 2, Fluids engineering, heat transfer, power, combustion, thermophysical properties

Year:

1992

File:

PDF, 1.09 MB

1992

10

Suppression pool testing at the SIET laboratory: experimental investigation of critical phenomena expected in the Fukushima Daiichi suppression chamber

Pellegrini, Marco, Araneo, Lucio, Ninokata, Hisashi, Ricotti, Marco, Naitoh, Masanori, Achilli, Andrea

Journal:

Journal of Nuclear Science and Technology

Year:

2016

Language:

english

File:

PDF, 1.62 MB

english, 2016

11

[ASME ASME 2009 Fluids Engineering Division Summer Meeting - Vail, Colorado, USA (August 2–6, 2009)] Volume 2: Fora - Cylindrical Couette Flow of a Rarefied Gas From Macro- to Micro-Scales

Wang, Sheng, Lei, Kangbin, Luo, Xilian, Kase, Kiwamu, Merzari, Elia, Ninokata, Hisashi

Year:

2009

Language:

english

File:

PDF, 553 KB

english, 2009

12

Development of Analytical Evaluation Method for Thermal Striping Phenomena.

MURAMATSU, Toshiharu, NINOKATA, Hisashi

Journal:

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan

Year:

1994

Language:

english

File:

PDF, 11.09 MB

english, 1994

13

Multi-dimensional analysis of two-phase flow inside subchannels of nuclear fuel assembly

Junichi Kaneko, Akihiko Minato, Hisashi Ninokata

Journal:

Progress in Nuclear Energy

Year:

2005

Language:

english

File:

PDF, 478 KB

english, 2005

14

In memoriam of Mujid S. Kazimi (1947–2015)

Ninokata, Hisashi

Journal:

Journal of Nuclear Science and Technology

Year:

2015

Language:

english

File:

PDF, 341 KB

english, 2015

15

Nodal neutron kinetics model based on nonlinear iteration procedure for LWR analysis

Vyacheslav G. Zimin, Hisashi Ninokata

Journal:

Annals of Nuclear Energy

Year:

1998

Language:

english

File:

PDF, 1.13 MB

english, 1998

16

Distributed resistance modeling of wire-wrapped rod bundles

Hisashi Ninokata, Apostolos Efthimiadis, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Year:

1987

Language:

english

File:

PDF, 657 KB

english, 1987

17

Validation of a computational model for the evaluation of fuel-coolant interaction under severe accidental condition in fast breeder reactors

Tetsuo Sawada, Hisashi Ninokata

Journal:

Annals of Nuclear Energy

Year:

1998

Language:

english

File:

PDF, 663 KB

english, 1998

18

Acceleration of the outer iterations of the space-dependent neutron kinetics equations solution

Vyacheslav G. Zimin, Hisashi Ninokata

Journal:

Annals of Nuclear Energy

Year:

1996

Language:

english

File:

PDF, 1.34 MB

english, 1996

19

Potential to approach the long-life core in a light water reactor with uranium oxide fuel

Vladimir Barchevtsev, Hisashi Ninokata, Vladimir Artisyuk

Journal:

Annals of Nuclear Energy

Year:

2002

Language:

english

File:

PDF, 244 KB

english, 2002

20

Calculation of a materials relocation experiment simulating a core discruptive accident condition in fast breeder reactors

Tetsuo Sawada, Hisashi Ninokata, Akinao Shimizu

Journal:

Nuclear Engineering and Design

Year:

1995

Language:

english

File:

PDF, 1.12 MB

english, 1995

21

Double-strata high burnup fuel performance in light water reactors

Vladimir Barchevtsev, Vladimir Artisyuk, Hisashi Ninokata

Journal:

Annals of Nuclear Energy

Year:

2002

Language:

english

File:

PDF, 363 KB

english, 2002

22

Investigation of turbulence modelling in thermal stratification analysis

Toshiharu Muramatsu, Hisashi Ninokata

Journal:

Nuclear Engineering and Design

Year:

1994

Language:

english

File:

PDF, 1.04 MB

english, 1994

23

Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (I)

NAITOH, Masanori, UCHIDA, Shunsuke, KOSHIZUKA, Seiichi, NINOKATA, Hisashi, HIRANUMA, Naoki, DOSAKI, Koji, NISHIDA, Koji, AKIYAMA, Minoru, SAITOH, Hiroaki

Journal:

Journal of Nuclear Science and Technology

Year:

2008

Language:

english

File:

PDF, 607 KB

english, 2008

24

Development of Analytical Method for Thermal Striping Phenomena.

MURAMATSU, Toshiharu, NINOKATA, Hisashi

Journal:

TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series B

Year:

1991

File:

PDF, 764 KB

1991

25

[ASME ASME-JSME-KSME 2011 Joint Fluids Engineering Conference - Hamamatsu, Japan (July 24–29, 2011)] ASME-JSME-KSME 2011 Joint Fluids Engineering Conference: Volume 1, Symposia – Parts A, B, C, and D - Subchannel Analysis of Single-Phase Flow Sodium Tests With Non-Uniform Radial Power Distributions

Pramuditya, Syeilendra, Ninokata, Hisashi

Year:

2011

Language:

english

File:

PDF, 1.06 MB

english, 2011

26

Development of Thermohydraulics Computer Programs for Thermal Striping Phenomena

Muramatsu, Toshiharu, Ninokata, Hisashi

Journal:

Nuclear Technology

Year:

1996

Language:

english

File:

PDF, 13.34 MB

english, 1996

27

A calculation methodology proposed for liquid droplet impingement erosion

Rui Li, Michitsugu Mori, Hisashi Ninokata

Journal:

Nuclear Engineering and Design

Year:

2012

Language:

english

File:

PDF, 823 KB

english, 2012

28

Concept of Erbium Doped Uranium Oxide Fuel Cycle in Light Water Reactors

BARCHEVTSEV, Vladimir, ARTISYUK, Vladimir, NINOKATA, Hisashi

Journal:

Journal of Nuclear Science and Technology

Year:

2002

Language:

english

File:

PDF, 165 KB

english, 2002

29

Numerical Simulation of Sodium Pool Fire

Doda, Norihiro, Okano, Yasushi, Ninokata, Hisashi

Journal:

Nuclear Technology

Year:

2003

Language:

english

File:

PDF, 456 KB

english, 2003

30

Simulation of Boiling Water Reactor One-Pump Trip Transient by TRAC/BF1-ENTRÉE

Hotta, Akitoshi, Anegawa, Takafumi, Hara, Takashi, Ninokata, Hisashi

Journal:

Nuclear Technology

Year:

2003

Language:

english

File:

PDF, 2.03 MB

english, 2003

31

Sabena: Subassembly boiling evolution numerical analysis

Hisashi Ninokata, Taka-aki Okano

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.13 MB

english, 1990

32

Distributed parameter analysis for the prediction of the fine structure of flow and temperature fields in wire-wrapped fuel pin bundle geometries

Takeshi Shimizu, Hisashi Ninokata, Hajime Shishido

Journal:

Nuclear Engineering and Design

Year:

1990

Language:

english

File:

PDF, 1.14 MB

english, 1990

33

Numerical Studies on Dynamic Behavior of Air-Water Cross Flow Between Two Circular Interconnected Channels

KANEKO, Junichi, NINOKATA, Hisashi, MINATO, Akihiko

Journal:

Journal of Nuclear Science and Technology

Year:

2009

Language:

english

File:

PDF, 907 KB

english, 2009

34

On Void Reactivity Limitation for the Core Loaded with Mixed Nitride Fuels

Ishizu, Tomoko, ENDO, Hiroshi, NINOKATA, Hisashi

Journal:

Journal of Nuclear Science and Technology

Year:

2009

Language:

english

File:

PDF, 1.11 MB

english, 2009

35

Validation Studies of a Computational Model for Molten Material Freezing

Sawada, Tetsuo, Ninokata, Hisashi, Shimizu, Akinao

Journal:

Nuclear Technology

Year:

1996

Language:

english

File:

PDF, 2.97 MB

english, 1996

36

A Recriticality-Free Fast Reactor Core Concept

Sawada, Tetsuo, Ninokata, Hisashi, Tomozoe, Hirofumi, Endo, Hiroshi

Journal:

Nuclear Technology

Year:

2000

Language:

english

File:

PDF, 697 KB

english, 2000

37

[ASME ASME-JSME-KSME 2011 Joint Fluids Engineering Conference - Hamamatsu, Japan (July 24–29, 2011)] ASME-JSME-KSME 2011 Joint Fluids Engineering Conference: Volume 1, Symposia – Parts A, B, C, and D - Study on General Wall Damping Functions Definition: A Low Reynolds Number Bounded Flows Validation

Pellegrini, Marco, Endo, Hiroshi, Ninokata, Hisashi

Year:

2011

Language:

english

File:

PDF, 2.15 MB

english, 2011

38

Development of analysis method for sodium void reactivity of step type FBR cores by using group-wise Monte Carlo code

Tsugio Yokoyama, Hiroshi Endo, Hisashi Ninokata

Journal:

Annals of Nuclear Energy

Year:

2011

Language:

english

File:

PDF, 1.19 MB

english, 2011

39

Feasibility study of the application of exotic pin for tight-lattice fuel assembly

Azizul Khakim, Hisashi Ninokata

Journal:

Progress in Nuclear Energy

Year:

2011

Language:

english

File:

PDF, 2.68 MB

english, 2011

40

Analysis of an Out-of-pile Experiment for Materials Redistribution under Core Disruptive Accident Condition of Fast Breeder Reactors

SAWADA, Tetsuo, NINOKATA, Hisashi, SHIMIZU, Akinao

Journal:

Journal of Nuclear Science and Technology

Year:

1995

Language:

english

File:

PDF, 1.84 MB

english, 1995

41

Biglobal linear stability analysis for the flow in eccentric annular channels and a related geometry

Merzari, Elia, Wang, Sheng, Ninokata, Hisashi, Theofilis, Vassilis

Journal:

Physics of Fluids

Year:

2008

Language:

english

File:

PDF, 2.41 MB

english, 2008

42

The pumping performances of the turbomoleculae pump simulated by direct simulation monte carlo method

Sheng Wang, Hisashi Ninokata

Journal:

Progress in Nuclear Energy

Year:

2005

Language:

english

File:

PDF, 907 KB

english, 2005

43

BWR Regional Instability Analysis by TRAC/BF1-ENTRÉE—II: Application to Ringhals Unit-1 Stability Test

Hotta, Akitoshi, Zhang, Minyan, Ninokata, Hisashi

Journal:

Nuclear Technology

Year:

2001

Language:

english

File:

PDF, 4.04 MB

english, 2001

44

Foreword: Selected papers from the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17)

Yang, Bao-Wen, Ninokata, Hisashi, Hassan, Yassin, Cheung, Fan-Bill

Journal:

Nuclear Technology

Year:

2019

File:

PDF, 360 KB

2019

45

The pumping performances of the turbomolecular pump simulated by Direct Simulation Monte Carlo method [Progress in Nuclear Energy 47 (2005) 664–671]

Sheng Wang, Hisashi Ninokata

Journal:

Progress in Nuclear Energy

Year:

2006

Language:

english

File:

PDF, 43 KB

english, 2006

46

Analysis of fuel pin behavior under slow-ramp type transient overpower condition by using the fuel performance evaluation code ‘FEMAXI-FBR’

Tsuboi, Yasushi, Endo, Hiroshi, Ishizu, Tomoko, Tatewaki, Isao, Saito, Hiroaki, Ninokata, Hisashi

Journal:

Journal of Nuclear Science and Technology

Year:

2012

Language:

english

File:

PDF, 3.55 MB

english, 2012

47

[ASME ASME 2009 Fluids Engineering Division Summer Meeting - Vail, Colorado, USA (August 2–6, 2009)] Volume 1: Symposia, Parts A, B and C - Simulation of Eccentric-Shaft Journal Microbearing by DSMC

Wang, Sheng, Lei, Kangbin, Luo, Xilian, Kase, Kiwamu, Merzari, Elia, Ninokata, Hisashi

Year:

2009

Language:

english

File:

PDF, 544 KB

english, 2009

48

Numerical Simulation of Free-Surface Vortices

Merzari, Elia, Ninokata, Hisashi, Wang, Sheng, Baglietto, Emilio

Journal:

Nuclear Technology

Year:

2009

Language:

english

File:

PDF, 633 KB

english, 2009

49

[ASME ASME 2012 Fluids Engineering Division Summer Meeting collocated with the ASME 2012 Heat Transfer Summer Conference and the ASME 2012 10th International Conference on Nanochannels, Microchannels, and Minichannels - Rio Grande, Puerto Rico, USA (Sunday 8 July 2012)] Volume 1: Symposia, Parts A and B - On the Interaction of Boundary Layer and Mixing Layer in Stratified Pipe Flow

Merzari, Elia, Fischer, Paul, Pointer, W. David, Pellegrini, Marco, Ninokata, Hisashi

Year:

2012

Language:

english

File:

PDF, 953 KB

english, 2012

50

Characteristics of fuel melting and relocation in metallic-fueled fast reactor core and its feasibility for eliminating recriticality

Tetsuo Sawada, Hisashi Ninokata, Hideto Taneichi, Hiroshi Endo

Journal:

Progress in Nuclear Energy

Year:

2000

Language:

english

File:

PDF, 573 KB

english, 2000

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