H. Ninokata : rechercher sur 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

Année:

2012

Langue:

english

Fichier:

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:

Année:

2016

Langue:

english

Fichier:

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

Année:

2013

Langue:

english

Fichier:

PDF, 813 KB

english, 2013

4

Distributed resistance modeling of wire-wrapped rod bundles

Hisashi Ninokata, Apostolos Efthimiadis, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

1987

Langue:

english

Fichier:

PDF, 657 KB

english, 1987

5

Investigation of turbulence modelling in thermal stratification analysis

Toshiharu Muramatsu, Hisashi Ninokata

Journal:

Nuclear Engineering and Design

Année:

1994

Langue:

english

Fichier:

PDF, 1.04 MB

english, 1994

6

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

Année:

1995

Langue:

english

Fichier:

PDF, 1.12 MB

english, 1995

7

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

Vyacheslav G. Zimin, Hisashi Ninokata

Journal:

Annals of Nuclear Energy

Année:

1996

Langue:

english

Fichier:

PDF, 1.34 MB

english, 1996

8

A turbulence model study for simulating flow inside tight lattice rod bundles

E. Baglietto, H. Ninokata

Journal:

Nuclear Engineering and Design

Année:

2005

Langue:

english

Fichier:

PDF, 512 KB

english, 2005

9

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

Junichi Kaneko, Akihiko Minato, Hisashi Ninokata

Journal:

Progress in Nuclear Energy

Année:

2005

Langue:

english

Fichier:

PDF, 478 KB

english, 2005

10

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

Alexandre Netchaev, Hiroshi Endo, Tetsuo Sawada, Hisashi Ninokata

Journal:

Annals of Nuclear Energy

Année:

2001

Langue:

english

Fichier:

PDF, 1.18 MB

english, 2001

11

Safety characteristics of the multipurpose fast reactor (MPFR)

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

Journal:

Annals of Nuclear Energy

Année:

2001

Langue:

english

Fichier:

PDF, 944 KB

english, 2001

12

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

Année:

2002

Langue:

english

Fichier:

PDF, 244 KB

english, 2002

13

Double-strata high burnup fuel performance in light water reactors

Vladimir Barchevtsev, Vladimir Artisyuk, Hisashi Ninokata

Journal:

Annals of Nuclear Energy

Année:

2002

Langue:

english

Fichier:

PDF, 363 KB

english, 2002

14

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

Vyacheslav G. Zimin, Hisashi Ninokata

Journal:

Annals of Nuclear Energy

Année:

1998

Langue:

english

Fichier:

PDF, 1.13 MB

english, 1998

15

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

Année:

1998

Langue:

english

Fichier:

PDF, 663 KB

english, 1998

16

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

Année:

2008

Langue:

english

Fichier:

PDF, 607 KB

english, 2008

17

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

Ninokata, Vladimir Kriventsev, Hisashi

Journal:

Numerical Heat Transfer Part B Fundamentals

Année:

1999

Langue:

english

Fichier:

PDF, 387 KB

english, 1999

18

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

Année:

2008

Langue:

english

Fichier:

PDF, 1.93 MB

english, 2008

19

Working Group on Advanced Nuclear Reactors Thermal Hydraulics

Journal:

Journal of Hydraulic Research

Année:

1997

Langue:

english

Fichier:

PDF, 615 KB

english, 1997

20

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

Ninokata, Hisashi

Journal:

Journal of Nuclear Science and Technology

Année:

2015

Langue:

english

Fichier:

PDF, 341 KB

english, 2015

21

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

Année:

2016

Langue:

english

Fichier:

PDF, 1.62 MB

english, 2016

22

Development of Analytical Method for Thermal Striping Phenomena.

MURAMATSU, Toshiharu, NINOKATA, Hisashi

Journal:

TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series B

Année:

1991

Fichier:

PDF, 764 KB

1991

23

[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

Année:

2011

Langue:

english

Fichier:

PDF, 1.06 MB

english, 2011

24

Effect of 17-allylamino-17-demethoxygeldanamycin (17-AAG) on Akt protein expression is more effective in head and neck cancer cell lineages that retain PTEN protein expression

Pontes, Flávia Sirotheau Corrêa, Pontes, Hélder Antônio Rebelo, de Souza, Lucas Lacerda, de Jesus, Adriana Souza, Joaquim, Andrea Maia Correa, Miyahara, Ligia Akiko Ninokata, Fonseca, Felipe Paiva, Pi

Journal:

Journal of Oral Pathology & Medicine

Année:

2018

Langue:

english

Fichier:

PDF, 581 KB

english, 2018

25

[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

Année:

2009

Langue:

english

Fichier:

PDF, 553 KB

english, 2009

26

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

Année:

1992

Langue:

english

Fichier:

PDF, 4.91 MB

english, 1992

27

Development of Thermohydraulics Computer Programs for Thermal Striping Phenomena

Muramatsu, Toshiharu, Ninokata, Hisashi

Journal:

Nuclear Technology

Année:

1996

Langue:

english

Fichier:

PDF, 13.34 MB

english, 1996

28

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

Année:

1992

Fichier:

PDF, 1.09 MB

1992

29

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

Année:

1994

Langue:

english

Fichier:

PDF, 11.09 MB

english, 1994

30

CASE REPORT: KAPOSI SARCOMA IN AN HIV-POSITIVE PATIENT

LAMARCK, RACHEL, COSTA, ANDERSON MAURICIO PAIVA E, DE BRITO SILVA, RAIRA, BRGLAH, SAMEH, MIYAHARA, LIGIA AKIKO NINOKATA, GONÇALVES, PRISCILLA FLORES SILVA, PONTES, DR. HÉLDER ANTÔNIO REBELO

Journal:

Oral Surgery Oral Medicine Oral Pathology and Oral Radiology

Année:

2020

Fichier:

PDF, 36 KB

2020

31

Adaptive control system using the fuzzy theory for transient multi-dimensional thermohydraulics calculations

Toshiharu Muramatsu, Hisashi Ninokata

Journal:

International Journal for Numerical Methods in Engineering

Année:

1994

Langue:

english

Fichier:

PDF, 897 KB

english, 1994

32

Analysis of low-heat-flux sodium boiling test in a 37-pin bundle by the two-fluid model computer code SABENA

Journal:

Nuclear Engineering and Design

Année:

1986

Langue:

english

Fichier:

PDF, 1.01 MB

english, 1986

33

Sabena: Subassembly boiling evolution numerical analysis

Hisashi Ninokata, Taka-aki Okano

Journal:

Nuclear Engineering and Design

Année:

1990

Langue:

english

Fichier:

PDF, 1.13 MB

english, 1990

34

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

Année:

1990

Langue:

english

Fichier:

PDF, 1.14 MB

english, 1990

35

A study on recriticality characteristics of fast reactors in pursuit of recriticality-accident-free concepts

H Ninokata, T Sawada, H Tomozoe, H Endo, A Shimizu

Journal:

Progress in Nuclear Energy

Année:

1995

Langue:

english

Fichier:

PDF, 515 KB

english, 1995

36

The design and safety features of the IRIS reactor

Mario D. Carelli, L.E. Conway, L. Oriani, B. Petrović, C.V. Lombardi, M.E. Ricotti, A.C.O. Barroso, J.M. Collado, L. Cinotti, N.E. Todreas, D. Grgić, M.M. Moraes, R.D. Boroughs, H. Ninokata, D.T. Inge

Journal:

Nuclear Engineering and Design

Année:

2004

Langue:

english

Fichier:

PDF, 557 KB

english, 2004

37

A modified equilibrium void distribution model applicable to subchannel-scale vapor–liquid cross flow model for conventional square and tight lattice BWR fuel bundles

Akitoshi Hotta, Hiroshi Shirai, Mie Azuma, Michio Sadatomi, Akimaro Kawahara, Hisashi Ninokata

Journal:

Nuclear Engineering and Design

Année:

2005

Langue:

english

Fichier:

PDF, 1.02 MB

english, 2005

38

CFD and DNS methodologies development for fuel bundle simulations

E. Baglietto, H. Ninokata, Takeharu Misawa

Journal:

Nuclear Engineering and Design

Année:

2006

Langue:

english

Fichier:

PDF, 627 KB

english, 2006

39

Investigation of ALPHA experiment by severe accident analysis code SAMPSON

Emilio Baglietto, Hisashi Ninokata, Masanori Naitoh

Journal:

Nuclear Engineering and Design

Année:

2008

Langue:

english

Fichier:

PDF, 1.19 MB

english, 2008

40

Numerical simulation of flows in tight-lattice fuel bundles

E. Merzari, H. Ninokata, E. Baglietto

Journal:

Nuclear Engineering and Design

Année:

2008

Langue:

english

Fichier:

PDF, 2.67 MB

english, 2008

41

Corrigendum to “Numerical simulation of flows in tight-lattice fuel bundles” [Nuclear Engineering and Design 238 (2008) 1703–1719]

E. Merzari, H. Ninokata, E. Baglietto

Journal:

Nuclear Engineering and Design

Année:

2009

Langue:

english

Fichier:

PDF, 70 KB

english, 2009

42

Analysis of low Reynolds number turbulent flow phenomena in nuclear fuel pin subassemblies of tight lattice configuration

H. Ninokata, E. Merzari, A. Khakim

Journal:

Nuclear Engineering and Design

Année:

2009

Langue:

english

Fichier:

PDF, 3.17 MB

english, 2009

43

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

Année:

2011

Langue:

english

Fichier:

PDF, 1.19 MB

english, 2011

44

A numerical study on turbulence attenuation model for liquid droplet impingement erosion

Rui Li, Marco Pellegrini, Hisashi Ninokata, Michitsugu Mori

Journal:

Annals of Nuclear Energy

Année:

2011

Langue:

english

Fichier:

PDF, 658 KB

english, 2011

45

A study on reactivity insertion controlled LMR cores with metallic fuel

Tsugio Yokoyama, Takashi Fujiki, Hiroshi Endo, Hisashi Ninokata

Journal:

Progress in Nuclear Energy

Année:

2005

Langue:

english

Fichier:

PDF, 448 KB

english, 2005

46

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

Sheng Wang, Hisashi Ninokata

Journal:

Progress in Nuclear Energy

Année:

2005

Langue:

english

Fichier:

PDF, 907 KB

english, 2005

47

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

Azizul Khakim, Hisashi Ninokata

Journal:

Progress in Nuclear Energy

Année:

2011

Langue:

english

Fichier:

PDF, 2.68 MB

english, 2011

48

Risk-informed design of IRIS using a level-1 probabilistic risk assessment from its conceptual design phase

Yuko Mizuno, Hisashi Ninokata, David J. Finnicum

Journal:

Reliability Engineering & System Safety

Année:

2005

Langue:

english

Fichier:

PDF, 255 KB

english, 2005

49

Numerical study of a single blade row in turbomolecular pump

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

Journal:

Année:

2009

Langue:

english

Fichier:

PDF, 2.32 MB

english, 2009

50

An effective finite-difference scheme for problems of turbulent heat and mass transfer

V. Kriventsev, H. Ninokata

Journal:

Nuclear Engineering and Design

Année:

2000

Langue:

english

Fichier:

PDF, 199 KB

english, 2000