• 594 引用
  • 11 h指数
20032019
Pureに変更を加えた場合、すぐここに表示されます。

研究成果 2003 2019

  • 594 引用
  • 11 h指数
  • 31 Article
  • 22 Conference contribution
  • 2 Conference article
  • 1 Book
2019

Ablation analysis with MPS for proposing ex-vessel corium spreading management in light water reactors

Katta, M., Duan, G., Yamaji, A. & Furuya, M., 2019 5 18, Proceedings of the 27th International Conference on Nuclear Engineering, ICONE 2019 - "Nuclear Power Saves the World!". American Society of Mechanical Engineers (ASME), (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 2019-May).

研究成果: Conference contribution

Light water reactors
Ablation
Accidents
Debris
Liquids
2 引用 (Scopus)
viscous fluids
crusts
viscosity
Viscosity
crust
2 引用 (Scopus)

Density and viscosity of liquid ZrO2 measured by aerodynamic levitation technique

Kondo, T., Muta, H., Kurosaki, K., Kargl, F., Yamaji, A., Furuya, M. & Ohishi, Y., 2019 7 1, : : Heliyon. 5, 7, e02049.

研究成果: Article

公開
levitation
aerodynamics
viscosity
liquids
melting points

Improving breeding performance of Super FR with fuel shuffling in multi-axial layers

Sukarman, Noda, S., Fukuda, T. & Yamaji, A., 2019 12 15, : : Nuclear Engineering and Design. 355, 110323.

研究成果: Article

blankets
breeding
Coolants
outlets
temperature
Reactor cores
Nuclear power plants
Sensitivity analysis
Water injection
Accidents
Stabilization
Error analysis
Random errors
Oil spills
Interpolation
2018

A core design of innovative breeder BWR

Rui, G., Yamaji, A., Cai, Y. & Peng, X., 2018 1 1, Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I and C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs. American Society of Mechanical Engineers (ASME), 巻 1.

研究成果: Conference contribution

Cooling water
Neutrons
Atoms
Hydrogen
Heavy metals
10 引用 (Scopus)
Particle interactions
Semi-implicit
Implicit Method
Interaction
Multiphase flow
1 引用 (Scopus)
breeder reactors
pressurized water reactors
Breeder reactors
blankets
Pressurized water reactors
1 引用 (Scopus)

Core design study of super FBR with multi-axial fuel shuffling and different coolant density

Noda, S., Sukarman, S., Yamaji, A., Takei, T., Fukuda, T. & Ayukawa, A., 2018 1 1, Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues. American Society of Mechanical Engineers (ASME), 巻 5.

研究成果: Conference contribution

Coolants
Mixed oxide fuels
Breeder reactors
Neutron flux
Uranium
1 引用 (Scopus)
supercritical pressures
light water
Fast reactors
reactors
Water

Preliminary core and fuel design of bwr with multi-Axial fuel shuffling

Tasaki, Y. & Yamaji, A., 2018 1 1, Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018. American Nuclear Society, p. 1144-1152 9 p.

研究成果: Conference contribution

Water cooled reactors
Boiling water reactors
Uranium
Swelling
Thermal conductivity
Molten materials
Concretes
Ablation
Liquids
Accidents
2017

A core design of breeding BWR

Guo, R., Yamaji, A., Qin, X., Ji, W., Jiang, Z., Wang, S. & Cai, Y., 2017 1 1, : : Transactions of the American Nuclear Society. 117, p. 1513-1516 4 p.

研究成果: Conference article

1 引用 (Scopus)

Conceptual core design of breeding BWR

Guo, R. & Yamaji, A., 2017, Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. American Society of Mechanical Engineers (ASME), 巻 5.

研究成果: Conference contribution

Neutrons
Cooling water
Coolants
Water
Water cooled reactors
3 引用 (Scopus)

Flexible core design of Super FBR with multi-axial fuel shuffling

Noda, S., Someya, T. & Yamaji, A., 2017 12 1, : : Nuclear Engineering and Design. 324, p. 45-53 9 p.

研究成果: Article

enthalpy
Enthalpy
breeding
Water
cooling water

Investigation on accident progression and melt behavior at the fukushima daiichi units 1 & 2 using melcor code

Li, G., Zheng, S., Yamaji, A., Chong, D. & Yan, J., 2017, Thermal-Hydraulics. American Society of Mechanical Engineers (ASME), 巻 6.

研究成果: Conference contribution

Debris
Accidents
Thermal stratification
Pressure vessels
4 引用 (Scopus)
Substrates
Containment vessels
Viscosity
Light water reactors
Incompressible flow

Investigation to reduce mass of a ultra-light solid reactor for electricity supply in environments without human maintenance

Akie, H., Yamaji, A., Kugo, T., Iwamura, T. & Suyama, K., 2017 1 1, 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings. International Congress on Advances in Nuclear Power Plants, ICAPP

研究成果: Conference contribution

Neutrons
Electricity
Uranium
Space probes
Actinides
9 引用 (Scopus)

Numerical analysis of the melt behavior in a fuel support piece of the BWR by MPS

Chen, R., Chen, L., Guo, K., Yamaji, A., Furuya, M., Tian, W., Su, G. H. & Qiu, S., 2017 4 1, : : Annals of Nuclear Energy. 102, p. 422-439 18 p.

研究成果: Article

Boiling water reactors
Numerical analysis
Stainless steel
Ablation
Solidification

Preliminary study on flexible core design of super FBR with multi-axial fuel shuffling

Sukarman, Yamaji, A., Someya, T. & Noda, S., 2017 1 1, 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings. International Congress on Advances in Nuclear Power Plants, ICAPP

研究成果: Conference contribution

Coolants
Enthalpy
Hydraulics
Mixed oxide fuels
Water cooled reactors

Sensitivity study of accident scenarios on MCCI for Fukushima Daiichi unit-1 by MELCOR

Noju, T., Yamaji, A., Matsumoto, K. & Li, X., 2017 1 1, 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings. International Congress on Advances in Nuclear Power Plants, ICAPP

研究成果: Conference contribution

Molten materials
Accidents
Concretes
Ablation
Water injection
5 引用 (Scopus)
Molten materials
Concretes
ablation
Ablation
interactions
2016
15 引用 (Scopus)
Ablation
ablation
Molten materials
Concretes
Limestone
7 引用 (Scopus)
supercritical pressures
light water
Fast reactors
reactors
breeding
3 引用 (Scopus)
accidents
interactions
ablation
containment
crusts
1 引用 (Scopus)

Melting Penetration Simulation of Fe-U System at High Temperature Using MPS-LER

Mustari, A. P. A., Yamaji, A. & Irwanto, D., 2016 9 23, : : Journal of Physics: Conference Series. 739, 1, 012016.

研究成果: Article

penetration
melting
Transient Reactor Test Facility
simulation
nuclear power plants
2015
1 引用 (Scopus)
supercritical pressures
light water
Fast reactors
accidents
accident

Analysis of metal vessel wall ablation experiment with high temperature liquid by MPS method

Masumura, D., Oka, Y., Yamaji, A. & Furuya, M., 2015, International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, 巻 9. p. 7401-7413 13 p.

研究成果: Conference contribution

Ablation
ablation
vessels
Liquids
liquids
7 引用 (Scopus)

Multi-physics and multi-scale benchmarking and uncertainty quantification within OECD/NEA framework

Avramova, M., Ivanov, K., Kozlowski, T., Pasichnyk, I., Zwermann, W., Velkov, K., Royer, E., Yamaji, A. & Gulliford, J., 2015 7 28, : : Annals of Nuclear Energy. 84, p. 178-196 19 p.

研究成果: Article

Benchmarking
Light water reactors
Nuclear energy
Physics
Economics

Numerical simulation of anisotropic ablation of siliceous concrete - Analysis of CCI-3 MCCI experiment by MPS method

Li, X. & Yamaji, A., 2015, International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, 巻 9. p. 7358-7371 14 p.

研究成果: Conference contribution

Ablation
ablation
Molten materials
Concretes
Computer simulation

Sensitivity study of 1F1 type accident by MELCOR code

Saito, K. & Yamaji, A., 2015 1 1, : : Transactions of the American Nuclear Society. 113, p. 1411-1414 4 p.

研究成果: Conference article

Accidents
2012
6 引用 (Scopus)

Design study to increase plutonium conversion ratio of hc-flwr core

Yamaji, A., Nakano, Y., Uchikawa, S. & Okubo, T., 2012 9, : : Nuclear Technology. 179, 3, p. 309-322 14 p.

研究成果: Article

plutonium
Plutonium
Mixed oxide fuels
reactors
mixed oxides
1 引用 (Scopus)

Development of IDAT: IRPhE database and analysis tool

Hill, I., Gulliford, J., Soppera, N., Bossant, M. & Yamaji, A., 2012, Transactions of the American Nuclear Society. 巻 106. p. 805-807 3 p.

研究成果: Conference contribution

2010
114 引用 (Scopus)
Water cooled reactors
Light water reactors
Fast reactors
Nuclear energy
Nuclear engineering
2 引用 (Scopus)

The impact of americium target in-core loading on reactivity characteristics and ULOF response of sodium-cooled MOX FBR

Yamaji, A., Kawashima, K., Ohm, S., Mizuno, T. & Okubo, T., 2010 8, : : Nuclear Technology. 171, 2, p. 142-152 11 p.

研究成果: Article

breeder reactors
Americium
americium
Breeder reactors
reactivity
2009
3 引用 (Scopus)

Design study of nuclear power systems for deep space explorers (1) criticality of low enriched uranium fueled core

Kugo, T., Akie, H., Yamaji, A., Nabeshima, K., Iwamura, T. & Akikmoto, H., 2009, International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009. Atomic Energy Society of Japan, 巻 3. p. 2487-2494 8 p.

研究成果: Conference contribution

Criticality (nuclear fission)
Moderators
Beryllium
Hydrides
Nuclear energy
1 引用 (Scopus)

Design study of nuclear power systems for deep space explorers (2) electricity supply capabilities of solid cores

Yamaji, A., Takizuka, T., Nabeshima, K., Iwamura, T. & Akimoto, H., 2009, International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009. Atomic Energy Society of Japan, 巻 3. p. 2495-2502 8 p.

研究成果: Conference contribution

Heat pipes
Nuclear energy
Electricity
Cooling
Radiators

Evaluation of uncertainties in FEMAXI-6 calculations for predicting MOX fuel behaviors in FLWR design

Yamaji, A., Suzuki, M. & Okubo, T., 2009, International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009. Atomic Energy Society of Japan, 巻 1. p. 49-57 9 p.

研究成果: Conference contribution

Boiling water reactors
Relocation
Plutonium
Gases
Densification
2 引用 (Scopus)

FEMAXI-6 code verification with MOX fuels irradiated in Halden reactor

Yamaji, A., Suzuki, M. & Okubo, T., 2009 12, : : Journal of Nuclear Science and Technology. 46, 12, p. 1152-1161 10 p.

研究成果: Article

Halden Boiling Water Reactor
rods
light water reactors
relocation
Light water reactors
2007

Core design of the super LWR

Yamaji, A., 2007, : : Atomos. 49, 9, p. 607-612 6 p.

研究成果: Article

2006

Development of statistical thermal design procedure to evaluate engineering uncertainty of super lwr

Yang, J., Oka, Y., Liu, J., Ishiwatari, Y. & Yamaji, A., 2006, : : Journal of Nuclear Science and Technology. 43, 1, p. 32-42 11 p.

研究成果: Article

supercritical pressures
light water reactors
Light water reactors
engineering
nuclear reactors
13 引用 (Scopus)

Development of statistical thermal design procedure to evaluate engineering uncertainty of Super LWR

Yang, J., Oka, Y., Liu, J., Ishiwatari, Y. & Yamaji, A., 2006 1, : : Journal of Nuclear Science and Technology. 43, 1, p. 32-42 11 p.

研究成果: Article

supercritical pressures
light water reactors
Light water reactors
engineering
nuclear reactors
62 引用 (Scopus)

Fuel and core design of super light water reactor with low leakage fuel loading pattern

Kamei, K., Yamaji, A., Ishiwatari, Y., Oka, Y. & Liu, J., 2006, : : Journal of Nuclear Science and Technology. 43, 2, p. 129-139 11 p.

研究成果: Article

light water reactors
Light water reactors
leakage
rods
heat transfer

Fuel and core design of super light water reactor with low leakage fuel loading pattern

Kamei, K., Yamaji, A., Ishiwatari, Y., Oka, Y. & Liu, J., 2006, : : Journal of Nuclear Science and Technology. 43, 2, p. 129-139 11 p.

研究成果: Article

light water reactors
Light water reactors
leakage
rods
heat transfer
11 引用 (Scopus)

Principle of rationalizing the criteria for abnormal transients of the Super LWR with fuel rod analyses

Yamaji, A., Oka, Y., Ishiwatari, Y., Liu, J. & Suzuki, M., 2006 8, : : Annals of Nuclear Energy. 33, 11-12, p. 984-993 10 p.

研究成果: Article

Light water reactors
water
reactor
buckling
Buckling
2005
21 引用 (Scopus)

Fuel and core design of super LWR with stainless steel cladding

Kamei, K., Yamaji, A., Ishiwatari, Y., Jie, L. & Oka, Y., 2005, Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05. 巻 5. p. 2711-2720 10 p.

研究成果: Conference contribution

Stainless steel
Heat transfer
Coolants
Temperature
Light water reactors
80 引用 (Scopus)

Improved core design of the high temperature supercritical-pressure light water reactor

Yamaji, A., Kamei, K., Oka, Y. & Koshizuka, S., 2005 5, : : Annals of Nuclear Energy. 32, 7, p. 651-670 20 p.

研究成果: Article

Light water reactors
Coolants
water
Temperature
temperature
3 引用 (Scopus)

Rationalization of the fuel integrity and transient criteria for the super LWR

Yamaji, A., Oka, Y., Ishiwatari, Y., Jie, L., Koshizuka, S. & Suzuki, M., 2005, Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05. 巻 5. p. 2751-2758 8 p.

研究成果: Conference contribution

Light water reactors
Nuclear energy
Buckling
Melting point
Stainless steel
35 引用 (Scopus)

Safety of super LWR, (I) safety system design

Ishiwatari, Y., Oka, Y., Koshizuka, S., Yamaji, A. & Liu, J., 2005 11, : : Journal of Nuclear Science and Technology. 42, 11, p. 927-934 8 p.

研究成果: Article

light water reactors
Light water reactors
coolants
Security systems
systems engineering