• 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
フィルター
Conference contribution
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
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
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

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
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

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

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

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
2015

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

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
2012
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

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
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
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
2004
6 引用 (Scopus)

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

Yamaji, A., Kamei, K., Oka, Y. & Koshizuka, S., 2004, Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04. p. 509-517 9 p.

研究成果: Conference contribution

Light water reactors
Coolants
Temperature
Orifices
Power generation
2003
4 引用 (Scopus)

Conceptual design of high temperature reactors cooled by supercritical light water

Oka, Y., Koshizuka, S., Ishiwatari, Y. & Yamaji, A., 2003, 2003 International Congress on Advances in Nuclear Power Plants - Proceedings of ICAPP 2003. American Nuclear Society

研究成果: Conference contribution

High temperature reactors
Conceptual design
Coolants
Water
water
12 引用 (Scopus)

High temperature LWR operationg at supercritical pressure

Oka, Y., Koshizuka, S., Ishiwatari, Y., Yamaji, A. & Yi, T. T., 2003, Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy. p. 1128-1135 8 p.

研究成果: Conference contribution

Plant startup
Hydrogen production
Conceptual design
Boilers
Innovation
16 引用 (Scopus)

Three-dimensional core design of SCLWR-H with neutronic and thermal-hydraulic coupling

Yamaji, A., Oka, Y. & Koshizuka, S., 2003, Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy. p. 1763-1771 9 p.

研究成果: Conference contribution

Hydraulic equipment
Control rods
Coolants
Temperature distribution
Flow rate