• 646 引用
  • 12 h指数
20032019

年単位の研究成果

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

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

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

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

1 引用 (Scopus)

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. (Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018).

研究成果: Conference contribution

Three-dimensional numerical study on pool stratification behavior in molten corium-concrete interaction (MCCI) with MPS method

Li, X., Sato, I., Yamaji, A. & Duan, G., 2018 1 1, Thermal-Hydraulics and Safety Analyses. American Society of Mechanical Engineers (ASME), 巻 6B.

研究成果: Conference contribution

2017

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

1 引用 (Scopus)

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

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

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

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

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

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

2009

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 1 1, International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009. Atomic Energy Society of Japan, p. 2487-2494 8 p. (International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009; 巻数 3).

研究成果: Conference contribution

3 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 1 1, International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009. Atomic Energy Society of Japan, p. 2495-2502 8 p. (International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009; 巻数 3).

研究成果: Conference contribution

1 引用 (Scopus)

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

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

研究成果: Conference contribution

2004

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

Yamaji, A., Kamei, K., Oka, Y. & Koshizuka, S., 2004 12 1, Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04. p. 509-517 9 p. (Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04).

研究成果: Conference contribution

6 引用 (Scopus)
2003

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

4 引用 (Scopus)

High temperature LWR operationg at supercritical pressure

Oka, Y., Koshizuka, S., Ishiwatari, Y., Yamaji, A. & Yi, T. T., 2003 12 1, Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy. p. 1128-1135 8 p. (Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy).

研究成果: Conference contribution

12 引用 (Scopus)

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

Yamaji, A., Oka, Y. & Koshizuka, S., 2003 12 1, Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy. p. 1763-1771 9 p. (Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy).

研究成果: Conference contribution

17 引用 (Scopus)