• 626 Citations
  • 12 h-Index
20032019

Research output per year

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Research Output

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 May 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; vol. 2019-May).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

A novel multiphase MPS algorithm for modeling crust formation by highly viscous fluid for simulating corium spreading

Duan, G., Yamaji, A. & Koshizuka, S., 2019 Mar 1, In : Nuclear Engineering and Design. 343, p. 218-231 14 p.

Research output: Contribution to journalArticle

5 Citations (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 Jul 1, In : Heliyon. 5, 7, e02049.

Research output: Contribution to journalArticle

Open Access
3 Citations (Scopus)

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

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

Research output: Contribution to journalArticle

1 Citation (Scopus)

Sensitivity analysis of in-vessel accident progression behavior in Fukushima Daiichi Nuclear Power Plant Unit 3

Li, X., Sato, I. & Yamaji, A., 2019 Nov 1, In : Annals of Nuclear Energy. 133, p. 21-34 14 p.

Research output: Contribution to journalArticle

The truncation and stabilization error in multiphase moving particle semi-implicit method based on corrective matrix: Which is dominant?

Duan, G., Yamaji, A., Koshizuka, S. & Chen, B., 2019 Aug 15, In : Computers and Fluids. 190, p. 254-273 20 p.

Research output: Contribution to journalArticle

2018

A core design of innovative breeder BWR

Rui, G., Yamaji, A., Cai, Y. & Peng, X., 2018 Jan 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), Vol. 1.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

An accurate and stable multiphase moving particle semi-implicit method based on a corrective matrix for all particle interaction models

Duan, G., Koshizuka, S., Yamaji, A., Chen, B., Li, X. & Tamai, T., 2018 Sep 7, In : International Journal for Numerical Methods in Engineering. 115, 10, p. 1287-1314 28 p.

Research output: Contribution to journalArticle

15 Citations (Scopus)

Core design of PWR-type seed-blanket core breeder reactor with tightly packed fuel assembly

Takei, T. & Yamaji, A., 2018 Jul 1, In : Nuclear Engineering and Design. 333, p. 45-54 10 p.

Research output: Contribution to journalArticle

1 Citation (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 Jan 1, Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues. American Society of Mechanical Engineers (ASME), Vol. 5.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

Improved core design of a high breeding fast reactor cooled by supercritical pressure light water

Someya, T., Yamaji, A. & Sukarman, 2018 Jan 1, In : Journal of Nuclear Engineering and Radiation Science. 4, 1, 021002.

Research output: Contribution to journalArticle

1 Citation (Scopus)

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

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

Research output: Chapter in Book/Report/Conference proceedingConference 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 Jan 1, Thermal-Hydraulics and Safety Analyses. American Society of Mechanical Engineers (ASME), Vol. 6B.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

2017

A core design of breeding BWR

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

Research output: Contribution to journalConference article

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), Vol. 5.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

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

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

Research output: Contribution to journalArticle

4 Citations (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), Vol. 6.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Investigation on influence of crust formation on VULCANO VE-U7 corium spreading with MPS method

Yasumura, Y., Yamaji, A., Furuya, M., Ohishi, Y. & Duan, G., 2017 Sep 1, In : Annals of Nuclear Energy. 107, p. 119-127 9 p.

Research output: Contribution to journalArticle

4 Citations (Scopus)

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 Jan 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

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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 Apr 1, In : Annals of Nuclear Energy. 102, p. 422-439 18 p.

Research output: Contribution to journalArticle

9 Citations (Scopus)

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

Sukarman, Yamaji, A., Someya, T. & Noda, S., 2017 Jan 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

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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

Noju, T., Yamaji, A., Matsumoto, K. & Li, X., 2017 Jan 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

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Three-dimensional numerical study on the mechanism of anisotropic MCCI by improved MPS method

Li, X. & Yamaji, A., 2017 Apr 1, In : Nuclear Engineering and Design. 314, p. 207-216 10 p.

Research output: Contribution to journalArticle

7 Citations (Scopus)
2016

A numerical study of isotropic and anisotropic ablation in MCCI by MPS method

Li, X. & Yamaji, A., 2016 Jul 1, In : Progress in Nuclear Energy. 90, p. 46-57 12 p.

Research output: Contribution to journalArticle

16 Citations (Scopus)

Core design of a high breeding fast reactor cooled by supercritical pressure light water

Someya, T. & Yamaji, A., 2016 Jan 1, In : Nuclear Engineering and Design. 296, p. 30-37 8 p.

Research output: Contribution to journalArticle

8 Citations (Scopus)

Development of MPS Method for Analyzing Melt Spreading Behavior and MCCI in Severe Accidents

Yamaji, A. & Li, X., 2016 Sep 23, In : Journal of Physics: Conference Series. 739, 1, 012002.

Research output: Contribution to journalArticle

4 Citations (Scopus)

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

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

Research output: Contribution to journalArticle

1 Citation (Scopus)
2015

Analysis of accidents and abnormal transients of a high breeding fast reactor cooled by supercritical-pressure light water

Guo, R., Yamaji, A. & Oka, Y., 2015 Dec 15, In : Nuclear Engineering and Design. 295, p. 228-238 11 p.

Research output: Contribution to journalArticle

1 Citation (Scopus)

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, Vol. 9. p. 7401-7413 13 p.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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 Jul 28, In : Annals of Nuclear Energy. 84, p. 178-196 19 p.

Research output: Contribution to journalArticle

7 Citations (Scopus)

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, Vol. 9. p. 7358-7371 14 p.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Sensitivity study of 1F1 type accident by MELCOR code

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

Research output: Contribution to journalConference article

2012

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

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

Research output: Contribution to journalArticle

6 Citations (Scopus)

Development of IDAT: IRPhE database and analysis tool

Hill, I., Gulliford, J., Soppera, N., Bossant, M. & Yamaji, A., 2012 Dec 1, In : Transactions of the American Nuclear Society. 106, p. 805-807 3 p.

Research output: Contribution to journalConference article

1 Citation (Scopus)
2010

Super light water reactors and super fast reactors: Supercritical-pressure light water cooled reactors

Oka, Y., Koshizuka, S., Ishiwatari, Y. & Yamaji, A., 2010 Dec 1, Springer US. 651 p.

Research output: Book/ReportBook

121 Citations (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 Aug, In : Nuclear Technology. 171, 2, p. 142-152 11 p.

Research output: Contribution to journalArticle

2 Citations (Scopus)
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 Jan 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; vol. 3).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

3 Citations (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 Jan 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; vol. 3).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

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

Yamaji, A., Suzuki, M. & Okubo, T., 2009 Jan 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; vol. 1).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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

Yamaji, A., Suzuki, M. & Okubo, T., 2009 Dec 1, In : Journal of Nuclear Science and Technology. 46, 12, p. 1152-1161 10 p.

Research output: Contribution to journalArticle

2 Citations (Scopus)
2007

Core design of the super LWR

Yamaji, A., 2007 Dec 1, In : Atomos. 49, 9, p. 607-612 6 p.

Research output: Contribution to journalArticle

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, In : Journal of Nuclear Science and Technology. 43, 1, p. 32-42 11 p.

Research output: Contribution to journalArticle

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

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

Research output: Contribution to journalArticle

13 Citations (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 Mar 13, In : Journal of Nuclear Science and Technology. 43, 2, p. 129-139 11 p.

Research output: Contribution to journalArticle

62 Citations (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, In : Journal of Nuclear Science and Technology. 43, 2, p. 129-139 11 p.

Research output: Contribution to journalArticle

1 Citation (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 Aug 1, In : Annals of Nuclear Energy. 33, 11-12, p. 984-993 10 p.

Research output: Contribution to journalArticle

11 Citations (Scopus)
2005

Fuel and core design of super LWR with stainless steel cladding

Kamei, K., Yamaji, A., Ishiwatari, Y., Jie, L. & Oka, Y., 2005 Dec 1, p. 2711-2720. 10 p.

Research output: Contribution to conferencePaper

22 Citations (Scopus)

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

Yamaji, A., Kamei, K., Oka, Y. & Koshizuka, S., 2005 May 1, In : Annals of Nuclear Energy. 32, 7, p. 651-670 20 p.

Research output: Contribution to journalArticle

81 Citations (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 Dec 1, p. 2751-2758. 8 p.

Research output: Contribution to conferencePaper

3 Citations (Scopus)

Safety of super LWR, (I) safety system design

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

Research output: Contribution to journalArticle

37 Citations (Scopus)