• 559 Citations
  • 11 h-Index
20032019
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Research Output 2003 2019

  • 559 Citations
  • 11 h-Index
  • 29 Article
  • 21 Conference contribution
  • 2 Conference article
  • 1 Book
2019

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

viscous fluids
crusts
viscosity
Viscosity
crust

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

Reactor cores
Nuclear power plants
Sensitivity analysis
Water injection
Accidents

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

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 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

Cooling water
Neutrons
Atoms
Hydrogen
Heavy metals
4 Citations (Scopus)

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

Particle interactions
Semi-implicit
Implicit Method
Interaction
Multiphase flow

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

breeder reactors
pressurized water reactors
Breeder reactors
blankets
Pressurized water reactors

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

Coolants
Mixed oxide fuels
Breeder reactors
Neutron flux
Uranium

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

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 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

Water cooled reactors
Boiling water reactors
Uranium
Swelling
Thermal conductivity

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

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 Jan 1, In : Transactions of the American Nuclear Society. 117, p. 1513-1516 4 p.

Research output: Contribution to journalConference article

1 Citation (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), Vol. 5.

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

Neutrons
Cooling water
Coolants
Water
Water cooled reactors
2 Citations (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

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), Vol. 6.

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

Debris
Accidents
Thermal stratification
Pressure vessels
2 Citations (Scopus)

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

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 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

Neutrons
Electricity
Uranium
Space probes
Actinides
7 Citations (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 Apr 1, In : Annals of Nuclear Energy. 102, p. 422-439 18 p.

Research output: Contribution to journalArticle

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 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

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 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

Molten materials
Accidents
Concretes
Ablation
Water injection
4 Citations (Scopus)

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

Molten materials
Concretes
ablation
Ablation
interactions
2016
13 Citations (Scopus)

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

Ablation
ablation
Molten materials
Concretes
Limestone
6 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

supercritical pressures
light water
Fast reactors
reactors
breeding
2 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

accidents
interactions
ablation
containment
crusts
1 Citation (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

penetration
melting
Transient Reactor Test Facility
simulation
nuclear power plants
2015
1 Citation (Scopus)

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

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

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

Ablation
ablation
vessels
Liquids
liquids
5 Citations (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 Jul 28, In : Annals of Nuclear Energy. 84, p. 178-196 19 p.

Research output: Contribution to journalArticle

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

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

Ablation
ablation
Molten materials
Concretes
Computer simulation

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

Accidents
2012
6 Citations (Scopus)

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

plutonium
Plutonium
Mixed oxide fuels
reactors
mixed oxides
1 Citation (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. Vol. 106. p. 805-807 3 p.

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

2010
109 Citations (Scopus)

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

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

Research output: Book/ReportBook

Water cooled reactors
Light water reactors
Fast reactors
Nuclear energy
Nuclear engineering
2 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

breeder reactors
Americium
americium
Breeder reactors
reactivity
2009
3 Citations (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, Vol. 3. p. 2487-2494 8 p.

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

Criticality (nuclear fission)
Moderators
Beryllium
Hydrides
Nuclear energy
1 Citation (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, Vol. 3. p. 2495-2502 8 p.

Research output: Chapter in Book/Report/Conference proceedingConference 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, Vol. 1. p. 49-57 9 p.

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

Boiling water reactors
Relocation
Plutonium
Gases
Densification
1 Citation (Scopus)

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

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

Research output: Contribution to journalArticle

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

Core design of the super LWR

Yamaji, A., 2007, 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

supercritical pressures
light water reactors
Light water reactors
engineering
nuclear reactors
13 Citations (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 Jan, In : Journal of Nuclear Science and Technology. 43, 1, p. 32-42 11 p.

Research output: Contribution to journalArticle

supercritical pressures
light water reactors
Light water reactors
engineering
nuclear reactors
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

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

Research output: Contribution to journalArticle

light water reactors
Light water reactors
leakage
rods
heat transfer
10 Citations (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, In : Annals of Nuclear Energy. 33, 11-12, p. 984-993 10 p.

Research output: Contribution to journalArticle

Light water reactors
water
reactor
buckling
Buckling
2005
21 Citations (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. Vol. 5. p. 2711-2720 10 p.

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

Stainless steel
Heat transfer
Coolants
Temperature
Light water reactors
78 Citations (Scopus)

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

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

Research output: Contribution to journalArticle

Light water reactors
Coolants
water
Temperature
temperature
4 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, Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05. Vol. 5. p. 2751-2758 8 p.

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

Light water reactors
Nuclear energy
Buckling
Melting point
Stainless steel
35 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

light water reactors
Light water reactors
coolants
Security systems
systems engineering
48 Citations (Scopus)

Safety of super LWR, (II) safety analysis at supercritical pressure

Ishiwatari, Y., Oka, Y., Koshizuka, S., Yamaji, A. & Liu, J., 2005 Nov, In : Journal of Nuclear Science and Technology. 42, 11, p. 935-948 14 p.

Research output: Contribution to journalArticle

supercritical pressures
water flow
accidents
safety
rods
79 Citations (Scopus)
supercritical pressures
light water reactors
Hydraulic equipment
Light water reactors
hydraulics
2004
6 Citations (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.

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

Light water reactors
Coolants
Temperature
Orifices
Power generation