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Study on the mechanism of diametral cladding strain and mixed-oxide fuel element breaching in slow-ramp extended overpower transients

Journal of nuclear materials, 2012-10, Vol.429 (1-3), p.149-158

2012

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Development of a mixed oxide fuel pin performance analysis code “CEDAR”: Models and analyses of fuel pin irradiation behavior

Nuclear engineering and design, 2014-12, Vol.280, p.27-36

2014

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Effect of Precise Control of V/III Ratio on In-Rich InGaN Epitaxial Growth

Japanese Journal of Applied Physics, 2006-12, Vol.45 (12L), p.L1259

2006

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A Design Study of High Breeding Ratio Sodium Cooled Metal Fuel Core without Blanket Fuels

Journal of Power and Energy Systems, 2009, Vol.3(1), pp.126-135

2009

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Fabrication and properties of coherent-structure In-polarity InN∕In0.7Ga0.3N multiquantum wells emitting at around 1.55μm

Journal of applied physics, 2007-10, Vol.102 (8)

2007

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Thermal conductivity of cesium molybdate Cs2MoO4

Journal of nuclear materials, 1996-08, Vol.231 (3), p.242-244

1996

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An investigation of the thermal conductivity of Cs2 Mo04

Journal of nuclear materials, 1997-08, Vol.247, p.82-85

1997

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Irradiation performance of fast reactor MOX fuel pins with ferritic/martensitic cladding irradiated to high burnups

Journal of nuclear materials, 2011-05, Vol.412 (3), p.294-300

2011

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Minor Actinide-Bearing Oxide Fuel Core Design Study for the JSFR

Nuclear technology, 2010-04, Vol.170 (1), p.170-180

2010

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Correlations among FBR core characteristics for various fuel compositions

Journal of nuclear science and technology, 2012-06, Vol.49 (6), p.640-654

2012

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Evaluation of Creep Damage and Diametral Strain of Fast Reactor MOX Fuel Pins Irradiated to High Burnups

Journal of nuclear science and technology, 2010-08, Vol.47 (8), p.712

2010

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MINOR ACTINIDE-BEARING OXIDE FUEL CORE DESIGN STUDY FOR THE JSFR: SPECIAL ISSUE ON THE 2008 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS

Nuclear technology, 2010, Vol.170 (1), p.170-180

2010

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Advanced MOX Core Design Study of Sodium-Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan

Nuclear technology, 2004-05, Vol.146 (2), p.155-163

2004

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Fabrication and properties of coherent-structure In-polarity In N ∕ In 0.7 Ga 0.3 N multiquantum wells emitting at around 1.55 μ m

Journal of applied physics, 2007-10, Vol.102 (8), p.083539-083539-6

2007

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Tensile properties of 11Cr-0.5Mo-2W, V, Nb stainless steel in LMFBR environment

Journal of nuclear science and technology, 2000-09, Vol.37 (9), p.780-786

2000

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The Impact of Americium Target In-Core Loading on Reactivity Characteristics and ULOF Response of Sodium-Cooled MOX FBR

Nuclear technology, 2010-08, Vol.171 (2), p.142-152

2010

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Evaluation of Creep Damage and Diametral Strain of Fast Reactor MOX Fuel Pins Irradiated to High Burnups

Journal of nuclear science and technology, 2010-08, Vol.47 (8), p.712-720

2010

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Fabrication and properties of coherent-structure In-polarity InN/In{sub 0.7}Ga{sub 0.3}N multiquantum wells emitting at around 1.55 {mu}m

Journal of applied physics, 2007-10, Vol.102 (8)

2007

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A NEXT GENERATION SODIUM-COOLED FAST REACTOR CONCEPT AND ITS R&D PROGRAM

Nuclear engineering and technology, 2007-06, Vol.39 (3), p.171-186

2007

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Polarity dependence of In-rich InGaN and InN/InGaN MQWs

MRS proceedings, 2005, Vol.892, Article 0892-FF06-03

2005

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An investigation of the thermal conductivity of Cs 2 Mo0 4

Journal of nuclear materials, 1997, Vol.247, p.82-85

1997

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Tensile Properties of llCr-0.5Mo-2W, V, Nb Stainless Steel in LMFBR Environment

Journal of nuclear science and technology, 2000-09, Vol.37 (9), p.780-786

2000

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A Conceptual Design Study of a Small Natural Convection Lead-Bismuth-Cooled Reactor Without Refueling for 30 Years

Nuclear technology, 2006-05, Vol.154 (2), p.142-154

2006

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Thermal conductivity of cesium molybdate Cs 2MoO 4

Journal of nuclear materials, 1996, Vol.231 (3), p.242-244

1996

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ICONE11-36076 SYSTEM ANALYSES FOR LEAD-BISMUTH-COOLED NATURAL CIRCULATION REACTORS

The Proceedings of the International Conference on Nuclear Engineering (ICONE), 2003, Vol.2003, p.144

2003

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Study on the mechanism of diametral cladding strain and mixed-oxide fuel element breaching in slow-ramp extended overpower transients

Development of a mixed oxide fuel pin performance analysis code “CEDAR”: Models and analyses of fuel pin irradiation behavior

Effect of Precise Control of V/III Ratio on In-Rich InGaN Epitaxial Growth

A Design Study of High Breeding Ratio Sodium Cooled Metal Fuel Core without Blanket Fuels

Fabrication and properties of coherent-structure In-polarity InN∕In0.7Ga0.3N multiquantum wells emitting at around 1.55μm

Thermal conductivity of cesium molybdate Cs2MoO4

An investigation of the thermal conductivity of Cs2 Mo04

Irradiation performance of fast reactor MOX fuel pins with ferritic/martensitic cladding irradiated to high burnups

Minor Actinide-Bearing Oxide Fuel Core Design Study for the JSFR

Correlations among FBR core characteristics for various fuel compositions

Evaluation of Creep Damage and Diametral Strain of Fast Reactor MOX Fuel Pins Irradiated to High Burnups

MINOR ACTINIDE-BEARING OXIDE FUEL CORE DESIGN STUDY FOR THE JSFR: SPECIAL ISSUE ON THE 2008 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS

Advanced MOX Core Design Study of Sodium-Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan

Fabrication and properties of coherent-structure In-polarity In N ∕ In 0.7 Ga 0.3 N multiquantum wells emitting at around 1.55 μ m

Tensile properties of 11Cr-0.5Mo-2W, V, Nb stainless steel in LMFBR environment

The Impact of Americium Target In-Core Loading on Reactivity Characteristics and ULOF Response of Sodium-Cooled MOX FBR

Evaluation of Creep Damage and Diametral Strain of Fast Reactor MOX Fuel Pins Irradiated to High Burnups

Fabrication and properties of coherent-structure In-polarity InN/In{sub 0.7}Ga{sub 0.3}N multiquantum wells emitting at around 1.55 {mu}m

A NEXT GENERATION SODIUM-COOLED FAST REACTOR CONCEPT AND ITS R&D PROGRAM

Polarity dependence of In-rich InGaN and InN/InGaN MQWs

An investigation of the thermal conductivity of Cs 2 Mo0 4

Tensile Properties of llCr-0.5Mo-2W, V, Nb Stainless Steel in LMFBR Environment

A Conceptual Design Study of a Small Natural Convection Lead-Bismuth-Cooled Reactor Without Refueling for 30 Years

Thermal conductivity of cesium molybdate Cs 2MoO 4

ICONE11-36076 SYSTEM ANALYSES FOR LEAD-BISMUTH-COOLED NATURAL CIRCULATION REACTORS

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