Author Information

Naoaki Akasaka

Affiliation: Japan Nuclear Cycle Development Institute

Division/Department: Fuels and Materials Division, Oarai Engineering Center

Address:
4002 Narita
Oarai, Ibaraki
Japan

Other Names:
N. Akasaka

Publications


Behavior of Irradiated Type 316 Stainless Steels under Low- Strain-Rate Tensile Conditions

STP37564S
Naoaki Akasaka
Japan Nuclear Cycle Development Institute


Behavior of Irradiated Type 316 Stainless Steels under Low-Strain-Rate Tensile Conditions

JAI12346
Naoaki Akasaka
Japan Nuclear Cycle Development Institute


Detection of Radiation-Enhanced Diffusion by Means of Neutron-Irradiated Diffusion Couples of Fe-Cr-Ni System

STP11253S
Naoaki Akasaka
Japan Nuclear Cycle Development Institute


Effect of Irradiation Environment of Fast Reactor's Fuel Elements on Void Swelling in P, Ti-Modified 316 Stainless Steel

STP10549S
Naoaki Akasaka
Japan Nuclear Cycle Development Institute


Effects of Metallurgical Variables on Swelling of Modified 316 and Higher Ni Austenitic Stainless Steels

STP16513S
Naoaki Akasaka
Power Reactor and Nuclear Fuel Development Corporation


Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II

JAI12400
Naoaki Akasaka
Japan Nuclear Cycle Development Institute


Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II

STP37566S
Naoaki Akasaka
Japan Nuclear Cycle Development Institute


Oxide Particle Stability in Oxide Dispersion Strengthened Ferritic Steels During Neutron Irradiation

STP11242S
Naoaki Akasaka
Japan Nuclear Cycle Development Institute


Solute Addition Effect for Fe-15Cr-20Ni Austenitic Steels Irradiated in Joyo

STP11218S
Naoaki Akasaka
Japan Nuclear Cycle Development Institute


Swelling and Microstructural Evolution in 316 Stainless Steel Hexagonal Ducts Following Long-Term Irradiation in EBR-II

STP10547S
Naoaki Akasaka
Japan Nuclear Cycle Development Institute


The Effects of Phase Stability on Void Swelling in P, Ti-Modified 316 Stainless Steels During Neutron Irradiation

STP13905S
Naoaki Akasaka
Power Reactor and Nuclear Fuel Development Corporation


Void Formation and Induced-Segregation During Electron-Irradiation in Ti and Nb Modified Austenitic Steels

STP23983S
N. Akasaka
Power Reactor and Nuclear Fuel Development Corporation


StockCodeTitlePublished AsAffiliationPub Date by Most Viewed
STP37564S Behavior of Irradiated Type 316 Stainless Steels under Low- Strain-Rate Tensile Conditions Naoaki Akasaka Japan Nuclear Cycle Development Institute 01 January 2006
JAI12346 Behavior of Irradiated Type 316 Stainless Steels under Low-Strain-Rate Tensile Conditions Naoaki Akasaka Japan Nuclear Cycle Development Institute 28 February 2005
STP11253S Detection of Radiation-Enhanced Diffusion by Means of Neutron-Irradiated Diffusion Couples of Fe-Cr-Ni System Naoaki Akasaka Japan Nuclear Cycle Development Institute 01 January 2004
STP10549S Effect of Irradiation Environment of Fast Reactor's Fuel Elements on Void Swelling in P, Ti-Modified 316 Stainless Steel Naoaki Akasaka Japan Nuclear Cycle Development Institute 01 January 2001
STP16513S Effects of Metallurgical Variables on Swelling of Modified 316 and Higher Ni Austenitic Stainless Steels Naoaki Akasaka Power Reactor and Nuclear Fuel Development Corporation 01 January 1996
JAI12400 Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II Naoaki Akasaka Japan Nuclear Cycle Development Institute 28 December 2005
STP37566S Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II Naoaki Akasaka Japan Nuclear Cycle Development Institute 01 January 2006
STP11242S Oxide Particle Stability in Oxide Dispersion Strengthened Ferritic Steels During Neutron Irradiation Naoaki Akasaka Japan Nuclear Cycle Development Institute 01 January 2004
STP11218S Solute Addition Effect for Fe-15Cr-20Ni Austenitic Steels Irradiated in Joyo Naoaki Akasaka Japan Nuclear Cycle Development Institute 01 January 2004
STP10547S Swelling and Microstructural Evolution in 316 Stainless Steel Hexagonal Ducts Following Long-Term Irradiation in EBR-II Naoaki Akasaka Japan Nuclear Cycle Development Institute 01 January 2001
STP13905S The Effects of Phase Stability on Void Swelling in P, Ti-Modified 316 Stainless Steels During Neutron Irradiation Naoaki Akasaka Power Reactor and Nuclear Fuel Development Corporation 01 January 1999
STP23983S Void Formation and Induced-Segregation During Electron-Irradiation in Ti and Nb Modified Austenitic Steels N. Akasaka Power Reactor and Nuclear Fuel Development Corporation 01 January 1994