中込 良廣

Simulataneous Measurement of Prompt Neutrons and Fission Fragments for 239PU(nth.f) 

Journal of Nuclear Science and Technology 37(11) 941-948 2000年  

Resumption of Transport of KUR Spent Fuel from Japan to USA 

Proceedings of the 22nd International Meeting on Reduced Enrichment for Research and Test Reactors(RERTR) 1999年  

A system for correlation measurement of fission fragments and prompt neutrons for thermal neutron induced fission 

Nuclear Instruments&Methods in Physics Research 385(1) 171-178 1997年  

Spent Fuel Storage at KURRI 

Proceedings of the (]G0010[)(]G0008[)International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) 1996年  

Measurement of Fragment Mass Dependent Kinetic Energy and Neutron Multiplicity for Thermal Neutron Induced Fission of Plutonium-239 

Journal of Nuclear Science and Technology 32(5) 404-414 1995年  

臨界安全と燃焼度クレジット -燃焼度クレジット概念の輸送への適用- 

原子力工業 40(3) 30 1994年  

Criticality Safety and Burn-up Credit -Application of Burn-up Credit Concept to Nuclear Material Transportation- 

Nuclear Engineering 40(3) 30 1994年  

電子線ライナックと鉛スペクトロメータを組み合わせた装置を用いた共鳴領域におけるネプッニウム-237の核分裂断面積の測定 

30(9) 863-869 1993年  

Measurement of Fission Cross Section of Neptunium-237 in Resonance Region with Electron Linac-Driven Lead Spectrometer 

Journal of Nuclear Science and Technology 30(9) 863-869 1993年  

Multi-Mode Fission of ²³³U and ²³⁵U Induced by Thermal Neutrons 

Annual Report of Osaka Univ. Laboratory of Nuclear Studies 1991年  

Measurement of U(m*)by Fragment Double-Velocity Double. Energy Method 

Proceedings of International Conference : 50y with Nucl Fission 1989年  

Response Characteristics of Thin Film Detectors to Fission Fragments 

Nuclear Instruments and Methods A251 1986年  

A New Model of Luminescence Production in a Very Thin Plastic Scintillator Film 

Nuclear Instruments and Methods A244 1986年