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Home / Publications / Journals / Nuclear Technology / Volume 136 / Number 2

Volume 136

Number 2

Studies on the Comprehensive Methodology for Structuring Accident Mitigation Systems for Next-Generation Pressurized Water Reactors

Yonezo Tsujikura

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 141-157

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT01-A3234

A Statistical Approach to Predict the Failure Enthalpy and Reliability of Irradiated PWR Fuel Rods During Reactivity-Initiated Accidents

Cheol Nam, Yong-Hwan Jeong, Youn-Ho Jung

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 158-168

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT01-A3235

An Integral Response Scaling Method for Reduced-Height Test Facilities and Its Validation Using RELAP5 for Loss of RHR During Midloop Operation

Hyoung Tae Kim, Hee Cheon No

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 169-185

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3236

Thermal-Hydraulic Simulation of Localized Flow Characteristics in a Steam Generator

Yuh-Ming Ferng, Yin-Pang Ma, Jer-Cherng Kang

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 186-196

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3237

A New Method to Determine the Neutron Sensitivity of a Micro Fission Chamber for a Boiling Water Reactor

Atsushi Kimura, Kaoru Fujita, Masaharu Nakazawa, Shinya Fujita, Eiji Seki, Yutaka Tanaka, Shigehiro Kono

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 197-203

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3238

Safety Evaluation of Primary-Side Bleed-and-Feed Scenarios by an Experimental Loss of Feedwater Event at the IIST Facility

Tay-Jian Liu, Show-Chyuan Chiang

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 204-220

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT01-A3239

Incipient Fault Detection and Isolation of Field Devices in Nuclear Power Systems Using Principal Component Analysis

Nitin Kaistha, Belle R. Upadhyaya]

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 221-230

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT01-A3240

Radiolysis of Bicarbonate and Carbonate Aqueous Solutions: Product Analysis and Simulation of Radiolytic Processes

Zhongli Cai, Xifeng Li, Yosuke Katsumura, Osamu Urabe

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 231-240

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT01-A3241

Void Fraction Measurement in Subcooled-Boiling Flow Using High-Frame-Rate Neutron Radiography

Masatoshi Kureta, Hajime Akimoto, Takashi Hibiki, Kaichiro Mishima

Nuclear Technology / Volume 136 / Number 2 / November 2001 / Pages 241-254

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT01-A3242

 

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