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Home / Publications / Journals / Nuclear Technology / Volume 127 / Number 1

Volume 127

Number 1

Automatic Rapid Process for the Generation of Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries

Luiz C. Leal, Otto W. Hermann, Stephen M. Bowman, Cecil V. Parks

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 1-23

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A2980

Drag Coefficients for Reactor Loose Parts

Liang Shi, J. Michael Doster, Charles W. Mayo

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 24-37

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2981

Modeling the Statics of a Natural-Circulation Boiling Water Reactor Loop

Haico V. Kok, Tim H. J. J. van der Hagen

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 38-48

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2982

Qualification of a Three-Dimensional Core Dynamics Analysis Program Coupled with a Detailed Mesh Division for Commercial Boiling Water Reactors-I

Yasunori Bessho, Takafumi Anegawa, Osamu Yokomizo, Yuichiro Yoshimoto, Masao Chaki, Motoo Aoyama, Takanori Fukahori

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 49-65

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2983

Natural Convection Heat Transfer with Crust Formation in the Molten Metal Pool

Rae-Joon Park, Sang-Baik Kim, Hee-Dong Kim, Sang-Min Choi

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 66-80

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2984

Separation of Radioactive Strontium from Alkaline Nuclear Waste Solutions with the Highly Effective Ion Exchanger SrTreat

Jukka Lehto, Leena Brodkin, Risto Harjula, Esko Tusa

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 81-87

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A2985

Dose Rate Measurements and Calculation of TN-12/2 Packages

Hiroaki Taniuchi, Fumio Matsuda

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 88-101

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT99-A2986

Empirical Steam Generator Water-Level Modeling Using Neural Networks

Chaung Lin, Tsung-Ming Lin

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 102-112

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT99-A2987

Theoretical Calculations of Proton Reaction Cross Sections in a Lead Target with Energy Ep 300 MeV

Jinfeng Zhou, Qingbiao Shen, Xiuquan Sun

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 113-122

Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT99-A2988

Uncertainty Analysis in DUPIC Fuel-Cycle Cost Using a Probabilistic Simulation Method

Won Il Ko, Jong Won Choi, Jae Sol Lee, Hyun Soo Park, Kun Jai Lee

Nuclear Technology / Volume 127 / Number 1 / July 1999 / Pages 123-140

Technical Note / Fuel Cycle and Management / dx.doi.org/10.13182/NT99-A2989

 

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