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Home / Publications / Journals / Nuclear Technology / Volume 108 / Number 2

Volume 108

Number 2

Conceptual Designs of Epithermal Neutron Beams for Boron Neutron Capture Therapy from Low-Power Reactors

Hungyuan B. Liu, Robert M. Brugger

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 151-156

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35026

Development and Comparison of a TOPAZ-II System Model with Experimental Data

Dmitry V. Paramonov, Mohamed S. El-Genk

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 157-170

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35027

An Integrated Model of the TOPAZ-II Electromagnetic Pump

Mohamed S. El-Genk, Dmitry V. Paramonov

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 171-180

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35028

Characteristics of the Flow-Controlled Accumulator

Tadashi Shiraishi, Hisato Watakabe, Nobuo Nakamori, Kozo Tabuchi, Yoji Takayama, Takayoshi Sugizaki

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 181-190

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT94-A35029

RELAP5/MOD3 Simulation of the Loss of the Residual Heat Removal System During a Midloop Operation Experiment Conducted at the ROSA-IV Large-Scale Test Facility

Yassin A. Hassan, Sibashis S. Banerjee

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 191-206

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A35030

Strength of Silicon Carbide Layers of Fuel Particles for High-Temperature Gas-Cooled Reactors

Paul A. Lessing, Ronald J. Heaps

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 207-234

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A35031

Preliminary Neutronics Investigation of the Delayed Neutron Nondestructive Assay of an Integral Fast Reactor Waste Canister

Cheng-Wei Wu, Douglass L. Henderson, Edgar F. Bennett

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 235-255

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT94-A35032

A Modeling Study of Parameters ControIIing Local Concentration Processes in Pressurized Water Reactor Steam Generators

Peter J. Millett, James M. Fenton

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 256-265

Technical Paper / Material / dx.doi.org/10.13182/NT94-A35033

Effect of External Cooling on the Thermal Behavior of a Boiling Water Reactor Vessel Lower Head

Hyunjae Park, V. K. Dhir, William E. Kastenberg

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 266-282

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A35034

Error Prediction for a Nuclear Power Plant Fault-Diagnostic Advisor Using Neural Networks

Keehoon Kim, Eric B. Bartlett

Nuclear Technology / Volume 108 / Number 2 / November 1994 / Pages 283-297

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A35035

 

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