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Volume 118

Number 2

Advanced Vessel Cooling System Concept for High-Temperature Gas-Cooled Reactors

Akio Saikusa, Kazuhiko Kunitomi, Shusaku Shiozawa

Nuclear Technology / Volume 118 / Number 2 / May 1997 / Pages 89-96

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT97-A35370

A Decision Support System for Emergency Response to Major Nuclear Accidents

Ioannis A. Papazoglou, Michalis D. Christou

Nuclear Technology / Volume 118 / Number 2 / May 1997 / Pages 97-122

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT97-A35371

An Investigation of Cesium Release from Coated Particle Fuel of the High-Temperature Gas-Cooled Reactor

Kazuhiro Sawa, Kazuo Minato, Tsutomu Tobita, Kousaka Fukuda

Nuclear Technology / Volume 118 / Number 2 / May 1997 / Pages 123-131

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35372

Stochastic Radionuclide Distributions After a Basaltic Eruption for Performance Assessments of Yucca Mountain

Mark S. Jarzemba

Nuclear Technology / Volume 118 / Number 2 / May 1997 / Pages 132-141

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT97-A35373

Comparison of Characteristics of Solution and Conventional Reactors for 99Mo Production

Dan Glenn, A. Sharif Heger, William B. Hladik III

Nuclear Technology / Volume 118 / Number 2 / May 1997 / Pages 142-150

Technical Paper / Radioisotopes and Isotopes / dx.doi.org/10.13182/NT97-A35374

A Two-Phase Flow Regime Map for a Maple-Type Nuclear Research Reactor Fuel Channel: Effect of Hexagonal Finned Bundle

Glenn D. Harvel, J. S. Chang, V. Santhana Krishnan

Nuclear Technology / Volume 118 / Number 2 / May 1997 / Pages 151-161

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35375

Simulation of a Small Cold-Leg-Break Experiment at the PMK-2 Test Facility Using the RELAP5 and ATHLET Codes

György Ézsöl, Atilla Guba, László Perneczky, Eckhard Krepper, Horst-Michael Prasser, Frank Schäfer

Nuclear Technology / Volume 118 / Number 2 / May 1997 / Pages 162-174

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35376

Three-Dimensional Numerical Simulations of Heat Transfer in an Annular Fuel Channel with Periodic Spacer Ribs Under a Fully Developed Turbulent Flow

Kazuyuki Takase

Nuclear Technology / Volume 118 / Number 2 / May 1997 / Pages 175-185

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT97-A35377