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Volume 128

Number 1

Design of a Simulated Void-Reactivity Feedback in a Boiling Water Reactor Loop

H. V. Kok, T. H. J. J. Van der Hagen

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 1-11

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A3009

RAPID-A Fast Reactor Concept Without Any Control Rods

Mitsuru Kambe

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 12-24

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A3010

Radiological Impact at the Extraction Stage of the Thorium Fuel Cycle

J. P. Schapira, R. K. Singhal

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 25-34

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT99-A3011

Fuel Element Burnup Determination in Mixed TRIGA Core Using Reactor Calculations

Matjaz Ravnik, Tomaz Zagar, Andreja Persic

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 35-45

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT99-A3012

Finite Element-Based Vibration Analysis of WWER-440 Reactors

Eberhard Alstadt, Frank-Peter Weiss

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 46-57

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3013

Turbulence Simulation in Tube Bundle Geometries Using the Dynamic Subgrid-Scale Model

Yassin A. Hassan, Hagop R. Barsamian

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 58-74

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3014

Natural Circulation Experiments at the ISB-VVER Integral Test Facility and Calculations Using the Thermal-Hydraulic Code ATHLET

Eckhard Krepper, Horst-Michael Prasser

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 75-86

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3015

RELAP5-3D Multidimensional Heat Conduction Enclosure Model for RBMK Reactor Application

Seungho Paik

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 87-102

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3016

Precipitation of Uranium and Plutonium from Alkaline Salt Solutions

David T. Hobbs

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 103-112

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT128-103

Development and Validation of ALFUS: An Irradiation Behavior Analysis Code for Metallic Fast Reactor Fuels

Takanari Ogata, Takeshi Yokoo

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 113-123

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT99-A3018

Multinodal Treatment of Production, Decay, and Spreading of Radioactive Isotopes

Péter Vértes

Nuclear Technology / Volume 128 / Number 1 / October 1999 / Pages 124-130

Technical Note / Reactor Safety / dx.doi.org/10.13182/NT99-A3019