American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 95 / Number 2

Volume 95

Number 2

Sensitivity and Uncertainty Analysis of Integral Physics Parameters in High-Conversion Reactor Systems

John R. White, Thomas F. DeLorey

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 129-147

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34551

Corrosion Product Radionuclide Buildup in Fast Flux Test Facility Heat Transport System Cells

William F. Brehm, Robert L. Simons

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 148-155

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34552

Xenon Dynamics and Related Parameters in the Taiwan Research Reactor

Shih-Jen Wang, Ming-Song Lin

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 156-161

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34553

Effect of Flushing Boron During a Boiling Water Reactor Anticipated Transient Without Scram

Dragan Mirkovic, David J. Diamond

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 162-174

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34554

Theory and Verification of a Fuel Rod Mechanics Model Based on a Two-Dimensional Finite Element Method with Consideration of Fuel/Cladding Contact and Friction

Klaus L. Nissen

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 175-192

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34555

A Simple Nondestructive Measurement System for Spent-Fuel Management

Hermann Würz

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 193-206

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34556

Analysis of Cylindrical and Annular Pulsed Columns with Different Internal Plates in the Purex Process

Masahiro Nabeshima

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 207-218

Technical Paper / Environment and Reprocessing System / dx.doi.org/10.13182/NT91-A34557

Elaborated Constitutive Equations for Structural Analysis for Creep, Swelling, and Damage Under Irradiation

S. Murakami, M. Mizuno

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 219-227

Technical Paper / Material / dx.doi.org/10.13182/NT91-A34558

Thermal-Hydraulic Systems Safety Analysis to Support the Design Process for the Advanced Neutron Source Reactor

C. D. Fletcher, L. S. Ghan

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 228-246

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34559

The Probability Density Function of the Total Departure from Nucleate Boiling Ratio

Ross C. Anderson

Nuclear Technology / Volume 95 / Number 2 / August 1991 / Pages 247-250

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34560