ANS / Publications / Journals / Nuclear Technology

Simplified Boiling Water Reactor Thermal-Hydraulic Performance: A RELAP5/MOD2 Model Simulation

P. Barbucci, L. Bella

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 1-8

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT95-A15847

Radial Resonance Captures in ²³⁸U Metal Rods and Spatial Resonance Production of ²³⁹Pu in Uranium-Oxide Fuels

Donald Bogart

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 9-20

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT95-A15848

Aging Effects on Time-Dependent Nuclear Plant Component Unavailability: An Investigation of Variations from Static Calculations

Rob D. Radulovich, William E. Vesely, Tunc Aldemir

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 21-41

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15849

Evaluation of Reflooding Effects on an Overheated Boiling Water Reactor Core in a Small Steam-Line Break Accident Using MAAP, MELCOR, and SCDAP/RELAP5 Computer Codes

I. Lindholm, E. Pekkarinen, H. Sjövall

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 42-57

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15850

Qualification of a Passive Catalytic Module for Hydrogen Mitigation

Karsten Fischer

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 58-62

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15851

A Route-Specific System for Risk Assessment of Radioactive Materials Transportation Accidents

John E. Moore, Gary M. Sandquist, David M. Slaughter

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 63-78

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A15852

Thermal and Thermomechanical Analyses for Disposal in Drifts of a Repository in Rock Salt

Alexandra Pudewills, Nina Müller-Hoeppe, Reiner Papp

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 79-88

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A15853

Fast Multiple-Path Model to Calculate Radionuclide Release from the Near Field of a Repository

L. Romero, L. Moreno, I. Neretnieks

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 89-98

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A15854

The Fast Multiple-Path NUCTRAN Model—Calculating the Radionuclide Release from a Repository

L. Romero, L. Moreno, I. Neretnieks

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 99-107

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A15855

Framatome Antistratification Device for Steam Generator Feedwater Nozzle: Effectiveness, Qualification Test, and On-Site Measurements

Christophe Poussin, Alain Holcblat

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 108-121

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A15856

Experimental Study on Performance of a Hybrid Baffle Plate for the Water-Wall-Type Passive Containment Cooling System

Tadashi Fujii, Yoshiyuki Kataoka, Michio Murase, Kenji Tominaga

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 122-131

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A15857

Calculated Shielding Characteristics of Eight Materials for Neutrons and Secondary Photons Produced by Monoenergetic Source Neutrons with Energies Less Than 400 MeV

Noriyoshi Nakanishi, Takashi Shikata, Shin Fujita, Toshiso Kosako

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 132-141

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT95-A15858

Improved Neutronics Model of the High Flux Isotope Reactor

S. Goluoglu, H. L. Dodds

Nuclear Technology / Volume 112 / Number 1 / October 1995 / Pages 142-153

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT95-A15859