Home / Publications / Journals / Nuclear Technology / Volume 27 / Number 2

Volume 27

Number 2

Table of Contents
Authors(M. A. Gaafer, L. Mango, F. V. Orestano, F. Pistella, V. Marinelli, A. Pellei, P. Vallero, C. Vitanza, W. L. Kruer, Friedbert Kappler, J. R. Beattie, J. H. Pitts, John O. Mingle, George Yadigaroglu, J. T. A. Roberts, B. J. Wrona, D. Fischer, J. A. Buzzell, David E. Lamkin, Richard L. Brehm, J. F. Bates, G. L. Guthrie, F. L. Yaggee, G. M. Dragel)
Nuclear Criticality Safety(G. Ronald Dalton)
Power Plants with Air-Cooled Condensing Systems(J. F. Bregar)
Annual Review of Nuclear Science(Joseph G. Gratton)
Science Policy Making in the United States and the Batavia Accelerator(V. Lawrence Parsegian)
On Limit-Line Curves in Risk Evaluation(David Okrent)
Comments on “Total Energy Investment in Nuclear Power Plants”(Martha W. Gilliland, James B. Freim)
Response to Comments on “Total Energy Investment in Nuclear Power Plants’”(C. T. Rombough)

Assessment of the Reliability of the CNEN’s Calculational Methods for the Neutronic Design of PWRs

M. A. Gaafer, L. Mango, + F. V. Orestano,†, F. Pistella

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 187-206

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24286

Use of the “Lagrangian and Eulerian Points of View” in the Transient Critical Heat Flux Calculations for BWR Rod Bundles and Experimental Verifications

V. Marinelli, A. Pellei, P. Vallero, C. Vitanza

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 207-215

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24287

Plasma Simulation Using Particle Codes

W. L. Kruer

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 216-223

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24288

Measurement and Calculation of Neutron Spectra at a Sodium-Iron Interface

Friedbert Kappler

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 224-232

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24289

Rationale of Reactor Site Selection for Public Safety

J. R. Beattie

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 233-239

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A24290

Flow of Radioactive Fluid Through the Soil Surrounding a Power-Reactor Station After a Core Meltdown Accident

J. H. Pitts

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 240-247

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A24291

In-Core Fuel Management Via Perturbation Theory

John O. Mingle

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 248-257

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT75-A24292

Spent Fuel Transportation on Highways-the Radioactive Dose to the Traffic

George Yadigaroglu

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 258-266

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT75-A24293

Observations of Irradiated Fuel Behavior Under Simulated Accident Heating Conditions

J. T. A. Roberts, B. J. Wrona, D. Fischer, J. A. Buzzell

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 267-272

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24294

Analytical Stress Analysis Solution for a Simplified Model of a Reactor Fuel Element

David E. Lamkin, Richard L. Brehm

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 273-285

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24295

A Relationship Between Equivalent Chromium Content and Irradiation-Induced Swelling in Type 316 Stainless Steel

J. F. Bates, G. L. Guthrie

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 286-291

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24296

An Ultrasonic Trepanning Technique for Radial Sampling of Ceramic Fuel Pellets

F. L. Yaggee, G. M. Dragel

Nuclear Technology / Volume 27 / Number 2 / October 1975 / Pages 292-300

Technical Paper / Instrument / dx.doi.org/10.13182/NT75-A24297