American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 27 / Number 3

Volume 27

Number 3

A Method for Optimum Determination of Adjustable Parameters in the Boiling Water Reactor Core Simulator Using Operating Data on Flux Distribution

Takashi Kiguchi, Toshio Kawai

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 315-326

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24307

Subcompartment Analysis of High-Energy Pipe Ruptures

C. William Savery, Y. S. Huang, George M. Kowal

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 327-336

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24308

Computer Simulation of Pulsed-Neutron Experiments Performed on the Fort St. Vrain High-Temperature Gas-Cooled Reactor

Wayne Pfeiffer

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 337-351

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24309

Analysis and Results of Pulsed-Neutron Experiments Performed on the Fort St. Vrain High-Temperature Gas-Cooled Reactor

W. Pfeiffer, J. R. Brown, A. C. Marshall

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 352-375

Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24310

Mechanical Properties of Unirradiated Fast Reactor Cladding During Simulated Overpower Transients

C. W. Hunter, R. L. Fish, J. J. Holmes

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 376-388

Department / Fuel / dx.doi.org/10.13182/NT75-A24311

Effects of Fissile Atom Segregation in Light Water Reactor Plutonium Recycle Fuels

R. O. Meyer, C. R. Hann, D. D. Lanning

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 389-393

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24312

An Assessment of the Coolant Voiding Dynamics Following the Failure of Preirradiated LMFBR Fuel Pins

August W. Cronenberg, Michael A. Grolmes

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 394-410

Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24313

Plutonium Trifluoride as a Fuel for Molten Salt Reactors-Solubility Studies

D. D. Sood, P. N. Iyer, R. Prasad, V. N. Vaidya, K. N. Roy, V. Venugopal, Z. Singh, M. V. Ramaniah

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 411-415

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24314

Fast- and Thermal-Neutron Irradiation and Annealing of Cu, Ni, Fe, Ti, and Pd

J. A. Horak, T. H. Blewitt

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 416-438

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24315

Analytical Determination of Nitride Nitrogen in Lithium Coolants

R. J. Schlager, D. L. Olson, W. L. Bradley

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 439-441

Technical Paper / Material / dx.doi.org/10.13182/NT75-A24316

A Gamma-Ray Absorptometer for Nuclear Fuel Evaluation

James E. Ayer, Donald R. Schmitt

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 442-448

Technical Paper / Instrument / dx.doi.org/10.13182/NT75-A24317

Fast-Neutron Hodoscope at Treat: Development and Operation

A. De Volpi, R. J. Pecina, R. T. Daly, D. J. Travis, R. R. Stewart, E. A. Rhodes

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 449-487

Technical Paper / Instruments / dx.doi.org/10.13182/NT75-1

Analysis of Geothermal Power Plant Water Using Gamma Rays from Capture of Californium-252 Neutrons

Dick Duffey, J. P. Balogna, Peter F. Wiggins

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 488-499

Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24319

Measurement of Transuranic Solid Wastes at the 10 nCi/g Activity Level

C. J. Umbarger, L. R. Cowder

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 500-510

Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24320

Thermal-Neutron Flux Distribution in Cubical Cavities from an Isotopic Neutron Source

John Bartko

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 511-513

Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24321

The Influence of Nonstatistical Variations on Low-Level Measurements of 131l in Milk

J. M. Matuszek, C. J. Paperiello

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 514-522

Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24322

A Fast-Response Thermocouple for Temperature Fluctuation Measurements in Sodium Coolants

H. Bunschi, W. Seifritz

Nuclear Technology / Volume 27 / Number 3 / November 1975 / Pages 523-525

Technical Note / Technique / dx.doi.org/10.13182/NT75-A24323