ANS / Publications / Journals / Nuclear Technology

Development of an Automatic Metal Analysis System for Boiling Water Reactor Primary Water and Its Application

Hiroo Igarashi, Michio Nitto, Fumio Mizumiwa, Katumi Ohsumi

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 287-296

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A17027

Development of the Chinshan Plant Analyzer and Its Assessment with Plant Data

Shih-Jen Wang, Chun-Sheng Chien, Jung-Yuh Jang, Shaw-Cuang Lee

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 297-303

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A17028

Steam Generator Secondary pH During a Steam Generator Tube Rupture

James P. Adams, Eric S. Peterson

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 304-312

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A17029

Estimation of Burnup in Taiwan Research Reactor Fuel Pins by Using Nondestructive Techniques

Lung Kwang Pan, Cheng Si Tsao

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 313-322

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A17030

Radiochemical Evaluation for Debris-Induced Failures

G. Goncarovs

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 323-330

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A17031

Cadmium Transport Through Molten Salts in the Reprocessing of Spent Fuel for the Integral Fast Reactor

K. Michael Goff, Alfred Schneider, James E. Battles

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 331-340

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A17032

New Separation Process for Neptunium, Plutonium, and Uranium Using Butyraldehydes as Reductants in Reprocessing

Gunzo Uchiyama, Sachio Fujine, Shinobu Hotoku, Mitsuru Maeda

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 341-352

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A17033

A Liquid-Metal Reactor Core Demonstration Experiment Using HT-9

Alvia E. Bridges, Alan E. Waltar, Robert D. Leggett, Ronald B. Baker, Jerry L. Ethridge

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 353-366

Technical Paper / Material / dx.doi.org/10.13182/NT93-A17034

Fracture and Tensile Properties of Irradiated Zircaloy-2 Pressure Tubes

Frank H. Huang, William J. Mills

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 367-375

Technical Paper / Material / dx.doi.org/10.13182/NT93-A17035

Tensile Behavior of Neutron-Irradiated Martensitic Steels: A Review

R. L. Klueh

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 376-385

Technical Paper / Material / dx.doi.org/10.13182/NT93-A17036

Local Heat Transfer Coefficients for Forced-Convection Condensation of Steam in a Vertical Tube in the Presence of a Noncondensable Gas

Mansoor Siddique, Michael W. Golay, Mujid S. Kazimi

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 386-402

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT93-A17037

Development of In-Service Inspection Plans for Nuclear Components at the Surry Unit 1 Nuclear Power Station

Truong V. Vo, Frederic A. Simonen, Steven R. Doctor, Brian W. Smith, Bryan F. Gore

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 403-415

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT93-A17038

Modification to Unal’s Subcooled Flow Boiling Bubble Model

Richard A. Riemke

Nuclear Technology / Volume 102 / Number 3 / June 1993 / Pages 416-417

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT93-A17039