ANS / Publications / Journals / Nuclear Technology

Development of Mixed-Oxide Fuel Manufacture in the United Kingdom and the Influence of Fuel Characteristics on Irradiation Performance

Hugh M. MacLeod, Geoffrey Yates

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 3-17

Technical Paper / Mixed-Oxide Fuel / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34798

Plutonium Processing at the Siemens Hanau Fuel Fabrication Plant

Jürgen Krellmann

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 18-28

Technical Paper / Mixed-Oxide Fuel / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A34799

Irradiation Behavior of UO₂/PuO₂ Fuel in Light Water Reactors

Wolfgang Goll, Hans-Peter Fuchs, Reiner Manzel, Fritz U. Schlemmer

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 29-46

Technical Paper / Mixed-Oxide Fuel / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34800

In-Pile Performance of Mixed-Oxide Fuel with Particular Emphasis on MIMAS Fuel

P. Deramaix, D. Haas, J. Van De Velde

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 47-53

Technical Paper / Mixed-Oxide Fuel / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34801

Experience in PWR and BWR Mixed-Oxide Fuel Management

Gerhard J. Schlosser, Wolf-Dieter Krebs, Peter Urban

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 54-67

Technical Paper / Mixed-Oxide Fuel / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34802

Investigation of the Nuclear Inventories of High-Exposure PWR Mixed-Oxide Fuels with Multiple Recycling of Self-Generated Plutonium

Hans-Werner Wiese

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 68-80

Technical Paper / Mixed-Oxide Fuel / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34803

Validation of Fuel Bundle Mechanical Performance Code ÉTOILE with Bundle/Duct Interaction Experimental Data

Masatoshi Nakagawa

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 81-89

Technical Paper / Mixed-Oxide Fuel / Fission Reactor / dx.doi.org/10.13182/NT93-A34804

Development of a Connectivity Verification System for Sequence Diagrams of Power Plants

Mitsuko Fukuda, Naoyuki Yamada, Ken’ichi Kan, Mitsugu Utsunomiya

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 90-99

Technical Paper / Mixed-Oxide Fuel / Fission Reactor / dx.doi.org/10.13182/NT93-A34805

Global Analysis of Bundle Behavior in Pressurized Water Reactor Specific CORA Experiments

Wolfgang Hering, Kazuo Minato, Fumihisa Nagase

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 100-115

Technical Paper / Mixed-Oxide Fuel / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34806

RELAP5/MOD2 Split Reactor Vessel Model and Steamline Break Analysis

Stojan Petelin, Borut Mavko, Oton Gortnar

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 116-124

Technical Paper / Mixed-Oxide Fuel / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34807

Ex-Core Detector Response Caused by Control Rod Misalignment Observed During Operation of the Reactor on the Nuclear Ship Mutsu

Masafumi Itagaki, Yoshinori Miyoshi, Kazuhiko Gakuhari, Noboru Okada, Tomohiro Sakai

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 125-136

Technical Paper / Mixed-Oxide Fuel / Reactor Operation / dx.doi.org/10.13182/NT93-A34808

Formalisms for Handling Phenomenological Uncertainties: The Concepts of Probability, Frequency, Variability, and Probability of Frequency

Stan Kaplan

Nuclear Technology / Volume 102 / Number 1 / April 1993 / Pages 137-142

Technical Note / Mixed-Oxide Fuel / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34809

Transient and Load-Following Characteristics of a Fully Integrated Single-Cell Thermionic Fuel Element

Mohamed S. El-Genk, Huimin Xue, Chris Murray

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 145-166

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34813

Proof of Principle of a Nuclear Turbine Flowmeter

Tim H. J. J. Van Der Hagen

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 167-176

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34814

Application of Neural Networks to a Connectionist Expert System for Transient Identification in Nuclear Power Plants

Se Woo Cheon, Soon Heung Chang

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 177-191

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34815

Reduction of the Reactivity of Water Ingress in Modular Pebble-Bed High-Temperature Reactors

E. Teuchert, K. A. Haas, H. J. Rütten, Yuliang Sun

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 192-195

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34816

Error Propagation for Gamma Spectroscopy and Neutron Coincidence Counting for Plutonium-Bearing Materials

Ming-Shih Lu, Theodor Teichmann

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 196-209

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34817

Evaluation of Fission Gas Release in High-Burnup Light Water Reactor Fuel Rods

John O. Barner, Mitchel E. Cunningham, Maxwell D. Freshley, Donald D. Lanning

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 210-231

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34818

Development of the FACE Computer Code to Evaluate the Safety of an Air Ventilation System During a Postulated Solvent Fire in a Nuclear Fuel Reprocessing Plant

Gunji Nishio, Noboru Yamazaki

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 232-251

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A34819

The Effect of Correlated Flow in Pulsed Column Contactors Using the Purex Process

John F. Geldard, Adolph L. Beyerlein

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 252-258

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A34820

Characterization of the Thermalness of a Fissile System with a Two-Group Diffusion Theory Parameter

Brent B. Bredehoft, Robert D. Busch

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 259-269

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT93-A34821

LRAD-Based Alpha-Particle Contamination Monitoring of Personnel and Equipment

Duncan W. MacArthur, Krag S. Allander, John A. Bounds, J. Lee McAtee

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 270-276

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT93-A34822

Automatic Reactor Power Control for a Pressurized Water Reactor

Jung-In Choi, Yung-Joon Hah, Un-Chul Lee

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 277-286

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT93-A34823

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