American Nuclear Society
Join ANS|Member Center|ANS Store|Contact Us
Home

Home / Publications / Journals / Nuclear Technology / Volume 96

Volume 96

Number 1 | Number 2 | Number 3

Number 1

A Knowledge-Based System for Power Maneuver Planning for Boiling Water Reactors

Mitsuo Kinoshita, Takaharu Fukuzaki, Akira Nishimura, Yukihisa Fukasawa, Tsutomu Matsuki

Nuclear Technology / Volume 96 / Number 1 / October 1991 / Pages 1-10

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A35528

A New Boiling Water Reactor Core Concept for a Next-Generation Light Water Reactor

Junichi Yamashita, Akira Nishimura, Takaaki Mochida, Osamu Yokomizo

Nuclear Technology / Volume 96 / Number 1 / October 1991 / Pages 11-19

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A35529

Development of a High-Conversion Boiling Water Reactor

Junichi Yamashita, Takaaki Mochida

Nuclear Technology / Volume 96 / Number 1 / October 1991 / Pages 20-28

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A35530

Results of Postirradiation Examination of the In-Pile Blockage Experiments Mol-7C/4 and Mol-7C/5

P. Weimar, Karl Schleisiek

Nuclear Technology / Volume 96 / Number 1 / October 1991 / Pages 29-36

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A35531

Safety Analysis of Depressurization Accidents in a Medium-Sized High-Temperature Gas Reactor

Shlomo Ron, Judah Tzoref

Nuclear Technology / Volume 96 / Number 1 / October 1991 / Pages 37-49

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A35532

Assessment of Gamma Fields Inside Buildings in an Urban Area Resulting from External Radionuclide Deposition

O. Graf, A. Bayer

Nuclear Technology / Volume 96 / Number 1 / October 1991 / Pages 50-71

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT91-A35533

Fabrication Experience of AI-233U and Al-Pu Plate Fuel for the Purnima III and Kamini Research Reactors

C. Ganguly, G. J. Prasad, K. N. Mahule, J. K. Ghosh, K. V. J. Asari, K. N. P. Chandrasekharan, S. Muralidhar, T. S. Balan, P. R. Roy

Nuclear Technology / Volume 96 / Number 1 / October 1991 / Pages 72-83

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A35534

U(IV) and U(VI) Extraction Behavior in Pulsed Columns During Off-Standard Operation

Kenzo Munakata, Masahiro Nabeshima

Nuclear Technology / Volume 96 / Number 1 / October 1991 / Pages 84-95

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT91-A35535

Vaporization of Strontium, Barium, Lanthanum, and Uranium from Mixtures of Urania, Zirconia, Steel, and Concretes at 2150 and 2400 K

Michael F. Roche, Leonard Leibowitz, Jack L. Settle, Carl E. Johnson, Richard C. Vogel, Robert L. Ritzman

Nuclear Technology / Volume 96 / Number 1 / October 1991 / Pages 96-116

Technical Paper / Material / dx.doi.org/10.13182/NT91-A35536

Finite Element Stress Analysis for Coated Particle Fuel Modeling Under Normal Operating Conditions

Ralph G. Bennett

Nuclear Technology / Volume 96 / Number 1 / October 1991 / Pages 117-122

Technical Note / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A35537

Steady-State Simulations of a 30-Tube Once-Through Steam Generator with the RELAP5/MOD3 and RELAP5/MOD2 Computer Codes

Yassin A. Hassan, Parvez Salim

Nuclear Technology / Volume 96 / Number 1 / October 1991 / Pages 123-128

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A35538

Number 2

A “Nonproliferating” Nuclear Fuel for Light Water Reactors

Yigal Ronen, Yehoshua Kimhi

Nuclear Technology / Volume 96 / Number 2 / November 1991 / Pages 133-138

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34599

Simulation of the Primary-Secondary Leak Experiment of IAEA’ Third Standard Problem Exercise Using the RELAP5/MOD2 and RELAP5/MOD3 Computer Codes

Y. A. Hassan, Parvez Salim

Nuclear Technology / Volume 96 / Number 2 / November 1991 / Pages 139-146

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34600

N Reactor Level III Probabilistic Risk Assessment Using NUREG-1150 Methods

Oliver S. Wang, Garill A. Coles, John E. Kelly, Thomas B. Powers, Thomas E. Rainey, Michael D. Zentner, Gregory D. Wyss, David M. Kunsman, LeAnn Adams Miller, Timothy A. Wheeler, Jeremy L. Sprung, Allen L. Camp

Nuclear Technology / Volume 96 / Number 2 / November 1991 / Pages 147-168

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34601

Studies of the Preparation of Thoria and Thoria-Urania Microspheres Using an Internal Gelation Process

N. Kumar, R. K. Sharma, V. R. Ganatra, S. K. Mukerjee, V. N. Vaidya, D. D. Sood

Nuclear Technology / Volume 96 / Number 2 / November 1991 / Pages 169-177

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34602

In Situ Vitrification of Soils Containing Various Metals

James L. Buelt, Richard K. Farnsworth

Nuclear Technology / Volume 96 / Number 2 / November 1991 / Pages 178-184

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT91-A34603

Properties of a Radioactive Waste Pellet Package Using Cement-Glass

Kiyomi Funabashi, Koichi Chino, Makoto Kikuchi, Susumu Horiuchi, Hiroyuki Tsuchiya

Nuclear Technology / Volume 96 / Number 2 / November 1991 / Pages 185-191

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT91-A34604

The Equilibrium Concept—An Extended Approach to Assess Long-Term Radionuclide Release from Repositories

Rainer Köster, Günter Rudolph

Nuclear Technology / Volume 96 / Number 2 / November 1991 / Pages 192-201

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT91-A34605

Results of 0.5% Hot-Leg Break Loss-of-Coolant Accident Experiments at ROSA-IV/LSTF: The Effect of Break Orientation

Hideaki Asaka, Yutaka Kukita, Taisuke Yonomoto, Kanji Tasaka

Nuclear Technology / Volume 96 / Number 2 / November 1991 / Pages 202-214

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34606

Influence of Secondary System Conditions on Steam Generator U-Tube Flow Distribution During Single-Phase Natural Circulation

Alessandro Annunziato

Nuclear Technology / Volume 96 / Number 2 / November 1991 / Pages 215-228

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34607

A Water Level-Initiated Decay Energy Cooling System

Charles W. Forsberg

Nuclear Technology / Volume 96 / Number 2 / November 1991 / Pages 229-235

Technical Note / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34608

Number 3

Study of Coolant Activation and Dose Rates with Flow Rate and Power Perturbations in Pool-Type Research Reactors

Nasir M. Mirza, Sikander M. Mirza, N. Ahmad

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 237-247

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34586

Evaluation of a Dilute Chemical Decontaminant for Pressurized Heavy Water Reactors

S. Velmurugan, S. V. Narasimhan, P. K. Mathur, K. S. Venkateswarlu

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 248-258

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-248

Estimates of Rupture Probabilities for Nuclear Power Plant Components: Expert Judgment Elicitation

Truong V. Vo, Patrick G. Heasler, Steven R. Doctor, Frederic A. Simonen, Bryan F. Gore

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 259-271

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34588

The Response of Ex-Core Neutron Detectors to Large- and Small-Break Loss-of-Coolant Accidents in Pressurized Water Reactors

E. Wilson Okyere, Anthony J. Baratta, William A. Jester

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 272-289

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34589

Temporary Core Liquid Level Depression During a Cold-Leg Small-Break Loss-of-Coolant Accident: The Effect of Break Size and Power Level

Yasuo Koizumi, Hiroshige Kumamaru, Yuichi Mimura+, Yutaka Kukita, Kanji Tasaka†

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 290-301

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34590

Quantitative Fuel Motion Determination with the CABRI Fast Neutron Hodoscope: Evaluation Methods and Results

Kurt Baumung, Gérard Augier

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 302-313

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34591

A Model to Predict the Ultimate Failure of Coated Fuel Particles During Core Heatup Events

Toru Ogawa, Kazuo Minato, Kousaku Fukuda, Masami Numata, Hideshi Miyanishi, Hajime Sekino, Hideo Matsushima, Tadaharu Itoh, Shigeo Kado, Ishio Takahashi

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 314-322

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34592

High-Temperature Reactor Fuel Fission Product Release and Distribution at 1600 to 1800°C

Werner Schenk, Heinz Nabielek

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 323-336

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT96-3-323

Isotope Separation by Chemical Exchange: A Computer Simulation

Heinrich R. Obermoller, David A. White

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 337-345

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT91-A34594

Neutron Effects on Borated Stainless Steel

S. E. Soliman, D. L. Youchison, A. J. Baratta, T. A. Balliett

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 346-352

Technical Paper / Material / dx.doi.org/10.13182/NT91-A34595

Operating Margin of Soviet RBMK-1000 Nuclear Power Reactors

James M. Adams, Lawrence E. Hochreiter, Gordon E. Robinson

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 353-360

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34596

 

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use