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Volume 147

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Number 1

Core Designs and Economic Analyses of Homogeneous Thoria-Urania Fuel in Light Water Reactors

Mehmet Saglam, Joe J. Sapyta, Stewart W. Spetz, Lawrence A. Hassler

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 8-19

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT03-29

Microheterogeneous Thoria-Urania Fuels for Pressurized Water Reactors

Eugene Shwageraus, Xianfeng Zhao, Michael J. Driscoll, Pavel Hejzlar, Mujid S. Kazimi, J. Stephen Herring

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 20-36

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT04-A3512

Alternative Applications of Homogeneous Thoria-Urania Fuel in Light Water Reactors to Enhance the Economics of the Thorium Fuel Cycle

Hyung-Kook Joo, Jae-Man Noh, Jae-Woon Yoo, Jin-Young Cho, Sang-Yoon Park, Moon-Hee Chang

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 37-52

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT03-30

Use of Thorium for Transmutation of Plutonium and Minor Actinides in PWRs

Eugene Shwageraus, Pavel Hejzlar, Mujid S. Kazimi

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 53-68

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT04-A3514

Weapons-Grade Plutonium-Thorium PWR Assembly Design and Core Safety Analysis

David Dziadosz, Timothy N. Ake, Mehmet Saglam, Joe J. Sapyta

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 69-83

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT147-69

Thorium-Based Transmuter Fuels for Light Water Reactors

J. Stephen Herring, Philip E. MacDonald, Kevan D. Weaver

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 84-101

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT04-A3516

Costs for Manufacturing Thorium-Uranium Dioxide Fuels for Light Water Reactors

Edward J. Lahoda

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 102-112

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT04-A3517

Fabrication and Thermal Conductivity of (Th,U)O2 Pellets

Jae Ho Yang, Ki Won Kang, Kun Woo Song, Chan Bock Lee, Youn Ho Jung

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 113-119

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT04-A3518

The Behavior of ThO2-Based Fuel Rods During Normal Operation and Transient Events in LWRs

Yun Long, Larry J. Siefken, Pavel Hejzlar, Eric P. Loewen, Judith K. Hohorst, Philip E. MacDonald, Mujid S. Kazimi

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 120-139

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT04-A3519

Irradiation Behavior of Thoria-Urania Fuel in a PWR

Chan Bock Lee, Yong Sik Yang, Young Min Kim, Dae Ho Kim, Youn Ho Jung

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 140-148

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT04-A3520

Xenon Diffusivity in Thoria-Urania Fuel

Heemoon Kim, Kwangheon Park, Bong Goo Kim, Yong Sun Choo, Keon Sik Kim, Kun Woo Song, Kwon Pyo Hong, Young Hwan Kang, Kwangil Ho

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 149-156

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT04-A3521

Aqueous Dissolution of Urania-Thoria Nuclear Fuel

Paul A. Demkowicz, James L. Jerden, Jr., James C. Cunnane, Noriko Shibuya, Ronald Baney, James Tulenko

Nuclear Technology / Volume 147 / Number 1 / July 2004 / Pages 157-170

Technical Paper / Thoria-Urania NERI / dx.doi.org/10.13182/NT04-A3522

Number 2

Neutronic and Logistic Proposal for Transmutation of Plutonium from Spent Nuclear Fuel as Mixed-Oxide Fuel in Existing Light Water Reactors

Holly R. Trellue

Nuclear Technology / Volume 147 / Number 2 / August 2004 / Pages 171-180

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-A3523

Computational Fluid Dynamics for the Analysis of Light Water Reactor Flows

Constantine P. Tzanos

Nuclear Technology / Volume 147 / Number 2 / August 2004 / Pages 181-190

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3524

Validation of Heat Transfer Models in Narrow Gap for RELAP/SCDAPSIM/MOD3.2

Tamio Kohriyama, Michio Murase, Takashi Nagae, Yukimitsu Okano, Alexandre Ezzidi

Nuclear Technology / Volume 147 / Number 2 / August 2004 / Pages 191-201

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3525

Hydrogen Generation in Reflooding Experiments with LWR-Type Rod Bundles (QUENCH Program)

Leo K. Sepold, Alexei Miassoedov, Gerhard Schanz, Ulrike Stegmaier, Martin Steinbrück, Juri Stuckert, Christoph Homann

Nuclear Technology / Volume 147 / Number 2 / August 2004 / Pages 202-215

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3526

Identification of Loss-of-Coolant Accidents in LWRs by Inverse Models

Wojciech Cholewa, Wiktor Frid, Marcin Bednarski

Nuclear Technology / Volume 147 / Number 2 / August 2004 / Pages 216-226

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3527

Software Safety Analysis of Digital Protection System Requirements Using a Qualitative Formal Method

Jang-Soo Lee, Kee-Choon Kwon, Sung-Deok Cha

Nuclear Technology / Volume 147 / Number 2 / August 2004 / Pages 227-239

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT04-A3528

Design and Validation of Optimized Feedforward with Robust Feedback Control of a Nuclear Reactor

Roman Shaffer, Weidong He, Robert M. Edwards

Nuclear Technology / Volume 147 / Number 2 / August 2004 / Pages 240-257

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT04-A3529

Water Sorption and Gamma Radiolysis Studies for Uranium Oxides

Alan S. Icenhour, L. M. Toth, Huimin Luo

Nuclear Technology / Volume 147 / Number 2 / August 2004 / Pages 258-268

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT04-A3530

Nitrogen-16 Generation and Transport and Associated Shielding Requirements in a Supercritical-Water-Cooled Reactor

Benjamin Fischer, Marci Smolinski, Jacopo Buongiorno

Nuclear Technology / Volume 147 / Number 2 / August 2004 / Pages 269-283

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT04-A3531

Development of a Cobalt Dicarbollide/Polyethylene Glycol Solvent Extraction Process for Separation of Cesium and Strontium to Support Advanced Aqueous Reprocessing

Jack D. Law, R. Scott Herbst, Dean R. Peterman, Rich D. Tillotson, Terry A. Todd

Nuclear Technology / Volume 147 / Number 2 / August 2004 / Pages 284-290

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT04-A3532

Eddy Current Measurements of Corrosion and Metal Loss in Zircaloy Cladding with Ferromagnetic Crud

Suresh K. Yagnik, Duane P. Johnson, John A. Kervinen

Nuclear Technology / Volume 147 / Number 2 / August 2004 / Pages 291-300

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT04-A3533

Number 3

Medium-Power Lead-Alloy Reactors: Missions for This Reactor Technology

Neil E. Todreas, Philip E. MacDonald, Pavel Hejzlar, Jacopo Buongiorno, Eric P. Loewen

Nuclear Technology / Volume 147 / Number 3 / September 2004 / Pages 305-320

Technical Paper / Medium-Power Lead-Alloy Reactors / dx.doi.org/10.13182/NT04-A3534

Design Strategy and Constraints for Medium-Power Lead-Alloy–Cooled Actinide Burners

Pavel Hejzlar, Jacopo Buongiorno, Philip E. MacDonald, Neil E. Todreas

Nuclear Technology / Volume 147 / Number 3 / September 2004 / Pages 321-343

Technical Paper / Medium-Power Lead-Alloy Reactors / dx.doi.org/10.13182/NT147-321

Performance of the Lead-Alloy-Cooled Reactor Concept Balanced for Actinide Burning and Electricity Production

Pavel Hejzlar, Cliff B. Davis

Nuclear Technology / Volume 147 / Number 3 / September 2004 / Pages 344-367

Technical Paper / Medium-Power Lead-Alloy Reactors / dx.doi.org/10.13182/NT04-A3536

Fertile-Free Fast Lead-Cooled Incinerators for Efficient Actinide Burning

Antonino Romano, Pavel Hejzlar, Neil E. Todreas

Nuclear Technology / Volume 147 / Number 3 / September 2004 / Pages 368-387

Technical Paper / Medium-Power Lead-Alloy Reactors / dx.doi.org/10.13182/NT04-1

Medium-Power Lead-Alloy Fast Reactor Balance-of-Plant Options

Vaclav Dostal, Pavel Hejzlar, Neil E. Todreas, Jacopo Buongiorno

Nuclear Technology / Volume 147 / Number 3 / September 2004 / Pages 388-405

Technical Paper / Medium-Power Lead-Alloy Reactors / dx.doi.org/10.13182/NT147-388

Studies of Polonium Removal from Molten Lead-Bismuth for Lead-Alloy-Cooled Reactor Applications

Jacopo Buongiorno, Eric P. Loewen, Kenneth Czerwinski, Christopher Larson

Nuclear Technology / Volume 147 / Number 3 / September 2004 / Pages 406-417

Technical Paper / Medium-Power Lead-Alloy Reactors / dx.doi.org/10.13182/NT04-A3539

An Overview of Corrosion Issues for the Design and Operation of High-Temperature Lead- and Lead-Bismuth-Cooled Reactor Systems

Ronald G. Ballinger, Jeongyoun Lim

Nuclear Technology / Volume 147 / Number 3 / September 2004 / Pages 418-435

Technical Paper / Medium-Power Lead-Alloy Reactors / dx.doi.org/10.13182/NT04-A3540

Corrosion Studies in Support of Medium-Power Lead-Alloy-Cooled Reactor

Eric P. Loewen, Ronald G. Ballinger, Jeongyoun Lim

Nuclear Technology / Volume 147 / Number 3 / September 2004 / Pages 436-456

Technical Paper / Medium-Power Lead-Alloy Reactors / dx.doi.org/10.13182/NT04-A3541

A Qualitative Reactivity and Isotopic Assessment of Fuels for Lead-Alloy-Cooled Fast Reactors

Kevan D. Weaver, Philip E. MacDonald

Nuclear Technology / Volume 147 / Number 3 / September 2004 / Pages 457-469

Technical Paper / Medium-Power Lead-Alloy Reactors / dx.doi.org/10.13182/NT04-A3542