ANS / Publications / Journals / Nuclear Technology

Annular Fast Reactor Cores with Low Sodium Void Worth for TRU Burning

Ser Gi Hong, Sang Ji Kim, Yeong Il Kim

Nuclear Technology / Volume 162 / Number 1 / April 2008 / Pages 1-25

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT162-1-25

A Markov Model Approach to Proliferation-Resistance Assessment of Nuclear Energy Systems

Meng Yue, Lap-Yan Cheng, Robert A. Bari

Nuclear Technology / Volume 162 / Number 1 / April 2008 / Pages 26-44

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT08-A3931

Multiobjective Optimization of a Wire-Wrapped LMR Fuel Assembly

Wasim Raza, Kwang-Yong Kim

Nuclear Technology / Volume 162 / Number 1 / April 2008 / Pages 45-52

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT08-A3932

A TRU-Zr Metal-Fuel Sodium-Cooled Fast Subcritical Advanced Burner Reactor

W. M. Stacey, W. Van Rooijen, T. Bates, E. Colvin, J. Dion, J. Feener, E. Gayton, D. Gibbs, C. Grennor, J. Head, F. Hope, J. Ireland, A. Johnson, B. Jones, N. Mejias, C. Myers, A. Schmitz, C. Sommer, T. Sumner, L. Tschaepe

Nuclear Technology / Volume 162 / Number 1 / April 2008 / Pages 53-79

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT08-A3933

Nanofluids for Enhanced Economics and Safety of Nuclear Reactors: An Evaluation of the Potential Features, Issues, and Research Gaps

Jacopo Buongiorno, Lin-Wen Hu, Sung Joong Kim, Ryan Hannink, Bao Truong, Eric Forrest

Nuclear Technology / Volume 162 / Number 1 / April 2008 / Pages 80-91

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3934

Assessment of MARS-GCR Code for a New Reactor Cavity Cooling System Design

Yun-Je Cho, Hyoung-Kyu Cho, Goon-Cherl Park

Nuclear Technology / Volume 162 / Number 1 / April 2008 / Pages 92-106

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3935

Assessment of a High-Throughput Electrorefining Concept for a Spent Metallic Nuclear Fuel - I: Computational Fluid Dynamics Analysis

J. H. Lee, Y. H. Kang, S. C. Hwang, H. S. Lee, E. H. Kim, S. W. Park

Nuclear Technology / Volume 162 / Number 1 / April 2008 / Pages 107-116

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT08-A3936

Recovery of U-Pu Alloy from MOX Using a Pyroprocess Series

Shinichi Kitawaki, Tadahiro Shinozaki, Mineo Fukushima, Tsuyoshi Usami, Noboru Yahagi, Masaki Kurata

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 118-123

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3937

Engineering-Scale Liquid Cadmium Cathode Experiments

D. Vaden, S. X. Li, B. R. Westphal, K. B. Davies, T. A. Johnson, D. M. Pace

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 124-128

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3938

Cyclic Voltammetry Behavior of Americium at a Liquid Cadmium Electrode in LiCl-KCl Eutectic Melts

Hirokazu Hayashi, Mitsuo Akabori, Kazuo Minato

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 129-134

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3939

Application of Graphite as a Cathode Material for Electrorefining of Uranium

J. H. Lee, Y. H. Kang, S. C. Hwang, J. B. Shim, E. H. Kim, S. W. Park

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 135-143

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3940

Experimental Observations on the Roles of the Cadmium Pool in the Mark-IV Electrorefiner

Shelly X. Li

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 144-152

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3941

Effect of Process Variables During the Head-End Treatment of Spent Oxide Fuel

B. R. Westphal, K. J. Bateman, C. D. Morgan, J. F. Berg, P. J. Crane, D. G. Cummings, J. J. Giglio, M. W. Huntley, R. P. Lind, D. A. Sell

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 153-157

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3942

Fractional Release Behavior of Volatile and Semivolatile Fission Products During a Voloxidation and OREOX Treatment of Spent PWR Fuel

Kee Chan Song, Geun Il Park, Jung Won Lee, Jang Jin Park, Myung Seung Yang

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 158-168

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3943

Application of Electrochemical Reduction to Produce Metal Fuel Material from Actinide Oxides

Yoshiharu Sakamura, Takashi Omori, Tadashi Inoue

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 169-178

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT162-169

Modeling the Pyrochemical Reduction of Spent UO₂ Fuel in a Pilot-Scale Reactor

Michael F. Simpson, Steven D. Herrmann

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 179-183

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT162-179

An Electrochemical Reduction of Uranium Oxide in the Advanced Spent-Fuel Conditioning Process

Sang Mun Jeong, Jin-Mok Hur, Sun Seok Hong, Dae Seung Kang, Myoung Soo Choung, Chung-Seok Seo, Ji-Sup Yoon, Seong-Won Park

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 184-191

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT162-184

Chemical Behavior of Fission Products in the Pyrochemical Process

Jin-Mok Hur, Tack-Jin Kim, In-Kyu Choi, Jae Bum Do, Sun-Seok Hong, Chung-Seok Seo

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 192-198

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3947

The Ceramic Waste Form Process at Idaho National Laboratory

Stephen Priebe, Ken Bateman

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 199-207

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3948

A New Approach to Minimize Pyroprocessing Waste Salts Through a Series of Fission Product Removal Process

Eung-Ho Kim, Geun-Il Park, Yung-Zun Cho, Hee-Chul Yang

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 208-218

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3949

Alternative Technology for the Treatment of Waste LiCl Salt by Using Gelation with a Si-P-Al Material System and a Subsequent Thermal Conditioning Method

In-Tae Kim, Hwan-Seo Park, Seong-Won Park, Eung-Ho Kim

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 219-228

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3950

Absorption Characteristics of Fission Product Elements on Zeolite

Takeshi Tsukada, Keiju Takahashi

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 229-243

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3951

Synthesis of Actinide Nitrides in Molten Cadmium

Yasuo Arai, Takashi Iwai, Mitsuo Akabori, Kazuo Minato

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 244-249

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3952

A Feasibility Study for the Development of Alternative Methods to Treat a Spent TRISO Fuel

Jong-Hyeon Lee, Joon-Bo Shim, Eung-Ho Kim, Jae-Hyung Yoo, Seong-Won Park, Christine T. Snyder

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 250-258

Technical Paper / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3953

Current Status of Pyrochemical Reprocessing Research in India

K. Nagarajan, T. Subramanian, B. Prabhakara Reddy, P. R. Vasudeva Rao, Baldev Raj

Nuclear Technology / Volume 162 / Number 2 / May 2008 / Pages 259-263

Technical Note / First International Pyroprocessing Research Conference / dx.doi.org/10.13182/NT08-A3954

Characteristics and Sinterability of MOX Powder Prepared by the Microwave Heating Denitration Method

Koichi Asakura, Yoshiyuki Kato, Hirotaka Furuya

Nuclear Technology / Volume 162 / Number 3 / June 2008 / Pages 265-275

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT08-A3955

Stress Analysis of Coated Particle Fuel in Graphite of High-Temperature Reactors

B. Boer, A. M. Ougouag, J. L. Kloosterman, G. K. Miller

Nuclear Technology / Volume 162 / Number 3 / June 2008 / Pages 276-292

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT08-A3956

Assessing the Proliferation Resistance of Nuclear Fuel Cycle Systems Using a Fuzzy Logic-Based Barrier Method

Jun Li, Man-Sung Yim, David McNelis

Nuclear Technology / Volume 162 / Number 3 / June 2008 / Pages 293-307

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT08-A3957

An Analysis of Possible Impacts of Power Uprate on the Distributions of Erosion-Corrosion Wear Sites for a BWR Through CFD Simulation

Yuh Ming Ferng, Yung Shin Tseng, Bau Shei Pei, S. Long Wang, Chunkuan Shih, Tsun Fu Hung

Nuclear Technology / Volume 162 / Number 3 / June 2008 / Pages 308-322

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3958

Using Genetic Algorithms to Optimize the Helium Loop of a Very High Temperature Reactor

Christine Mansilla

Nuclear Technology / Volume 162 / Number 3 / June 2008 / Pages 323-332

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT08-A3959

A Cleanup Machine Using Reverse Osmosis Method to Remove Silica from Boric Acid Tank at Maanshan Nuclear Power Station

Chung-Hsien Liang, Kuo-Hwa Su

Nuclear Technology / Volume 162 / Number 3 / June 2008 / Pages 333-341

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT08-A3960

Materials Challenges for Generation IV Nuclear Energy Systems

T. R. Allen, K. Sridharan, L. Tan, W. E. Windes, J. I. Cole, D. C. Crawford, Gary S. Was

Nuclear Technology / Volume 162 / Number 3 / June 2008 / Pages 342-357

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT08-A3961

Results of a Full-Scale Liquid-Metal Leak Test in a Neutron Spallation Source Containment

K. Samec

Nuclear Technology / Volume 162 / Number 3 / June 2008 / Pages 358-378

Technical Paper / Accelerators / dx.doi.org/10.13182/NT08-A3962

Long-Term Uranium Supply Estimates

Erich A. Schneider, William C. Sailor

Nuclear Technology / Volume 162 / Number 3 / June 2008 / Pages 379-387

Technical Paper / Miscellaneous / dx.doi.org/10.13182/NT08-A3963