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Home / Publications / Journals / Nuclear Technology / Volume 187 / Number 1

Volume 187

Number 1

The SABrR Concept for A Fission-Fusion Hybrid 238U-to-239Pu Fissile Production Reactor

C. L. Stewart, W. M. Stacey

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 1-14

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-102

Resolution of Fission and Fusion Technology Integration Issues: An Upgraded Design Concept for the Subcritical Advanced Burner Reactor

W. M. Stacey, C. L. Stewart, J.-P. Floyd, T. M. Wilks, A. P. Moore, A. T. Bopp, M. D. Hill, S. Tandon, and A. S. Erickson

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 15-43

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-96

Effects of Shape and Size on Countercurrent Flow Limitation in Flow Channels Simulating A PWR Hot Leg

Ikuo Kinoshita, Michio Murase, Yoichi Utanohara, Dirk Lucas, Christophe Vallée, and Akio Tomiyama

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 44-56

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-32

Clogging of HEPA Filters By Soot During Fire Events in Nuclear Fuel Cycle Facilities

Takashi Ishibashi, Susumu Tsuchino, Shiro Matsumoto, and Fumio Kasahara

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 57-68

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-94

Efficient Digital Implementation of Signal Processing Algorithms in State-Of-The-Art Field-Programmable Gate Arrays for Gamma-Ray Spectroscopy

Fateme Fahiman, Mahdi Kafaee, Ali Moussavi-Zarandi, and Meisam Fahiman

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 69-81

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-65

Deployment Strategies for Wireless Sensor Networks in Nuclear Power Plants

Ataul Bariand, Jin Jiang

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 82-95

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT13-1

Computer-Based Investigative Techniques: A Comparison of Dose Using the MCNP Code for Optically Stimulated Light Dosimeters

Thomas B. Rezentes, Mark A. Prelas, Eric Lukosi, Matthew L. Watermann, Jack Crawford, and Richard H. Olsher

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 96-102

Technical Note / Radiation Transport and Protection / dx.doi.org/10.13182/NT11-105

Impact of Local Burnup on Prediction of Power Density in the NIST Research Reactor

Nicholas R. Brown, Albert L. Hanson, and David J. Diamond

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 103-116

Technical Note / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-20

 

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