ANS / Publications / Journals / Nuclear Technology

Optimal Shielding Design for Minimum Materials Cost or Mass

Robert D. Woolley

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 191-207

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-133

Radiation Protection Study for the First Korea Heavy-Ion Medical Accelerator Facility

Oyeon Kum, Seung Uk Heo, Sang Hyoun Choi, Yongkeun Song, Sung-Ho Cho

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 208-214

Technical Paper / Accelerators / dx.doi.org/10.13182/NT14-121

Design and Performance Test of Photosensitive Glass–Based Nonfocused X-Ray Antiscattering Grid by Using MCNP Simulation

Jun Woo Bae, Hee Reyoung Kim

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 215-221

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT14-131

Experiment Design of Secondary Neutron and Charged-Particle Measurement with Stopping Targets Bombarded by 100 and 230 MeV/amu ⁴He Ions

Pi-En Tsai, Lawrence H. Heilbronn

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 222-231

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-130

Enhancements to the MCNP6 Background Source

Garrett E. McMath, Gregg W. McKinney

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 232-239

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-134

Computational Assessment of Naturally Occurring Neutron and Photon Background Radiation Produced by Extraterrestrial Sources

Thomas M. Miller, Wouter C. de Wet, Bruce W. Patton

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 240-249

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT14-153

Testing the Delayed Gamma Capability in MCNP6

R. A. Weldon, Jr., M. L. Fensin, G. W. McKinney

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 250-258

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-127

Analog Neutron Transport for Nuclear Instrumentation Applications with the Monte Carlo Code TRIPOLI-4

O. Petit, E. Dumonteil

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 259-263

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-128

Enhanced Hybrid Diffusion-Transport Spatial Homogenization Method

Gabriel Kooreman, Farzad Rahnema

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 264-277

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT14-150

Activation Neutronics for a Swiss Pressurized Water Reactor

Manuel Pantelias, Benjamin Volmert

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 278-285

Technical Paper / Nuclear Plant Operations and Controls / dx.doi.org/10.13182/NT15-13

The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation

Ahmad M. Ibrahim, Douglas E. Peplow, Robert E. Grove, Joshua L. Peterson, Seth R. Johnson

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 286-298

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT15-1

Radiation Mapping at JET and ITER Using Advanced Computational Acceleration Techniques and Tools

Jonathan Naish, Frances Fox, Zamir Ghani, Michael Loughlin, Lee Packer, Andrew Turner

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 299-307

Technical Paper / Accelerators / dx.doi.org/10.13182/NT14-132

Development of the Standalone Package for Enhanced Estimation of Dose Distribution for Space Radiation Applications

Wouter C. de Wet, Lawrence W. Townsend, X. George Xu, Whitney J. Smith

Nuclear Technology / Volume 192 / Number 3 / December 2015 / Pages 308-313

Technical Note / Radiation Biology / dx.doi.org/10.13182/NT15-21