ANS / Publications / Journals / Nuclear Technology

Passive System Reliability Analysis: A Study on the Isolation Condenser

Luciano Burgazzi

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 3-9

Technical Paper / dx.doi.org/10.13182/NT139-3-9

Severe Accident Related Research and Development at Forschungszentrum Karlsruhe for Present and Future Needs

Werner Scholtyssek, Gerhard Heusener, Fritz Hofmann, Helmut Plitz

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 10-20

Technical Paper / dx.doi.org/10.13182/NT02-A3298

The Model of the IBR-2 Pulsed Reactor Dynamics and Investigation of Pulse Energy Stabilization

Alexander K. Popov, Juri N. Pepyolyshev, Eugene A. Bondarchenko

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 21-29

Technical Paper / dx.doi.org/10.13182/NT02-A3299

Regulatory Concerns on the In-Containment Water Storage System of the Korean Next Generation Reactor

Hyung-Joon Ahn, Jae-Hun Lee, Young-Seok Bang, Hho-Jung Kim

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 30-35

Technical Note / dx.doi.org/10.13182/NT02-A3300

General Safety Criteria for the Korean Next Generation Reactor

Jae-Hun Lee, Woong-Sik Kim, Young Gill Yune, Jae-Seong Lee

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 36-41

Technical Note / dx.doi.org/10.13182/NT02-A3301

Korean Standard Nuclear Power Plant Response to Common Mode Failure of the Digital Plant Protection System

Cheol Shin Lee, Chan Eok Park, Chul Jin Choi, Jong Tae Seo

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 42-49

Technical Note / dx.doi.org/10.13182/NT02-A3302

Definition and Analysis of an Experimental Benchmark on Shutdown Rod Worths in LEU-HTR Configurations

Rakesh Chawla, Om Parkash Joneja, Marc Rosselet, Tony Williams

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 50-60

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT02-A3303

A Methodology for Selecting High Thermal-Hydraulic Performance Fuel Configurations for Tightly Packed Epithermal Core Designs

Antonino Romano, Neil E. Todreas

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 61-71

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT02-A3304

Empirical and Computational Pressure Drop Correlations for Pressurized Water Reactor Fuel Spacer Grids

Wang Kee In, Dong Seok Oh, Tae Hyun Chun

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 72-79

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3305

Criticality Analysis of MOX and LEU Assemblies for Transport and Storage at the Balakovo Nuclear Power Plant

Sedat Goluoglu, R. T. Primm III

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 80-88

Technical Note / Criticality of Nuclear Materials / dx.doi.org/10.13182/NT02-A3306

Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit

John C. Wagner, Charlotta E. Sanders

Nuclear Technology / Volume 139 / Number 2 / August 2002 / Pages 91-126

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT02-A3307

Fuel-Coolant Interactions: Visualization and Mixing Measurements

Eric P. Loewen, Riccardo Bonazza, Michael L. Corradini, Robert E. Johannesen

Nuclear Technology / Volume 139 / Number 2 / August 2002 / Pages 127-144

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3308

Transport Characteristics of Selected Pressurized Water Reactor LOCA-Generated Debris

Arup K. Maji, Daseri V. Rao, Bruce Letellier, Luke Bartlein, Brooke Marshall

Nuclear Technology / Volume 139 / Number 2 / August 2002 / Pages 145-155

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3309

Building Up an On-Line Plant Information System for the Emergency Response Center of the Hungarian Nuclear Safety Directorate

János Végh, Csaba Major, Csaba Horváth, Zoltán Hózer, Ferenc Adorján, Iván Lux, Kristóf Horváth

Nuclear Technology / Volume 139 / Number 2 / August 2002 / Pages 156-166

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT02-A3310

Test of Actinide-Lanthanide Separation in an Aluminum-Based Pyrochemical System

Laurence Rault, Murielle Heusch, Michel Allibert, Florent Lemort, Xavier Deschanel, Roger Boen

Nuclear Technology / Volume 139 / Number 2 / August 2002 / Pages 167-174

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT02-A3311

Startup of the Fission Converter Epithermal Neutron Irradiation Facility at the MIT Reactor

Thomas H. Newton, Jr., Kent J. Riley, Peter J. Binns, Gordon E. Kohse, Lin-Wen Hu, Otto K. Harling

Nuclear Technology / Volume 139 / Number 2 / August 2002 / Pages 175-183

Technical Paper / Radiation Biology and Medicine / dx.doi.org/10.13182/NT02-A3312

Simulation and Analysis of Experimental Blowdown and Small-Break Loss-of-Coolant Scenarios with RETRAN-3D

Rafael Macian, Paul Coddington

Nuclear Technology / Volume 139 / Number 3 / September 2002 / Pages 185-204

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3313

Visualization and Measurement of Subcooled Water Jet Injection into High-Temperature Melt by Using High-Frame-Rate Neutron Radiography

Yasuteru Sibamoto, Yutaka Kukita, Hideo Nakamura

Nuclear Technology / Volume 139 / Number 3 / September 2002 / Pages 205-220

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3314

Adequacy of the Heat-Mass Transfer Analogy to Simulate Containment Atmospheric Cooling in the New Generation of Advanced Nuclear Reactors: Experimental Confirmation

Luis E. Herranz, Antonio Campo

Nuclear Technology / Volume 139 / Number 3 / September 2002 / Pages 221-232

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3315

Development and Assessment of the Appendix K Version of RELAP5-3D for LOCA Licensing Analysis

Thomas K. S. Liang, Chin-Jang Chang, Huan-Jen Hung

Nuclear Technology / Volume 139 / Number 3 / September 2002 / Pages 233-252

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT02-A3316

Development of the Diamex Process for Treating PHWR High-Level Liquid Waste

L. B. Kumbhare, D. R. Prabhu, G. R. Mahajan, S. Sriram, V. K. Manchanda, L. P. Badheka

Nuclear Technology / Volume 139 / Number 3 / September 2002 / Pages 253-262

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT02-A3317

A Real-Time Graphic Simulator to Monitor Spent Nuclear Fuel Dismantlement Devices

Soon-Hyuk Hong, Jae Wook Jeon, Tai Gil Song, Jong Youl Lee, Sung Hyun Kim, Ji Sup Yoon

Nuclear Technology / Volume 139 / Number 3 / September 2002 / Pages 263-273

Technical Note / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT02-A3318