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Volume 193

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Number 1

Validation of a Three-Dimensional Model of EBR-II and Assessment of RELAP5-3D Based on SHRT-17 Test

Alessandro Del Novo, Emanuela Martelli

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 1-14

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-152

Comparison of the PHISICS/RELAP5-3D Ring and Block Model Results for Phase I of the OECD/NEA MHTGR-350 Benchmark

G. Strydom, A. S. Epiney, A. Alfonsi, C. Rabiti

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 15-35

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-146

Comparison of MYRRHA RELAP5 MOD 3.3 and RELAP5-3D Models on Steady State and PLOF Transient

D. Castelliti, T. Hamidouche

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 36-46

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-139

Thirty Years’ Experience in RELAP5 Applications at GRNSPG & NINE

A. Petruzzi, M. Cherubini, F. D'Auria

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 47-87

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-144

Impact of Pressure Relief Holes on Core Coolability for a PWR During a Large-Break Loss-of-Coolant Accident with Core Blockage Using RELAP5-3D

Rodolfo Vaghetto, Timothy Crook, Alessandro Vanni, Yassin A. Hassan

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 88-95

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-147

Content, Completeness, and Consistency of Analytical Models for Regulatory Consideration

Robert P. Martin

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 96-112

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-143

The BEPU Evaluation Model with RELAP5-3D for the Licensing of the Atucha-II NPP

A. Petruzzi, M. Cherubini, M. Lanfredini, F. D’Auria, O. Mazzantini

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 113-160

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-145

BWR Station Blackout: A RISMC Analysis Using RAVEN and RELAP5-3D

D. Mandelli, C. Smith, T. Riley, J. Nielsen, A. Alfonsi, J. Cogliati, C. Rabiti, J. Schroeder

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 161-174

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-142

Simulation of AER-DYN-002 and AER-DYN-003 Control Rod Ejection Benchmarks by RELAP5-3D/PHISICS Coupled Codes

P. Balestra, C. Parisi, A. Alfonsi, C. Rabiti

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 175-182

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-138

Development of an Integrated Code System Using R5EXEC and RELAP5-3D

David Aumiller, Francis Buschman, Edward Tomlinson, Daniel Gill

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 183-199

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT15-5

RelapManager: A Safety Analysis Automation Framework and Software for RELAP5-3D

Robert P. Martin, Simone H. Morgan, Christopher Cragg

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 200-212

Technical Paper / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-140

RELAP5-3D User Tools

J. Hope Forsmann

Nuclear Technology / Volume 193 / Number 1 / January 2016 / Pages 213-217

Technical Note / Special Issue on the RELAP5-3D Computer Code / dx.doi.org/10.13182/NT14-141

Number 2

Economic Analysis of Complex Nuclear Fuel Cycles with NE-COST

Francesco Ganda, Brent Dixon, Edward Hoffman, Taek K. Kim, Temitope Taiwo, Roald Wigeland

Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 219-233

Technical Paper / dx.doi.org/10.13182/NT14-113

A Steady-State Thermal-Hydraulic Analysis Method for Prismatic High-Temperature Gas-Cooled Reactors

A. J. Huning, S. Garimella, F. Rahnema

Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 234-246

Technical Paper / dx.doi.org/10.13182/NT15-14

RPV Depressurization Strategy Analysis for Chinshan Nuclear Power Plant by Using MAAP5

Yu-Huai Shih, Te-Chuan Wang

Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 247-258

Technical Paper / dx.doi.org/10.13182/NT14-118

Modernization and Capability Investigation of the MATRIX Electromagnetic Pump Analysis Code

Seth Strege, Serkan Yilmaz, Pradip Saha, Eric P. Loewen

Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 259-275

Technical Paper / dx.doi.org/10.13182/NT14-120

Loose Parts Localization Delay Calculation Method Based on CWT and Hilbert Envelope

Li-Xian Fang, Dong-Shan Zhao, Tian-Tian Ji, Fu Zeng, Wei Zhang

Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 276-286

Technical Paper / dx.doi.org/10.13182/NT15-12

Lattice Parameter Behavior with Different Nd and O Concentrations in (U1−yNdy)O2±x Solid Solution

Seung Min Lee, Travis W. Knight, Stewart L. Voit, Rozaliya I. Barabash

Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 287-296

Technical Paper / dx.doi.org/10.13182/NT14-136

Chemical Durability of Gamma-Irradiated Glass Fibrous Insulation

Mária Chromčíková, Jana Vokelová, Jaroslava Michálková, Marek Liška, Jan Macháček, Ondrej Gedeon, Vojtech Soltész

Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 297-305

Technical Paper / dx.doi.org/10.13182/NT15-22

Evaluation of Corrosion Inhibitors for Carbon Steel and Type 304 Stainless Steel in Nitrilotriacetic Acid Medium at High Temperature

Valil S. Sathyaseelan, Appadurai L. Rufus, Sankaralingam Velmurugan

Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 306-317

Technical Paper / dx.doi.org/10.13182/NT15-27

A Concept for an Emergency Countermeasure Against Radioactive Wastewater Generated in Severe Nuclear Accidents Like the Fukushima Daiichi Disaster

Kwang-Wook Kim, Keun-Young Lee, Eil-Hee Lee, Yeji Baek, Dong-Yong Chung, Jei-Kwon Moon

Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 318-329

Technical Paper / dx.doi.org/10.13182/NT15-23

Material Irradiation Technology Using Capsules at HANARO

Man Soon Cho, Kee Nam Choo, Seong Woo Yang

Nuclear Technology / Volume 193 / Number 2 / February 2016 / Pages 330-339

Technical Note / dx.doi.org/10.13182/NT15-19

Number 3

Model Uncertainty in Severe Accident Calculations: A Structural Methodology with Application to LOFT LP-FP-2 Experiment

Seyed Mohsen Hoseyni, Mohammad Pourgol-Mohammad

Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 341-363

Technical Paper / dx.doi.org/10.13182/NT15-47

A Core Design Study for a Small Modular Boiling Water Reactor with Long-Life Core

Zeyun Wu, Won Sik Yang, Shanbin Shi, Mamoru Ishii

Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 364-374

Technical Paper / dx.doi.org/10.13182/NT15-58

Modeling a Porous Region for Natural Convection Heat Transfer and Experimental Validation in Slender Cylindrical Geometries

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer

Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 375-390

Technical Paper / dx.doi.org/10.13182/NT15-56

Analysis of the LIFT Variance-Reduction Method Applied to Monte Carlo Radiation Transport Simulations of a Realistic Nonproliferation Test Problem

Elanchezhian Somasundaram, Todd S. Palmer

Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 391-403

Technical Paper / dx.doi.org/10.13182/NT15-43

The Molten Salt Reactor Point-Kinetic Component of Neutron Noise in Two-Group Diffusion Theory

V. Dykin, I. Pázsit

Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 404-415

Technical Paper / dx.doi.org/10.13182/NT15-71

VEGAS: A Fuel Cycle Simulation and Preconditioner Tool with Restricted Material Balances

E. A. Schneider, U. B. Phathanapirom

Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 416-429

Technical Paper / dx.doi.org/10.13182/NT15-6

The Immobilization of Triuranium Octoxide by Gadolinium Zirconate

Li Liu, Long Fan, Xirui Lu

Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 430-433

Technical Paper / dx.doi.org/10.13182/NT15-31

Hydrogen Peroxide Production by Gamma Radiolysis of Sodium Chloride Solutions Containing a Small Amount of Bromide Ion

Kuniki Hata, Hiroyuki Inoue, Takao Kojima, Akihiro Iwase, Shigeki Kasahara, Satoshi Hanawa, Fumiyoshi Ueno, Takashi Tsukada

Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 434-443

Technical Paper / dx.doi.org/10.13182/NT15-32

Numerical Solution of Stochastic Point-Kinetics Neutron Equation with Fuzzy Parameters

S. Nayak, S. Chakraverty

Nuclear Technology / Volume 193 / Number 3 / March 2016 / Pages 444-456

Technical Note / dx.doi.org/10.13182/NT15-63

 
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