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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT14-141
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT15-19
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT15-63
