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Science and Technology of Nuclear Installations

ISSN Print: 1687-6075

ISSN Online:

主页: http://www.hindawi.com/journals/stni/

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Generator Development: Up-to-Date Recovery Technologies for Increasing the Effectiveness of Utilisation

Van So Le

Erratum to “Empirical Risk Analysis of Severe Reactor Accidents in Nuclear Power Plants after Fukushima”

Jan Christian Kaiser

The Application of Microdosimetric Principles to Radiation Hardness Testing

Jeremy D. Northum,Stephen B. Guetersloh

Thermomechanical Model and Bursting Tests to Evaluate the Risk of Swelling and Bursting of Modified 9Cr-1Mo Steel Steam Generator Tubes during a Sodium-Water Reaction Accident

C. Bertrand,A. Allou,F. Beauchamp,E. Pluyette,P. Defrasne,F. Baqué

Economic Analysis of the Management of the Nuclear Spent Fuel in Spain

B. Yolanda Moratilla Soria,David Echevarria-Lopez

Electrical Capacitance Probe Characterization in Vertical Annular Two-Phase Flow

Grazia Monni,Mario De Salve,Bruno Panella,Carlo Randaccio

Evaluation of and Productions Based on a High-Performance Cyclotron

J. Esposito,G. Vecchi,G. Pupillo,A. Taibi,L. Uccelli,A. Boschi,M. Gambaccini

Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores

Bruno Merk

Overview and Discussion of the OECD/NRC Benchmark Based on NUPEC PWR Subchannel and Bundle Tests

M. Avramova,A. Rubin,H. Utsuno

Unstructured Grids and the Multigroup Neutron Diffusion Equation

German Theler

BWR/5 Pressure-Suppression Pool Response during an SBO

Javier Ortiz-Villafuerte,Andrés Rodríguez-Hernández,Enrique Araiza-Martínez,Luis Fuentes-Márquez,Jorge Viais-Juárez

Modification of Neutron Kinetic Code for Plate Type Fuel Nuclear Reactor

Salah Ud-Din Khan,Shahab Ud-Din Khan,Yang Zhifei

Effective Atomic Number Determination of Rare Earth Oxides with Scattering Intensity Ratio

A. Tur？ucu,D. Demir,P. ？nder

Multiphysics Model Development and the Core Analysis for In Situ Breeding and Burning Reactor

Shengyi Si

Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1

C. J. Díez,J. J. Herrero,O. Cabellos,J. S. Martínez

K Shell X-Ray Fluorescence Parameters of Some Elements in the Atomic Range

Pinar Onder,Ahmet Tursucu,Demet Demir

Radioactive Iodine and Krypton Control for Nuclear Fuel Reprocessing Facilities

Nick R. Soelberg,Troy G. Garn,Mitchell R. Greenhalgh,Jack D. Law,Robert Jubin,Denis M. Strachan,Praveen K. Thallapally

A Solution-Based Approach for Mo-99 Production: Considerations for Nitrate versus Sulfate Media

Amanda J. Youker,Sergey D. Chemerisov,Michael Kalensky,Peter Tkac,Delbert L. Bowers,George F. Vandegrift

CFD for Subcooled Flow Boiling: Parametric Variations

Roland Rzehak,Eckhard Krepper

Uncertainty and Sensitivity Analyses of a Pebble Bed HTGR Loss of Cooling Event

Gerhard Strydom

Structural Integrity Evaluation of a Lab-Scale PCHE Prototype under the Test Conditions of HELP

Kee-nam Song,Sung-deok Hong

Influence of the Generator in-Growth Time on the Final Radiochemical Purity and Stability of Radiopharmaceuticals

L. Uccelli,A. Boschi,M. Pasquali,A. Duatti,G. Di Domenico,G. Pupillo,J. Esposito,M. Giganti,A. Taibi,M. Gambaccini

A THERP/ATHEANA Analysis of the Latent Operator Error in Leaving EFW Valves Closed in the TMI-2 Accident

Renato A. Fonseca,Antonio Carlos M. Alvim,Paulo Fernando F. Frutuoso e Melo,Marco Antonio B. Alvarenga

Economic Viability of Metallic Sodium-Cooled Fast Reactor Fuel in Korea

S. K. Kim,W. I. Ko,Yoon Hee Lee

Sensitivity Study on Availability of I&C Components Using Bayesian Network

Rahman Khalil Ur,Jinsoo Shin,Muhammad Zubair,Gyunyoung Heo,Hanseong Son

Online Fatigue-Monitoring Models with Consideration of Temperature Dependent Properties and Varying Heat Transfer Coefficients

HengLiang Zhang,Shi Liu,Danmei Xie,Yangheng Xiong,Yanzhi Yu,Yan Zhou,Rui Guo

Presentation and Discussion of the UAM/Exercise I-1b: “Pin-Cell Burn-Up Benchmark” with the Hybrid Method

O. Cabellos

Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System

A. Simonis,P. Poskas,A. Sirvydas,D. Grigaliuniene

Modeling Forced Flow Chemical Vapor Infiltration Fabrication of SiC-SiC Composites for Advanced Nuclear Reactors

Christian P. Deck,H. E. Khalifa,B. Sammuli,C. A. Back

German Spent Nuclear Fuel Legacy: Characteristics and High-Level Waste Management Issues

A. Schwenk-Ferrero

Radionuclide Transport in Fractured Rock: Numerical Assessment for High Level Waste Repository

Claudia Siqueira da Silveira,Antonio Carlos Marques Alvim,Jose de Jesus Rivero Oliva

The Fission-Based？？99Mo Production Process ROMOL-99 and Its Application to PINSTECH Islamabad

Rudolf Muenze,Gerd Juergen Beyer,Richard Ross,Gerhard Wagner,Dieter Novotny,Erik Franke,Mustansar Jehangir,Shahid Pervez,Ahmad Mushtaq

Solution of Point Reactor Neutron Kinetics Equations with Temperature Feedback by Singularly Perturbed Method

Wenzhen Chen,Jianli Hao,Ling Chen,Haofeng Li

SCALE Modeling of Selected Neutronics Test Problems within the OECD UAM LWR’s Benchmark

Luigi Mercatali,Kostadin Ivanov,Victor Hugo Sanchez

A Compact Gas-Cooled Fast Reactor with an Ultra-Long Fuel Cycle

Hangbok Choi,Robert W. Schleicher,Puja Gupta

Effect of Heaving Movement on Flow Instability in U-Tubes of Marine Steam Generator under Natural Circulation

Jianli Hao,Wenzhen Chen,De Zhang

Systems Thinking Safety Analysis: Nuclear Security Assessment of Physical Protection System in Nuclear Power Plants

Tae Ho Woo

Assessment of CTF Boiling Transition and Critical Heat Flux Modeling Capabilities Using the OECD/NRC BFBT and PSBT Benchmark Databases

Maria Avramova,Diana Cuervo

Projected Salt Waste Production from a Commercial Pyroprocessing Facility

Michael F. Simpson

Long-Term Station Blackout Accident Analyses of a PWR with RELAP5/MOD3.3

Andrej Pro？ek,Leon Cizelj

Assembly and Irradiation Modeling of Residual Stresses in Low-Enriched Uranium Foil-Based Annular Targets for Molybdenum-99 Production

Srisharan G. Govindarajan,Brian S. Graybill,Philip F. Makarewicz,Zhentao Xie,Gary L. Solbrekken

Analysis of the Natural Convection Flow in the Upper Plenum of the MONJU Reactor with Trio_U

Ulrich Bieder,Gauthier Fauchet

PSI Methodologies for Nuclear Data Uncertainty Propagation with CASMO-5M and MCNPX: Results for OECD/NEA UAM Benchmark Phase I

W. Wieselquist,T. Zhu,A. Vasiliev,H. Ferroukhi

Uncertainty Analyses Applied to the UAM/TMI-1 Lattice Calculations Using the DRAGON (Version 4.05) Code and Based on JENDL-4 and ENDF/B-VII.1 Covariance Data

Augusto Hernández-Solís,Christophe Demazière,Christian Ekberg

The Effective Convectivity Model for Simulation of Molten Metal Layer Heat Transfer in a Boiling Water Reactor Lower Head

Chi-Thanh Tran,Pavel Kudinov

Comparative Analysis of CTF and Trace Thermal-Hydraulic Codes Using OECD/NRC PSBT Benchmark Void Distribution Database

M. Avramova,A. Velazquez-Lozada,A. Rubin

Study of Thorium-Plutonium Fuel for Possible Operating Cycle Extension in PWRs

Klara Insulander Bj？rk,Cheuk Wah Lau,Henrik Nylén,Urban Sandberg

Design and Fabrication of Remote Welding Equipment in a Hot-Cell

Soosung Kim,Kihwan Kim,Jungwon Lee,Jinhyun Koh

Influence of the New Spanish Legislation concerning the Management of Nuclear Waste

B. Yolanda Moratilla Soria,Ainhoa Villar Lejarreta

Uncertainty and Sensitivity Studies with TRACE-SUSA and TRACE-DAKOTA by Means of Steady State BFBT Data

Wadim Jaeger,Victor Hugo Sánchez Espinoza,Francisco Javier Montero Mayorga,Cesar Queral

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