Science and Technology of Nuclear Installations - oalib

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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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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

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

Current Status of Pyroprocessing Development at KAERI

Hansoo Lee,Geun-IL Park,Jae-Won Lee,Kweon-Ho Kang,Jin-Mok Hur,Jeong-Guk Kim,Seungwoo Paek,In-Tae Kim,IL-Je Cho

Uncertainty Analysis of Light Water Reactor Fuel Lattices

C. Arenas,R. Bratton,F. Reventos,K. Ivanov

Simulation Strategy for the Evaluation of Neutronic Properties of a Canadian SCWR Fuel Channel

G. Harrisson,G. Marleau

Improvement of Core Performance by Introduction of Moderators in a Blanket Region of Fast Reactors

Toshio Wakabayashi

Solution Monitoring Evaluated by Proliferation Risk Assessment and Fuzzy Optimization Analysis for Safeguards in a Reprocessing Process

Mitsutoshi Suzuki,Norichika Terao

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

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

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

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

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

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

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

Nonlinear Adaptive Dynamic Output-Feedback Power-Level Control of Nuclear Heating Reactors

Zhe Dong

Design, Development and Installation of Jordan Subcritical Assembly

Ned Xoubi

Recycling versus Long-Term Storage of Nuclear Fuel: Economic Factors

B. Yolanda Moratilla Soria,Maria Uris Mas,Mathilde Estadieu,Ainhoa Villar Lejarreta,David Echevarria-López

Estimating Alarm Thresholds for Process Monitoring Data under Different Assumptions about the Data Generating Mechanism

Tom Burr,Michael S. Hamada,John Howell,Misha Skurikhin,Larry Ticknor,Brian Weaver

Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea

Yeong-il Kim,Yong Bum Lee,Chan Bock Lee,Jinwook Chang,Chiwoong Choi

Analysis of the Processes in Spent Fuel Pools in Case of Loss of Heat Removal due to Water Leakage

Algirdas Kaliatka,Viktor Ognerubov,Virginijus Vileini？kis,Eugenijus U？puras

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

Ulrich Bieder,Gauthier Fauchet

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

Chi-Thanh Tran,Pavel Kudinov

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

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

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

Hangbok Choi,Robert W. Schleicher,Puja Gupta

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

Luigi Mercatali,Kostadin Ivanov,Victor Hugo Sanchez

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

Maria Avramova,Diana Cuervo

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

Jianli Hao,Wenzhen Chen,De Zhang

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

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

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

Kee-nam Song,Sung-deok Hong

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

Pinar Onder,Ahmet Tursucu,Demet Demir

Application of the Critical Heat Flux Look-Up Table to Large Diameter Tubes

M. El Nakla,M. Habib,W. Ahmed,A. Al-Sarkhi,R. Ben Mansour,M. Y. Al-Awwad

A Study of Self-Burial of a Radioactive Waste Container by Deep Rock Melting

Wenzhen Chen,Jianli Hao,Zhiyun Chen

Production Cycle for Large Scale Fission Mo-99 Separation by the Processing of Irradiated LEU Uranium Silicide Fuel Element Targets

Abdel-Hadi Ali Sameh

Numerical Simulation of Particle Flow Motion in a Two-Dimensional Modular Pebble-Bed Reactor with Discrete Element Method

Guodong Liu,Yining Zhang,Huilin Lu,Ersheng You,Xiang Li

Fine Distributed Moderating Material with Improved Thermal Stability Applied to Enhance the Feedback Effects in SFR Cores

Bruno Merk

Modeling of the ORNL PCA Benchmark Using SCALE6.0 Hybrid Deterministic-Stochastic Methodology

Mario Matijevi？,Dubravko Pevec,Kre？imir Trontl

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

Tae Ho Woo

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

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

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

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

History and Actual State of Non-HEU Fission-Based Mo-99 Production with Low-Performance Research Reactors

S. Dittrich

Assessment of Severe Accident Depressurization Valve Activation Strategy for Chinese Improved 1000？MWe PWR

Ge Shao,Lili Tong,Xuewu Cao

Immobilisation of Higher Activity Wastes from Nuclear Reactor Production of 99Mo

Martin W. A. Stewart,Eric R. Vance,Sam A. Moricca,Daniel R. Brew,Catherine Cheung,Tina Eddowes,Walter Bermudez

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