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OALib Journal期刊
ISSN: 2333-9721
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Science and Technology of Nuclear Installations
ISSN Print: 1687-6075
ISSN Online:
主页:
http://www.hindawi.com/journals/stni/
分享:
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Role of Passive Safety Systems in Chinese Nuclear Power Development
X. Cheng
,
Y. H. Yang
,
Y. Ouyang
,
H. X. Miao
The SPES3 Experimental Facility Design for the IRIS Reactor Simulation
Mario Carelli
,
Lawrence Conway
,
Milorad Dzodzo
,
Andrea Maioli
,
Luca Oriani
,
Gary Storrick
,
Bojan Petrovic
,
Andrea Achilli
,
Gustavo Cattadori
,
Cinzia Congiu
,
Roberta Ferri
,
Marco Ricotti
,
Davide Papini
,
Fosco Bianchi
,
Paride Meloni
,
Stefano Monti
,
Fabio Berra
,
Davor Grgic
,
Graydon Yoder
,
Alessandro Alemberti
Gas-Cooled Fast Reactor: A Historical Overview and Future Outlook
W. F. G. van Rooijen
The Influence of the Packing Factor on the Fuel Temperature Hot Spots in a Particle-Bed GCFR
G. Lomonaco
,
W. Grassi
,
N. Cerullo
Application of REPAS Methodology to Assess the Reliability of Passive Safety Systems
Franco Pierro
,
Dino Araneo
,
Giorgio Galassi
,
Francesco D'Auria
Closed Fuel Cycle and Minor Actinide Multirecycling in a Gas-Cooled Fast Reactor
W. F. G. van Rooijen
,
J. L. Kloosterman
Computational Methods for Multidimensional Neutron Diffusion Problems
Song Han
,
Sandra Dulla
,
Piero Ravetto
The Use of Th in HTR: State of the Art and Implementation in Th/Pu Fuel Cycles
Guido Mazzini
,
Eleonora Bomboni
,
Nicola Cerullo
,
Emil Fridman
,
Guglielmo Lomonaco
,
Eugene Shwageraus
Gas Cooled Fast Reactor Research and Development in the European Union
Richard Stainsby
,
Karen Peers
,
Colin Mitchell
,
Christian Poette
,
Konstantin Mikityuk
,
Joe Somers
Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code
Maria Cristina Galassi
,
Pierre Coste
,
Christophe Morel
,
Fabio Moretti
Mechanistic Multidimensional Modeling of Forced Convection Boiling Heat Transfer
Michael Z. Podowski
,
Raf M. Podowski
Experiments and Modelling Techniques for Heat and Mass Transfer in Light Water Reactors
W. Ambrosini
,
M. Bucci
,
N. Forgione
,
A. Manfredini
,
F. Oriolo
Physics Features of TRU-Fueled VHTRs
Tom G. Lewis III
,
Pavel V. Tsvetkov
GASFLOW Validation with Panda Tests from the OECD SETH Benchmark Covering Steam/Air and Steam/Helium/Air Mixtures
Peter Royl
,
John R. Travis
,
Wolfgang Breitung
,
Jongtae Kim
,
Sang Baik Kim
Review of Available Data for Validation of Nuresim Two-Phase CFD Software Applied to CHF Investigations
D. Bestion
,
H. Anglart
,
D. Caraghiaur
,
P. Péturaud
,
B. Smith
,
M. Andreani
,
B. Niceno
,
E. Krepper
,
D. Lucas
,
F. Moretti
,
M. C. Galassi
,
J. Macek
,
L. Vyskocil
,
B. Koncar
,
G. Hazi
Modelling of HTR Confinement Behaviour during Accidents Involving Breach of the Helium Pressure Boundary
Joan Fontanet
,
Luis E. Herranz
,
Alastair Ramlakan
,
Lolan Naicker
Non-Boussinesq Integral Model for Horizontal Turbulent Buoyant Round Jets
J. Xiao
,
J.R. Travis
,
W. Breitung
GCFR Coupled Neutronic and Thermal-Fluid-Dynamics Analyses for a Core Containing Minor Actinides
Diego Castelliti
,
Eleonora Bomboni
,
Nicola Cerullo
,
Guglielmo Lomonaco
,
Carlo Parisi
CFD Simulation of Thermal-Hydraulic Benchmark V1000CT-2 Using ANSYS CFX
Thomas H hne
New Methods for Evaluation of Spent Fuel Condition during Long-Term Storage in Slovakia
M. Miklo
,
V. Kr jak
Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors
Lap-Yan Cheng
,
Thomas Y. C. Wei
Modeling of Multisize Bubbly Flow and Application to the Simulation of Boiling Flows with the Neptune_CFD Code
Christophe Morel
,
Jér me M. Laviéville
Computational Fluid Dynamics for Gas-Liquid Flows
Dirk Lucas
,
Iztok Tiselj
,
Yassin A. Hassan
,
Fabio Moretti
Erratum for “Assessment of LWR-HTR-GCFR Integrated Cycle”
Eleonora Bomboni
,
Nicola Cerullo
,
Guglielmo Lomonaco
Passive Safety Systems in Advanced PWRs
Xu Cheng
,
Yanhua Yang
,
Walter Ambrosini
,
Dino A. Araneo
Innovative Gas-Cooled Reactors
Jan Leen Kloosterman
,
Jim Kuijper
,
Colin Mitchell
,
Guglielmo Lomonaco
Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures
Alessandro Petruzzi
,
Francesco D'Auria
Deterministic Analysis of Natural Circulation Events at the Ignalina NPP
Algirdas Kaliatka
,
Eugenijus Uspuras
,
Virginijus Vileiniskis
Effect of Loop Diameter on the Steady State and Stability Behaviour of Single-Phase and Two-Phase Natural Circulation Loops
P. K. Vijayan
,
A. K. Nayak
,
D. Saha
,
M. R. Gartia
Wastes Management Through Transmutation in an ADS Reactor
Barbara Calgaro
,
Barbara Vezzoni
,
Nicola Cerullo
,
Giuseppe Forasassi
,
Bernard Verboomen
Use of the Natural Circulation Flow Map for Natural Circulation Systems Evaluation
M. Cherubini
,
W. Giannotti
,
D. Araneo
,
F. D'Auria
A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors
E. Bomboni
,
N. Cerullo
,
G. Lomonaco
,
V. Romanello
Machine Learning of the Reactor Core Loading Pattern Critical Parameters
Kre imir Trontl
,
Dubravko Pevec
,
Tomislav muc
Power Distribution and Possible Influence on Fuel Failure in WWER-1000
Ján Miku
Flow Instabilities in Boiling Two-Phase Natural Circulation Systems: A Review
A. K. Nayak
,
P. K. Vijayan
Flow Stagnation under Single and Two-Phase Natural Circulation Conditions in the APEX-CE Test Facility
José N. Reyes Jr.
International Standard Problems and Small Break Loss-of-Coolant Accident (SBLOCA)
N. Aksan
Natural Circulation Characteristics at Low-Pressure Conditions through PANDA Experiments and ATHLET Simulations
Domenico Paladino
,
Max Huggenberger
,
Frank Sch fer
Regulatory Scenario for the Acceptance of Uncertainty Analysis Methodologies for the LB-LOCA and the Brazilian Approach
Maria Regina Galetti
RELAP5/MOD3.3 Code Validation with Plant Abnormal Event
Andrej Pro ek
,
Borut Mavko
Numerical Simulations and Design Optimization of the PHT Loop of Natural Circulation BWR
G. V. Durga Prasad
,
G. Gopa Kishor
,
Manmohan Pandey
,
Uday S. Dixit
Evaluation of Heat Removal from RBMK-1500 Core Using Control Rods Cooling Circuit
A. Kaliatka
,
E. Uspuras
,
M. Vaisnoras
Accident Management in VVER-1000
F. D'Auria
,
A. Suslov
,
N. Muellner
,
G. Petrangeli
,
M. Cherubini
Coupling of Modular High-Temperature Gas-Cooled Reactor with Supercritical Rankine Cycle
Shutang Zhu
,
Ying Tang
,
Kun Xiao
,
Zuoyi Zhang
Modelling of the Production of Source Neutrons from Low-Voltage Accelerated Deuterons on Titanium-Tritium Targets
A. Milocco
,
A. Trkov
Fission Product Transport and Source Terms in HTRs: Experience from AVR Pebble Bed Reactor
Rainer Moormann
Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor
Giacomino Bandini
,
Paride Meloni
,
Massimiliano Polidori
,
Maddalena Casamirra
,
Francesco Castiglia
,
Mariarosa Giardina
Simulation of Boiling Flow Experiments Close to CHF with the Neptune_CFD Code
Bo tjan Kon ar
,
Borut Mavko
Use of Nuclear Data Sensitivity and Uncertainty Analysis for the Design Preparation of the HCLL Breeder Blanket Mockup Experiment for ITER
I. Kodeli
CFD Code Validation against Stratified Air-Water Flow Experimental Data
F. Terzuoli
,
M. C. Galassi
,
D. Mazzini
,
F. D'Auria
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