Science and Technology of Nuclear Installations - oalib

OALib Journal期刊
ISSN: 2333-9721
费用：99美元

投递稿件

为什么选择我们？ >>

- 开源期刊

- 同行审议

- 快速出刊

- 终身存储

- 免费检索

- 免费推广

- 更多...

- 搜索引擎

Science and Technology of Nuclear Installations

ISSN Print: 1687-6075

ISSN Online:

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

分享:

Design and Simulation of a New Model for Treatment by NCT

Seyed Alireza Mousavi Shirazi,Dariush Sardari

A Derivation of the Nonlocal Volume-Averaged Equations for Two-Phase Flow Transport

Gilberto Espinosa-Paredes

Validation of the Subchannel Code SUBCHANFLOW Using the NUPEC PWR Tests (PSBT)

Uwe Imke,Victor Hugo Sanchez

The Fukushima Event: The Outline and the Technological Background

Francesco D'Auria,Giorgio Galassi,Patricia Pla,Martina Adorni

Investigation of the Energy Correlations of Spallation Neutrons by Monte Carlo Simulations

Máté Szieberth,Gábor Radócz

PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications

Virpi Kouhia,Heikki Purhonen,Vesa Riikonen,Markku Puustinen,Riitta Kyrki-Rajam？ki,Juhani Vihavainen

Thermal Energetic Reactor with High Reproduction of Fission Materials

Vladimir M. Kotov

Subcritical Multiplication Parameters of the Accelerator-Driven System with 100？MeV Protons at the Kyoto University Critical Assembly

Jae-Yong Lim,Cheol Ho Pyeon,Takahiro Yagi,Tsuyoshi Misawa

Development of a Secondary SCRAM System for Fast Reactors and ADS Systems

Simon Vanmaercke,Gert Van den Eynde,Engelbert Tijskens,Yann Bartosiewicz

Effect of Weld Properties on the Crush Strength of the PWR Spacer Grid

Kee-nam Song,Sang-hoon Lee

Benchmark of Subchannel Code VIPRE-W with PSBT Void and Temperature Test Data

Y. Sung,R. L. Oelrich Jr.,C. C. Lee,N. Ruiz-Esquide,M. Gambetta,C. M. Mazufri

Numerical Simulation of Size Effects on Countercurrent Flow Limitation in PWR Hot Leg Models

I. Kinoshita,M. Murase,A. Tomiyama

Response Analysis on Electrical Pulses under Severe Nuclear Accident Temperature Conditions Using an Abnormal Signal Simulation Analysis Module

Kil-Mo Koo,Jin-Ho Song,Sang-Baik Kim,Kwang-Il Ahn,Won-Pil Baek,Kil-Nam Oh,Gyu-Tae Kim

Dynamic Analysis of a Pyroprocessing Coupled SFR Fuel Recycling

Fanxing Gao,Won Il Ko

Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA

Dae-Hyun Hwang,Seong-Jin Kim,Kyong-Won Seo,Hyuk Kwon

Counter Current Flow Limitation of Gas-Liquid Two-Phase Flow in Nearly Horizontal Pipe

Sigit Prayitno,R. A. Santoso,Deendarlianto,Thomas H？hne,Dirk Lucas

Simulation of the Lower Head Boiling Water Reactor Vessel in a Severe Accident

Alejandro Nu？ez-Carrera,Raúl Camargo-Camargo,Gilberto Espinosa-Paredes,Adrián López-García

Integral Test Facility PKL: Experimental PWR Accident Investigation

Klaus Umminger,Lars Dennhardt,Simon Schollenberger,Bernhard Schoen

Analyses of the OSU-MASLWR Experimental Test Facility

F. Mascari,G. Vella,B. G. Woods,F. D'Auria

The European Research on Severe Accidents in Generation-II and -III Nuclear Power Plants

Jean-Pierre Van Dorsselaere,Ari Auvinen,David Beraha,Patrick Chatelard,Christophe Journeau,Ivo Kljenak,Alexei Miassoedov,Sandro Paci,Th. Walter Tromm,Roland Zeyen

RELAP5 Analysis of OECD/NEA ROSA Project Experiment Simulating a PWR Loss-of-Feedwater Transient with High-Power Natural Circulation

Takeshi Takeda,Hideaki Asaka,Hideo Nakamura

Countercurrent Air-Water Flow in a Scale-Down Model of a Pressurizer Surge Line

Takashi Futatsugi,Chihiro Yanagi,Michio Murase,Shigeo Hosokawa,Akio Tomiyama

Interpretation of Local Flux Measurements in Subcritical Systems and Reactivity Determination

S. Dulla,P. Ravetto

Experimental Investigation of Rising Gas Bubble Characteristics from a Vertical Tube under CCFL Condition

Kunihito Matsumura,Fumito Kaminaga

Station Black-Out Analysis with MELCOR 1.8.6 Code for Atucha 2 Nuclear Power Plant

Analia Bonelli,Oscar Mazzantini,Martin Sonnenkalb,Marcelo Caputo,Juan Matias García,Pablo Zanocco,Marcelo Gimenez

Solutions without Space-Time Separation for ADS Experiments: Overview on Developments and Applications

B. Merk,V. Glivici-Cotru？？

SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review

Andrea Achilli,Cinzia Congiu,Roberta Ferri,Fosco Bianchi,Paride Meloni,Davor Grgi ,Milorad Dzodzo

Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213

Vladimir N. Blinkov,Oleg I. Melikhov,Vladimir I. Melikhov,Mikhail V. Davydov,Holger Wolff,Siegfried Arndt

Computational Fluid Dynamics Modeling of Steam Condensation on Nuclear Containment Wall Surfaces Based on Semiempirical Generalized Correlations

Pavan K. Sharma,B. Gera,R. K. Singh,K. K. Vaze

The Integral Test Facility Karlstein

Stephan Leyer,Michael Wich

Major Achievements and Prospect of the ATLAS Integral Effect Tests

Ki-Yong Choi,Yeon-Sik Kim,Chul-Hwa Song,Won-Pil Baek

Validation of Advanced Computer Codes for VVER Technology: LB-LOCA Transient in PSB-VVER Facility

A. Del Nevo,M. Adorni,F. D'Auria,O. I. Melikhov,I. V. Elkin,V. I. Schekoldin,M. O. Zakutaev,S. I. Zaitsev,M. Ben？ík

CATHARE Assessment of Natural Circulation in the PKL Test Facility during Asymmetric Cooldown Transients

Anis Bousbia Salah,Jacques Vlassenbroeck

PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Power Plants

Gy. ézs l,L. Perneczky,L. Szabados,I. Tóth

The LOBI Integral System Test Facility Experimental Programme

Carmelo Addabbo,Alessandro Annunziato

VOF Calculations of Countercurrent Gas-Liquid Flow in a PWR Hot Leg

M. Murase,A. Tomiyama,I. Kinoshita,Y. Utanohara,Chihiro Yanagi,T. Takata,A. Yamaguchi

Advanced Presentation of BETHSY 6.2TC Test Results Calculated by RELAP5 and TRACE

Andrej Pro？ek,Ovidiu-Adrian Berar

Failure Assessment Methodologies for Pressure-Retaining Components under Severe Accident Loading

J. Arndt,H. Grebner,J. Sievers

Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM

C. M. Allison,J. K. Hohorst,B. S. Allison,D. Konjarek,T. Bajs,R. Pericas,F. Reventos,R. Lopez

An Evaluation Methodology Development and Application Process for Severe Accident Safety Issue Resolution

Robert P. Martin

Monte Carlo Calculation of Fragment Distributions in Nuclear Reactions

A. Deppman,E. Andrade-II,P. C. R. Rossi,F. Garcia,J. R. Maiorino

Advanced Measuring (Instrumentation) Methods for Nuclear Installations: A Review

Wang Qiu-kuan,Lin Chang-hua,Yang Yan

Cylindrical Magnetorheological Fluid Variable Transmission Controlled by Shape-Memory Alloy

Song Chen,Kailin Jian,Xianghe Peng

Validation and Application of the Thermal Hydraulic System Code TRACE for Analysis of BWR Transients

V. H. Sánchez,M. Thieme,W. Tietsch

High-Temperature Structural Analysis of a Small-Scale PHE Prototype under the Test Condition of a Small-Scale Gas Loop

Kee-Nam Song,Sung-Deok Hong,Hong-Yoon Park

Assessment of TRACE CCFL Model with SBLOCA Experiment of IIST Facility

Jung-Hua Yang,Jong-Rong Wang,Hao-Tzu Lin,Chunkuan Shih

Detector Dead Time Determination and Optimal Counting Rate for a Detector Near a Spallation Source or a Subcritical Multiplying System

V. Bécares,J. Blázquez

Two-Group Theory of the Feynman-Alpha Method for Reactivity Measurement in ADS

Lénárd Pál,Imre Pázsit

Development of Tools, Instrumentation and Codes for Improving Periodic Examination and Repair of SFRs

Fran？ois Baqué,Frédéric Reverdy,Jean-Michel Augem,Julien Sibilo

Nuclear Level Density Parameters of and Deformed Target Isotopes Used on Accelerator-Driven Systems in Collective Excitation Modes

？eref Okuducu,Nisa N. Akt？,Sabahattin Akba？,M. Orhan Kansu

©2008-2020 OALib, Inc | Public user content licensed CC-BY 4.0 unless otherwise specified. OALib ISSN Online: 2333-9721 OALib ISSN Print: 2333-9705