Works matching DE "COOLANT loss in water cooled reactors"

Results: 45

Testing of five 30-year-old prestressed concrete beams.

Published in:

PCI Journal, 2010, p. 50, doi. 10.15554/pcij.09012010.50.58

By:

Lundqvist, Peter;
Riihimäki, Juha

Publication type:

Article

Determination of the region of vibroacoustic resonances of coolant and fuel assemblies in advanced enhanced-power reactors.

Published in:

Atomic Energy, 2010, v. 108, n. 3, p. 194, doi. 10.1007/s10512-010-9276-1

By:

Proskuryakov, K.;
Novikov, K.

Publication type:

Article

Supercritical-pressure water cooled thermal reactor with uranium–plutonium–thorium fuel cycle and bidirectional coolant flow articles.

Published in:

Atomic Energy, 2009, v. 106, n. 5, p. 305, doi. 10.1007/s10512-009-9169-3

By:

A. Glebov;
A. Klushin

Publication type:

Article

Method for fast separation of iodine isotopes on silver-containing membranes.

Published in:

Atomic Energy, 2008, v. 104, n. 4, p. 313, doi. 10.1007/s10512-008-9034-9

By:

V. Epimakhov;
S. Mysik;
V. Kobekov;
T. Epimakhov

Publication type:

Article

Evaluation of the technological parameters of a high-temperature reactor with solid coolant in the electricity generating regime.

Published in:

Atomic Energy, 2008, v. 104, n. 4, p. 268, doi. 10.1007/s10512-008-9027-8

By:

A. Dmitriev;
O. Kavun;
N. Khrennikov;
N. Piskunova

Publication type:

Article

IN-VESSEL RETENTION OF MOLTEN CORIUM: LESSONS LEARNED AND OUTSTANDING ISSUES.

Published in:

Nuclear Technology, 2008, v. 161, n. 3, p. 210, doi. 10.13182/NT08-A3924

By:

Rempe, J. L.;
Suh, K. Y.;
Cheung, F. B.;
Kim, S. B.

Publication type:

Article

DEVELOPMENT OF PARAMETER-IDENTIFICATION CAPABILITY FOR MAAP4 CODE.

Published in:

Nuclear Technology, 2008, v. 161, n. 3, p. 203, doi. 10.13182/NT08-A3923

By:

Chun-Sheng Chien;
Shih-Jen Wang;
Show-Chyuan Chiang

Publication type:

Article

FEASIBILITY OF DESIGNING THE ENCAPSULATED NUCLEAR HEAT SOURCE REACTOR WITH NEGATIVE VOID REACTIVITY FEEDBACK.

Published in:

Nuclear Technology, 2007, v. 160, n. 3, p. 257, doi. 10.13182/NT07-A3898

By:

Okawa, Tsuyoshi;
Greenspan, Ehud

Publication type:

Article

IDENTIFICATION OF LOSS-OF-COOLANT ACCIDENTS IN LWRs BY INVERSE MODELS.

Published in:

Nuclear Technology, 2004, v. 147, n. 2, p. 216, doi. 10.13182/NT04-A3527

By:

Cholewa, Wojciech;
Frid, Wiktor;
Bednarski, Marcin

Publication type:

Article

Laser-based sensor for a coolant leak detection in a nuclear reactor.

Published in:

Applied Physics B: Lasers & Optics, 2010, v. 100, n. 2, p. 437, doi. 10.1007/s00340-010-3947-4

By:

Kim, T.-S.;
Park, H.;
Ko, K.;
Lim, G.;
Cha, Y.-H.;
Han, J.;
Jeong, D.-Y.

Publication type:

Article

A Review of Dangerous Dust in Fusion Reactors: from Its Creation to Its Resuspension in Case of LOCA and LOVA.

Published in:

Energies (19961073), 2016, v. 9, n. 8, p. 578, doi. 10.3390/en9080578

By:

Malizia, Andrea;
Poggi, Luigi Antonio;
Ciparisse, Jean-François;
Rossi, Riccardo;
Bellecci, Carlo;
Gaudio, Pasquale

Publication type:

Article

Prospects for and problems of using light-water supercritical-pressure coolant in nuclear reactors in order to increase the efficiency of the nuclear fuel cycle.

Published in:

Physics of Atomic Nuclei, 2011, v. 74, n. 13, p. 1854, doi. 10.1134/S1063778811130011

By:

Alekseev, P.;
Semchenkov, Yu.;
Sedov, A.;
Subbotin, S.;
Chibinyaev, A.

Publication type:

Article

Neutron-Physical Model Impact on the Calculation of a Serious Accident with Sodium Boiling in a Fast Reactor.

Published in:

Atomic Energy, 2017, v. 122, n. 4, p. 217, doi. 10.1007/s10512-017-0259-3

By:

Ashurko, Yu.;
Volkov, A.;
Raskach, K.;
Solomonova, N.

Publication type:

Article

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.

Published in:

Nuclear Technology, 2016, v. 193, n. 1, p. 88, doi. 10.13182/NT14-147

By:

Vaghetto, Rodolfo;
Crook, Timothy;
Vanni, Alessandro;
Hassan, Yassin A.

Publication type:

Article

SAFETY ASSESSMENT OF SiC CLADDING OXIDATION UNDER LOSS-OF-COOLANT ACCIDENT CONDITIONS IN LIGHT WATER REACTORS.

Published in:

Nuclear Technology, 2013, v. 183, n. 2, p. 210, doi. 10.13182/NT12-122

By:

YOUHO LEE;
McKRELL, THOMAS J.;
CHAO YUE;
KAZIMI, MUJID S.

Publication type:

Article

LONG-TERM VALIDATION OF THE MOLTEN FUEL-MODERATOR INTERACTIONS MODEL.

Published in:

Nuclear Technology, 2010, v. 169, n. 2, p. 114, doi. 10.13182/NT10-A9356

By:

DIAB, AYA;
CORRADINI, MICHAEL;
MARTIN, CARL

Publication type:

Article

An attempt for a unified description of mechanical testing on Zircaloy-4 cladding subjected to simulated LOCA transient.

Published in:

EPJ Nuclear Sciences & Technologies, 2016, v. 2, p. 1, doi. 10.1051/epjn/2016009

By:

Desquines, Jean;
Drouan, Doris;
Torres, Elodie;
Guilbert, Séverine;
Lacote, Pauline

Publication type:

Article

Comparison of CATHARE results with the experimental results of cold leg intermediate break LOCA obtained during ROSA-2/ LSTF test 7.

Published in:

EPJ Nuclear Sciences & Technologies, 2016, v. 2, p. 1, doi. 10.1051/epjn/e2015-50020-7

By:

Mazgaj, Piotr;
Vacher, Jean-Luc;
Carnevali, Sofia

Publication type:

Article

Cooling the intact loop of primary heat transport system using Shutdown Cooling System in case of LOCA events.

Published in:

EPJ Nuclear Sciences & Technologies, 2015, v. 1, p. 1, doi. 10.1051/epjn/e2015-50024-y

By:

Icleanu, Diana Laura;
Prisecaru, Ilie;
Jianu, Iulia Nicoleta

Publication type:

Article

ROSA/LSTF Tests and Posttest Analyses by RELAP5 Code for Accident Management Measures during PWR Station Blackout Transient with Loss of Primary Coolant and Gas Inflow.

Published in:

Science & Technology of Nuclear Installations, 2018, p. 1, doi. 10.1155/2018/7635878

By:

Takeda, Takeshi;
Ohtsu, Iwao

Publication type:

Article

Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium-Cooled Pebble Bed Blanket Concept.

Published in:

Science & Technology of Nuclear Installations, 2015, p. 1, doi. 10.1155/2015/865829

By:

Gonfiotti, Bruno;
Paci, Sandro

Publication type:

Article

Modelling of QUENCH-03 and QUENCH-06 Experiments Using RELAP/SCDAPSIM and ASTEC Codes.

Published in:

Science & Technology of Nuclear Installations, 2014, p. 1, doi. 10.1155/2014/849480

By:

Kaliatka, Tadas;
Kaliatka, Algirdas;
Vileiniškis, Virginijus;
Ušpuras, Eugenijus

Publication type:

Article

Study on the Behaviors of a Conceptual Passive Containment Cooling System.

Published in:

Science & Technology of Nuclear Installations, 2014, p. 1, doi. 10.1155/2014/358365

By:

Jianjun Wang;
Xueqing Guo;
Shengzhi Yu;
Baowei Cai;
Zhongning Sun;
Changqi Yan

Publication type:

Article

PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications.

Published in:

Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/548513

By:

Kouhia, Virpi;
Purhonen, Heikki;
Riikonen, Vesa;
Puustinen, Markku;
Kyrki-Rajamäki, Riitta;
Vihavainen, Juhani

Publication type:

Article

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

Published in:

Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/487371

By:

Arndt, J.;
Grebner, H.;
Sievers, J.

Publication type:

Article

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

Published in:

Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/480948

By:

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

Publication type:

Article

Consistent Posttest Calculations for LOCA Scenarios in LOBI Integral Facility.

Published in:

Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/474162

By:

Reventós, F.;
Pla, P.;
Matteoli, C.;
Nacci, G.;
Cherubini, M.;
Del Nevo, A.;
D'Auria, F.

Publication type:

Article

The Integral Test Facility Karlstein.

Published in:

Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/439374

By:

Leyer, Stephan;
Wich, Michael

Publication type:

Article

Major Achievements and Prospect of the ATLAS Integral Effect Tests.

Published in:

Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/375070

By:

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

Publication type:

Article

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

Published in:

Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/305405

By:

Nuñez-Carrera, Alejandro;
Camargo-Camargo, Raúl;
Espinosa-Paredes, Gilberto;
López-García, Adrián

Publication type:

Article

Severe Accident Simulation of the Laguna Verde Nuclear Power Plant.

Published in:

Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/209420

By:

Espinosa-Paredes, Gilberto;
Camargo-Camargo, Raúl;
Nuñez-Carrera, Alejandro

Publication type:

Article

Application of CFD Codes in Nuclear Reactor Safety Analysis.

Published in:

Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/198758

By:

Höhne, T.;
Krepper, E.;
Rohde, U.

Publication type:

Article

CFD Application to Hydrogen Risk Analysis and PAR Qualification.

Published in:

Science & Technology of Nuclear Installations, 2009, v. 2009, p. 1, doi. 10.1155/2009/213981

By:

Jinbiao Xiong;
Yanhua Yang;
Xu Cheng

Publication type:

Article

An Overview of Westinghouse Realistic Large Break LOCA Evaluation Model.

Published in:

Science & Technology of Nuclear Installations, 2008, p. 1, doi. 10.1155/2008/498737

By:

Frepoli, Cesare

Publication type:

Article

GRS Method for Uncertainty and Sensitivity Evaluation of Code Results and Applications.

Published in:

Science & Technology of Nuclear Installations, 2008, p. 1, doi. 10.1155/2008/798901

By:

Glaeser, Horst

Publication type:

Article

Determination of Loss of Coolant Accident (LOCA) in Nuclear Power Plants Using Signal Processing Method.

Published in:

Engineering Letters, 2009, v. 17, n. 4, p. 305

By:

Mahmoodi, R.;
Shahriari, M.;
Zolfaghari, A.

Publication type:

Article

Computational Investigation of Film Cooling from Trenched Holes Near the Leading Edge of a Turbine Blade.

Published in:

Numerical Heat Transfer: Part A -- Applications, 2008, v. 53, n. 3, p. 308, doi. 10.1080/10407780701564200

By:

Islami, SimaBaheri;
Tabrizi, S. P.Alavi;
Jubran, B. A.

Publication type:

Article

Numerical and Experimental Study of Thermal Stratification Outside a Small SMR Containment Vessel.

Published in:

Sustainability (2071-1050), 2018, v. 10, n. 7, p. 2332, doi. 10.3390/su10072332

By:

Albadawi, Gasim;
Wang, Shengfei;
Cao, Xingdi

Publication type:

Article

Light water reactor fuel performance: Current status, challenges, and future high fidelity modeling.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2011, v. 63, n. 8, p. 49, doi. 10.1007/s11837-011-0138-7

By:

Edsinger, K.;
Stanek, C. R.;
Wirth, B. D.

Publication type:

Article

Chromate In coolant water of gramophone record presses.

Published in:

1978

By:

Calnan, C. D.

Publication type:

Case Study

Verification and validation of numerical models of the transport of insulation debris.

Published in:

Journal of Computational Multiphase Flows, 2012, v. 4, n. 3, p. 255, doi. 10.1260/1757-482X.4.3.255

By:

Glover, G. M. Cartland;
Kratzsch, A.;
Krepper, E.;
Renger, S.;
Seeliger, A.;
Zacharias, F.;
Alt, S.;
Kästner, W.;
Kryk, H.;
Weiss, F.-P.

Publication type:

Article

A Thermoelectric Generator Using Engine Coolant for Light-Duty Internal Combustion Engine-Powered Vehicles.

Published in:

Journal of Electronic Materials, 2011, v. 40, n. 5, p. 812, doi. 10.1007/s11664-011-1580-6

By:

Kim, Shiho;
Park, Soonseo;
Kim, SunKook;
Rhi, Seok-Ho

Publication type:

Article

Physical-chemical Background of the Potential Phase Transitions during Loss of Coolant Accidents in the Supercritical Water Loops of Various Generation IV Nuclear Reactor Types.

Published in:

Periodica Polytechnica: Chemical Engineering, 2019, v. 63, n. 2, p. 333, doi. 10.3311/PPch.12770

By:

Györke, Gábor;
Imre, Attila R.

Publication type:

Article

Concept of a demonstrational hybrid reactor-a tokamak with molten-salt blanket for U fuel production: 1. Concept of a stationary Tokamak as a neutron source.

Published in:

Physics of Atomic Nuclei, 2015, v. 78, n. 12, p. 1326, doi. 10.1134/S1063778815120017

By:

Azizov, E.;
Gladush, G.;
Dokuka, V.;
Khayrutdinov, R.

Publication type:

Article

Public Response to a Near‐Miss Nuclear Accident Scenario Varying in Causal Attributions and Outcome Uncertainty.

Published in:

Risk Analysis: An International Journal, 2018, v. 38, n. 5, p. 947, doi. 10.1111/risa.12920

By:

Cui, Jinshu;
Rosoff, Heather;
John, Richard S.

Publication type:

Article