Results 21 to 30 of about 218 (131)
Measurement of Velocity and Temperature Profiles in the 1/40 Scaled‐Down CANDU‐6 Moderator Tank
Science and Technology of Nuclear Installations, Volume 2015, Issue 1, 2015., 2015 In order to simulate the CANDU‐6 moderator circulation phenomena during steady state operating and accident conditions, a scaled‐down moderator test facility has been constructed at Korea Atomic Energy Institute (KAERI). In the present work an experiment using a 1/40 scaled‐down moderator tank has been performed to identify the potential problems of ...
Hyoung Tae Kim +4 more
wiley +1 more source
CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 4 - FUEL CHANNEL ASSEMBLY [PDF]
Fiabilitate şi Durabilitate, 2014 As many nuclear power plants are reaching their end of lifecycle, the decommissioning of these installations has become one of the 21st century’s great challenges. Each project may be managed differently, depending on the country, development policies,
Gabi ROSCA FARTAT +2 more
doaj
Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 Plant
Science and Technology of Nuclear Installations, Volume 2015, Issue 1, 2015., 2015 This paper illustrates the application of a severe accident analysis computer program to the uncertainty analysis of molten corium‐concrete interaction (MCCI) phenomena in cases of severe accidents in CANDU6 type plant. The potential hazard of MCCI is a failure of the reactor building owing to the possibility of a calandria vault floor melt‐through ...
Sooyong Park +3 more
wiley +1 more source
DETAILS OF OPERATIONS PERFORMED BY THE REMOTE CONTROL ROBOT (CONCEPT) TO THE HORIZONTAL FUEL CHANNEL DURING DECOMMISSIONING PHASE OF NUCLEAR REACTOR CALANDRIA STRUCTURE. PART I: OUTSIDE OPERATIONS [PDF]
Fiabilitate şi Durabilitate, 2017 The authors contribution to this paper is to present a concept solution of a remote control robot (RCR) used for the horizontal fuel channels pressure tube decommissioning in the CANDU nuclear reactor.
Constantin POPESCU +2 more
doaj
Safety Enhancements for PHWRs Based on Macroscopic Losses of the Fukushima Accident
Science and Technology of Nuclear Installations, Volume 2015, Issue 1, 2015., 2015 The role of nuclear energy is to supply electric power on a stable basis to meet increasing demands, reduce carbon dioxide emissions, and maintain stable electric power costs while ensuring safety. The Fukushima accident taught us many lessons for creating safer nuclear power plants.
Sang Ho Kim +4 more
wiley +1 more source
PVP2006-ICPVT11-93645 CALANDRIA TUBE TO TUBESHEET ROLLER-EXPANDED JOINT QUALIFICATION [PDF]
, 2020 The complex calandria tube to calandria tubesheet roller-expanded joint in CANDU nuclear reactors is usually qualified by test. In this paper, a state-of-the-art numerical simulation is undertaken in order to improve the understanding of the behaviour of
A S Banwatt, R G Sauvé
core
Science and Technology of Nuclear Installations, Volume 2015, Issue 1, 2015., 2015 To verify the periodic boundary condition (PBC) treatment which was implemented in a TRI‐angle elements induced numerical analyzer (TRIAINA), the pressure tube creep problem is chosen and examined with three cases of normal, 2.5% creep, and 5.0% creep on the aspects of the multiplication factor and relative pin power.
E. H. Ryu +4 more
wiley +1 more source
Subchannel Analysis of Wire Wrapped SCWR Assembly
Science and Technology of Nuclear Installations, Volume 2014, Issue 1, 2014., 2014 Application of wire wrap spacers in SCWR can reduce pressure drop and obtain better mixing capability. As a consequence, the required coolant pumping power is decreased and the coolant temperature profile inside the fuel bundle is flattened which will obviously decrease the peak cladding temperature.
Jianqiang Shan +6 more
wiley +1 more source
, 2016 Science and Technology of Nuclear Installations, Volume 2016, Issue 1, 2016.
Jin Ho Song +5 more
wiley +1 more source
Simulation Strategy for the Evaluation of Neutronic Properties of a Canadian SCWR Fuel Channel
Science and Technology of Nuclear Installations, Volume 2013, Issue 1, 2013., 2013 The Canadian Supercritical‐Water‐Cooled Reactor (SCWR) is a vertical pressure tube reactor cooled with supercritical light water and moderated with heavy water. For normal operation, the local conditions of the coolant (density and temperature) and fuel (temperature) vary substantially along the channel.
G. Harrisson, G. Marleau, Hangbok Choi
wiley +1 more source