Results 1 to 10 of about 218 (131)
Science and Technology of Nuclear Installations, 2018 The LOCA (loss of coolant accident) is a kind of severe accident in the operation of PHWR (pressurized heavy water reactor) as well as other nuclear facilities, and possible cause of LOCA can be counted on the ballooning of pressure tube (PT) contacted ...
Hyoung Tae Kim +3 more
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Eddy Current Measurement of Electrical Resistivity in Heat-Treated Zr-2.5%Nb Pressure Tubes [PDF]
SensorsZr-2.5%Nb pressure tubes (PTs) house uranium fuel bundles in the fuel channels of CANDU® nuclear reactors. Preventing a failure mode caused by contact of the PT with an outer calandria tube (CT) is performed by inspection using eddy current (EC) testing ...
W. G. Thorpe +2 more
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Contact Conductance between Cladding/Pressure Tube and Pressure Tube/Calandria Tube of Advanced Thermal Reactor (ATR) [PDF]
Journal of Nuclear Science and Technology, 1994 In some postulated accidents with coincident loss of emergency coolant injection of the Advanced Thermal Reactor (ATR), the rate of heat transfer to the heavy water moderator that acts as heat sink for the decay heat depends on the contact conductance between cladding and pressure tube, and the same between pressure and calandria tubes.
Hiroyasu Mochizuki
exaly +4 more sources
Effect of processing on properties of thin walled calandria tubes for pressurised heavy water reactor [PDF]
Journal of Nuclear Materials, 2003 Thin walled calandria tubes for pressurised heavy water reactors are manufactured either by seam welding of Zircaloy-4 sheets or by seamless route. In the present study, the effect of processing on the critical properties such as texture, microstructure, hydriding behaviour and residual stress for both the routes as well as the mechanical anisotropy ...
KAPOOR, K +4 more
openaire +3 more sources
Procedia Engineering, 2013 AbstractAdvanced Heavy Water Reactor (AHWR) is a 300 MWe vertical pressure tube type, boiling light water cooled and heavy water moderated reactor. It consists of 452 coolant channels wherein the heat of nuclear reaction is used to boil the light water coolant to generate steam.
Dureja, A.K., Sinha, S.K., Sinha, R.K.
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Moderator Flow Simulation Around Calandria Tubes of Candu-6 Nuclear Reactors [PDF]
Engineering Applications of Computational Fluid Mechanics, 2014 AbstractCFD simulations of cross-flows along in-line and staggered tube bundles which emulate those encountered in the calandria of CANDU-6 reactors are presented. The knowledge of external wall temperature distributions around calandria tubes is a major concern during normal and off-normal operating conditions of CANDU reactors.
A Teyssedou +2 more
exaly +3 more sources
CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 2 - FUEL CHANNEL PRESENTATION [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
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Numerical study on influence of cross flow on rewetting of AHWR fuel bundle. [PDF]
ScientificWorldJournal, 2014 Numerical study on AHWR fuel bundle has been carried out to assess influence of circumferential and cross flow rewetting on the conduction heat transfer. The AHWR fuel bundle quenching under accident condition is designed primarily with radial jets at several axial locations.
Kumar M +3 more
europepmc +2 more sources
Development of an analytical method to evaluate the integrity of a calandria tube in the case of pressure tube ruptureAn analytical method which consists of two-dimensional thermal-hydraulic analysis and three-dimensional structural analysis has been proposed to evaluate the integrity of a calandria tube in the case of pressure tube rupture in a pressure tube type reactor.In order to validate the method, experiments were carried out with coaxially arranged double ...
速水 義孝 +7 more
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TIME-DEPENDENT HOMOGENIZATION FOR PRESSURIZED HEAVY-WATER REACTORS [PDF]
EPJ Web of Conferences, 2021 A new time-dependent homogenization approach that accounts for inter-assembly leakage has recently been proposed. The new technique extends Generalized Equivalence Theory (GET) to transient simulations through the use of time-dependent, leakage-corrected
Schwanke Peter, Nichita Eleodor
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