Results 41 to 50 of about 218 (131)

Experimental investigations on decay heat removal in advanced nuclear reactors using single heater rod test facility: Air alone in the annular gap

open access: yes, 2010
During a loss of coolant accident in nuclear reactors, radiation heat transfer accounts for a significant amount of the total heat transfer in the fuel bundle. In case of heavy water moderator nuclear reactors, the decay heat of a fuel bundle enclosed in
Santosh B. Bopche   +3 more
core   +1 more source

A Novel Electromagnetic Technique for Remote Repositioning of Coolant Tube Spacers In CANDU Nuclear Reactors [PDF]

open access: yes, 1986
On August 1, 1983, a sudden failure of a coolant tube, known as a pressure tube, was experienced in one of the CANDU reactors at Pickering 'A' Nuclear Generating Station of Ontario Hydro. A contributing factor to the rupture of the tube was a contact for
Dableh, Hanna Youssef
core  

Improved Engineering Process-Zone Model for Evaluation of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors

open access: yes, 2017
The core of a CANDU®(1) pressurized heavy water reactor consists of a lattice of either 390 or 480 horizontal Zr-Nb pressure tubes, depending on the reactor design, which contain the nuclear fuel.
Leonid Gutkin, Cheng Liu, Douglas Scarth
core   +1 more source

Elovanoid-N34 modulates TXNRD1 key in protection against oxidative stress-related diseases. [PDF]

open access: yesCell Death Dis, 2023
Calandria JM   +7 more
europepmc   +1 more source

New Retinal Pigment Epithelial Cell Model to Unravel Neuroprotection Sensors of Neurodegeneration in Retinal Disease. [PDF]

open access: yesFront Neurosci, 2022
Asatryan A   +11 more
europepmc   +1 more source

Auto Sizing of CANDU Nuclear Reactor Fuel Channel Flaws from UT Scans. [PDF]

open access: yesSensors (Basel), 2023
Hammad I   +3 more
europepmc   +1 more source

QUENCH OF CYLINDRICAL TUBES DURING TRANSITION FROM FILM TO NUCLEATE BOILING HEAT TRANSFER IN CANDU REACTOR CORE [PDF]

open access: yes, 2011
Study of quench cooling is very important in nuclear reactor safety for limiting the extent of core damage during the early stages of severe accidents after Loss of Coolant Accidents (LOCA).
Takrouri, Kifah
core  

Compression of Multi-frequency Eddy Current Data using Principal Components Analysis for Pressure Tube to Calandria Tube Gap Measurement

open access: yes, 2016
Inspection of components with multi-variable influential parameters may result in a loss of accuracy for the measurement of the target variable. A particular example occurs in the case of a pressure tube (PT) that is contained within a calandria tube (CT)
Krause, Thomas   +2 more
core  

Investigation of pressure-tube and calandria-tube deformation following a single channel blockage event in ACR-700 [PDF]

open access: yes, 2006
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2006.Includes bibliographical references (leaves 113-115).The ACR-700 is an advanced pressure-tube (PT) reactor being developed by Atomic Energy of Canada ...
Gerardi, Craig Douglas
core  

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