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Institution

Atomic Energy of Canada Limited

CompanyOttawa, Ontario, Canada
About: Atomic Energy of Canada Limited is a company organization based out in Ottawa, Ontario, Canada. It is known for research contribution in the topics: Neutron & Zirconium alloy. The organization has 4845 authors who have published 4826 publications receiving 102951 citations.


Papers
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Journal ArticleDOI
TL;DR: In this article, a rapid procedure for sequential separation of Strontium-90 ( 90 Sr) was developed and tested in groundwater samples col- lected from an area of riverbed affected by a 90 Sr groundwater plume.
Abstract: Strontium-90 ( 90 Sr) is a ubiquitous contaminant at nuclear facilities, found at high concentrations in spent nuclear fuel and radioactive waste. Due to its long half-life and ability to be transported in groundwater, an accurate method for measuring 90 Sr in water samples is critical to the monitoring program of any nuclear facility. To address this need, a rapid procedure for sequential separation of Sr/ Y was developed and tested in groundwater samples col- lected from an area of riverbed affected by a 90 Sr groundwater plume. Sixteen samples, plus spike and water blanks, were analyzed. Five different measurements were performed to determine the 90 Sr and yttrium-90 ( 90 Y) activities in the samples: direct triple-to-double-coin- cidence ratio (TDCR) Cherenkov counting of 90 Y, liquid scintillation (LS) counting for 90 Sr following radiochemi- cal separation, LS counting for 90 Y following radiochem- ical separation, Cherenkov counting for 90 Y following radiochemical separation and LS counting of the Sr sam- ples for 90 Y in-growth. The counting was done using a low- level Hidex 300SL TDCR counter. Each measurement method was compared for accuracy, sensitivity and effi- ciency. The results following Cherenkov counting and radiochemical separation were in very good agreement with one another.

29 citations

Proceedings ArticleDOI
R. R. Sadhankar1, J. Li1, H. Li1, D.K. Ryland1, S. Suppiah1 
10 May 2006
TL;DR: The Supercritical Water-Cooled Reactor (SCWR) as discussed by the authors uses supercritical water as the coolant with a nominal outlet temperature of up to 6251 and could deliver heat at ges550degC for hydrogen production.
Abstract: The potential of hydrogen to replace fossil fuels presents a significant opportunity for reducing greenhouse gas (GHG) emissions, especially when hydrogen is produced by "water-splitting", instead of hydrocarbon processing. "Water- splitting" by energy derived from nuclear sources is a preferred method for "carbon-free" production of hydrogen on a large scale. Researchers around the world are pursuing two new ways of water-splitting - thermochemical cycles and high- temperature electrolysis (HTE), using thermal energy from the future generation of higher temperature reactors. Both these methods, when coupled with a high-temperature nuclear reactor, could have efficiencies in the range of 50-60% compared to <30% for conventional electrolysis - currently the only existing method of producing hydrogen without co-product CO2. Research is underway at Atomic Energy of Canada Limited (AECL) on the development of the next generation of advanced CANDUreg concepts that include the Supercritical Water-Cooled Reactor (SCWR). The SCWR would use supercritical water as the coolant with a nominal outlet temperature of up to 6251 and could deliver heat at ges550degC for hydrogen production. AECL is currently evaluating various thermochemical cycles and high-temperature electrolysis for matching with the temperature capability of the SCWR and ACR-1000reg.

29 citations

Journal ArticleDOI
TL;DR: In this paper, the conversion electron spectrum of Tb160 has been studied in the Chalk River air-cored ρ√2 β-ray spectrometer at resolution settings of 0.04 % to 0.1 %.

29 citations

Journal ArticleDOI
TL;DR: In this paper, an expression for the boundary value of the chemical driving force at the crack tip is derived for the flux of vacancies to the crack and hence the crack-tip velocity.

29 citations

Journal ArticleDOI
TL;DR: In this article, metallographic and scanning electron microscopy analyses of specimens from experiments to measure the solubility of unirradiated UO 2 fuel in molten Zircaloy-4 at 2300, 2400 and 2500°C were performed.

29 citations


Authors

Showing all 4845 results

NameH-indexPapersCitations
Henry P. Schwarcz7835120863
Jonathan N. Glickman7217224025
Andrej Atrens6941721741
See Leang Chin6746017181
Purnendu K. Dasgupta6250616779
John Katsaras552209263
Jing-Li Luo5543610963
Charles Gale5333110903
Sanjoy Banerjee522298880
Yoshio Takahashi504039801
Peter Sigmund4922011795
Michael P. Païdoussis461658825
Wei-Kan Chu464458616
A. G. W. Cameron4512310111
Erland M. Schulson442456966
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Performance
Metrics
No. of papers from the Institution in previous years
YearPapers
20221
20213
20205
20194
20185
20178