Atomic Energy of Canada Limited

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: Zirconium alloy & Neutron. The organization has 4845 authors who have published 4826 publications receiving 102951 citations.

C 12 (α,γ ) 16 O cross sections at stellar energies

Abstract: The excitation function of the $^{12}\mathrm{C}$(\ensuremath{\alpha},\ensuremath{\gamma}${)}^{16}$O reaction and the angular distribution of its \ensuremath{\gamma} rays were measured at nine center-of-mass energies ranging from E=1.37 to 2.98 MeV. These measurements allowed the separation of the E1 and E2 contributions and their extrapolation to the region of astrophysical interest. The analysis of all the available E1 cross sections with the K-matrix method and with a three-level R-matrix method yields a consistent prediction of 79\ifmmode\pm\else\textpm\fi{}16 keV b for the E1 S factor at 300 keV. The E2 contribution at the same energy is 36\ifmmode\pm\else\textpm\fi{}6 keV b from a cluster model analysis of the present data. The best estimate of the total S factor at 300 keV is 120 keV b, and it is unlikely that it will fall outside the range of 80--160 keV b. \textcopyright{} 1996 The American Physical Society.

Color and Oxidative Stability of Nitrite-Free Cured Meat after Gamma Irradiation

Abstract: The effects of 5 and 10 kGy irradiation on the color and oxidative stability of meats treated with nitrite or a nitrite-free curing system were investigated. The nitrite-free curing system consisted of the preformed cooked cured-meat pigment, sodium ascorbate and sodium tripolyphosphate with or without sodium acid pyrophosphate. Irradiation had no detrimental effects on the color or flavor of either cured samples. Polyphosphates had a beneficial effect on oxidative stability but had a slight detrimental effect on color stability of irradiated samples.

A Comprehensive Examination of Heat Transfer Correlations Suitable for Reactor Safety Analysis

Abstract: Fuel sheath temperatures in water-cooled nuclear reactors are usually near the saturation temperature of water. However, during an accidental increase in power, or a decrease in flow and pressure, deterioration in heat transfer is possible. It occurs when the surface temperature increases to such a high level that the heated surface can no longer support continuous liquid contact. This phenomenon is usually referred to as the boiling crisis (or dryout) and the corresponding heat flux as the critical heat flux (or CHF). The boiling crisis is characterized by either a sudden rise in surface temperature, caused by the heated surface being covered by a stable vapor film (film boiling), or by small surface temperature spikes, corresponding to the appearance and disappearance of dry patches (transition boiling).