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1.
Meat Sci ; 93(2): 171-7, 2013 Feb.
Article in English | MEDLINE | ID: mdl-23022578

ABSTRACT

The combination of (1)H NMR lipid profiling with multivariate analysis was applied to differentiate irradiated and non-irradiated beef. Two pattern recognition chemometric procedures, stepwise linear discriminant analysis (sLDA) and artificial neural networks (ANNs), provided a successful discrimination between the groups investigated. sLDA allowed the classification of 100% of the samples into irradiated or non-irradiated beef groups; the same result was obtained by ANNs using the 1 kGy irradiation dose as discriminant value suggested by the network. Furthermore, sLDA allowed the classification of 81.9% of the beef samples according to the irradiation dose (0, 2.5, 4.5 and 8 kGy). (1)H NMR lipid profiling, coupled with multivariate analysis may be considered a suitable and promising screening tool for the rapid detection of irradiated meat in official control of food.


Subject(s)
Food Irradiation , Lipids/analysis , Meat/analysis , Meat/radiation effects , Animals , Cattle , Cyclobutanes/analysis , Discriminant Analysis , Magnetic Resonance Spectroscopy , Multivariate Analysis , Neural Networks, Computer
2.
Radiat Prot Dosimetry ; 115(1-4): 86-91, 2005.
Article in English | MEDLINE | ID: mdl-16381688

ABSTRACT

The International Reactor Innovative and Secure is a modular pressurised water reactor with an integral design. This means that all the primary system components, such as the steam generators, pumps, pressuriser and control rod drive mechanisms, are located inside the reactor vessel, which requires a large diameter. For the sake of better reliability and safety, it is desirable to achieve the reduction of vessel embrittlement as well as the lowering of the dose beyond the vessel. The former can be easily accomplished by the presence of a wide downcomer, filled with water, which surrounds the core region, while the latter needs the presence of additional internal shields. An optimal shielding configuration is under investigation, for reducing the ex-vessel dose due to activated internals and for limiting the amount of the biological shielding. MCNP 4C calculations were performed to evaluate the neutron and the gamma dose during operation and the 60Co activation of various shields configurations. The gamma dose beyond the vessel from activation of its structural components was estimated in a shutdown condition, with the Monte Carlo code FLUKA 2002 and the MicroShield software. The results of the two codes are in agreement and show that the dose is sufficiently low, even without an additional shield.


Subject(s)
Models, Statistical , Monte Carlo Method , Nuclear Reactors , Radiation Monitoring/methods , Radiation Protection/instrumentation , Radiation Protection/methods , Software , Algorithms , Computer Simulation , Equipment Failure , Equipment Failure Analysis/methods , European Union , Facility Design and Construction/methods , Gamma Rays , Radiation Dosage
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