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By J.D. Dana

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Diamond, B. P. L. Aronson Brookhaven National Laboratory Energy Sciences and Technology Department ABSTRACT An analysis of pulse width during a rod ejection accident was carried out to help in designing experiments to test fuel behaviour under reactivity initiated accident conditions. The analysis used calculations based on a three-dimensional neutron kinetics code, PARCS, and a model of a pressurized water reactor at both beginning and end of a fuel cycle. Results showed that pulse width varied inversely with the maximum increase in local fuel enthalpy and this is consistent with simple analytical models.

An intercomparison of these codes does not guarantee estimating their real uncertainties. The problem can be solved by using a code a of different nature with a 3-D pin-by-pin core representation. Such a neutronic code, BARS, was developed at the RRC “Kurchatov Institute”. The BARS code was widely validated against the numerical and experimental benchmarks including LWR MOX-fuelled systems. Validation results demonstrate the capabilities of the code to describe complicated pin-by-pin effects within LWR cores with high accuracy.

Such a neutronic code, BARS, was developed at the RRC “Kurchatov Institute”. The BARS code was widely validated against the numerical and experimental benchmarks including LWR MOX-fuelled systems. Validation results demonstrate the capabilities of the code to describe complicated pin-by-pin effects within LWR cores with high accuracy. 2 thermal hydraulic code. Analyses of VVER and PWR accidents with ejection of a peripheral control rod show that the following: pin power distribution near the accident assembly is very complicated; assemblies adjacent to the core boundary contain hot fuel pins; the hottest fuel pin does not belong to the assembly with peak power.

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