2014•Applied Mechanics and MaterialsOpen access

Calculation on the Distribution of Ex-Core Neutron Flux during Reactor Start-Up

Chun Yu Liu, Benbicha Mohamed Elghazali

Abstract

The distribution of neutron flux is simulated by MCNP code from reactor start-up to criticality when the control rods are drawn different length from reactor core on ex-core detector area of the WWER reactor of TianWan. Because physical model built is very large, in order to save calculation time, the moving process of control rod is simplified. The results of calculation show that The neutron mainly distributed in the range of 0-400cm outside the pressure vessel. The value of the relative neutron flux ex-core is maximum in the range of 110cm to 180cm, so detection effect is better when the detector is set in this region.

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Available abstract

Key concepts: Control rod, Neutron flux, Criticality, Core (optical fiber), Nuclear engineering, Nuclear reactor core, Flux (metallurgy), Nuclear physics