Abstract

Determination of 14C, 55Fe, 63Ni and gamma emitters in two different types of activated reactor pressure vessel (RPV) steel samples were carried out. The gamma emitters were analysed using HPGe detectors with ISOCS and standard geometry calibrations. Two radioanalytical procedures for the 14C, 55Fe, 63Ni analysis were developed using inactive samples and activated samples were analysed using modified procedures. A Monte Carlo code was used for the modelling of the activation results. The obtained measured and calculated results were comparable.

Highlights

  • During operation of a nuclear reactor, excess neutrons are absorbed into the reactor structures causing activation of structure materials

  • This paper presents a comparison of calculation and experimental analysis in determination of 14C, 55Fe, 63Ni and gamma emitters in two different types of activated Reactor Pressure Vessel (RPV) steel samples

  • The measurement results for VVER steel samples were comparable with the calculated results whereas the Boiling Water Reactor (BWR) steel results are little bit lower than the calculated results

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Summary

Introduction

During operation of a nuclear reactor, excess neutrons are absorbed into the reactor structures causing activation of structure materials. BWR samples had been irradiated with a thermal neutron dose of 1.26 × 1018 n cm−2 and decay time was 10 years Both calculated and measured activities were decay corrected to fixed reference dates. Effectiveness of the oxidisation was tested by spiking the inactive steel samples with 14C standard solution and the yield was measured by analysing the 14C concentrations in absorption bottles two and three (Fig. 2). Testing of method 2 in determination of 55Fe and 63Ni but the procedures are different in practice, direct mixing of sample and DMG solutions in a beaker vs column separation The both methods are based on the complexation of Ni by DMG

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