Abstract

A new radioactive liquid waste cementation facility was under commissioning recently in the Institute of Nuclear and New Energy Technology of Tsinghua University, which is designed to simultaneously process multiple intermediate-level radioactive waste drums. Therefore, the multiple volume sources and the scattering effect becomes a key issue in its radiation protection. For this purpose, the Monte Carlo program FLUKA code and experimental measurement were both adopted. In the FLUKA simulation, five different scenarios were considered, i.e., one drum, two drums, four drums, six drums, and eight drums. For the multiple volume sources, the source subroutine code of FLUKA was rewritten to realize the sampling. The complex shielding also leads to a deep penetration problem; hence, the optimization algorithm and variance reduction techniques were adopted. During the measurement, two scenarios, outdoor and indoor, were carried out separately representing the dose field when only one drum is considered and when the scattering effect is considered. A comparison between the experiments and calculations shows very good agreement. From both of the Monte Carlo simulation and the experimental measurement, it can be drawn that, in the horizontal direction, with the increase of the drum number, the dose rate increases very little, while in the vertical direction, the increase of the dose rate is very obvious with the increase of the drum number. The complicated source term sampling methods, the optimization algorithm and variance reduction techniques, and the experimental verification can provide valuable references for the similar scattering problem in radiation protection and shielding design.

Highlights

  • For a room with walls, roof, and other structures, when considering the dose from a gamma radiation source to the point of interest, if the scattering effect is ignored, the dose may be underestimated

  • From the ratio of the FLUKA calculated and measured H∗(10) (F/M value), which ranges from 1.4 to 1.5, it can be seen that the differences between the measurement and the FLUKA simulation are within two times

  • The Monte Carlo program FLUKA was adopted to calculate the dose field distribution in a radioactive liquid waste cementation facility. e main emphasis was put on the effect of scattering when several intermediate-level radioactive waste (ILW) drums exist in the room

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Summary

Introduction

For a room with walls, roof, and other structures, when considering the dose from a gamma radiation source to the point of interest, if the scattering effect is ignored, the dose may be underestimated. When several radioactive sources exist, the total dose contribution of these radioactive sources to the point of interest should be considered. The radiation protection of a radioactive liquid waste cementation facility is investigated, which meets the above scenario. There may be multiple intermediate-level radioactive waste (ILW) drums in the room. There is an iron shielding of 12 cm Science and Technology of Nuclear Installations (a)

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