Shielding Thickness Calculations for Line Gamma-ray Sources in Regular Geometrical Array

일반적(一般的) 배열(配列)인 선형(線型) 감마선원(線源)의 차폐계산(遮蔽計算)

  • Lee, Chong-Chul (Korea Nuclear Fuel Development Institute)
  • 이종철
  • Published : 1978.06.30

Abstract

A shielding calculation has been carried out for a storage vault of $5292(42{\times}42{\times}3)$ waste drums in which the mixed radioactive gamma-emitters are contained. The required ordinary concrete shielding thickness seems to be approximately 50cm. The results in terms of dose rate for polyenergy gammas appear to be considerably higher than those of the averaged energy gamma.

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