- Volume 19 Issue 1
Determination of Derived Release Limits for a CANDU Nuclear Power Plant
CANDU형 원전에서의 유도방출한도 결정
- Kim, Kyo-Youn (Korea Atomic Energy Research Institute) ;
- Hwang, Hae-Ryong (Korea Atomic Energy Research Institute) ;
- Kim, Jong-Kyung (Hanyang University)
- Published : 1994.06.30
A computer code DRL was developed to calculate the derived release limits at CANDU type nuclear power plants. The derived release limits resulting from DRL code is to set guidelines for the release of radionuclides in airborne and water-borne effuents during normal operations of a CANDU type nuclear power plant. The DRL code generally follows the methodology Prescribed in the CSA standard N288.1-M87 and uses the Parameter values recommended in the same standards. The DRL code was used to calculate a set of preliminary derived release limits for the Wolsong NPP.