Radiological consequence estimates for LEU core of Pakistan research reactor-1 (PARR-1) along with the model used for these calculations is presented. A design basis loss of coolant accident (LOCA) resulting in release of fission products from reactor core to the containment building and eventually to the atmosphere has been analyzed. The consequences to the radiation workers and surrounding population are presented in term of radiological doses. These dose estimates are then compared with the recommended emergency dose limits to assess the boundaries of exclusion zone and low population zone. (author).