Safety Parameters of the Pakistan Research Reactor-1

Detailed analysis of the neutronic safety parameters is mandatory for new reactor start-up, normal operation and its shutdown. These parameters include initial criticality, excess reactivity, shut down margin, control rod worth, reactivity coefficients and peaking factors of the reactor core. This paper presents the safety parameters of the First High Power core of Pakistan Research Reactor –I (PARR-I) using Monte Carlo N-Particle (MCNP5) computer code. The PARR-1is MTR type research reactor, was established in 1965 and achieved its first criticality with 93% High Enriched Uranium (HEU) uranium silicide fuel. The reactor core was converted to Low Enriched Uranium (LEU) fuel and its power was first upgraded from 5 to 9 MW and then to 10 MW in 1992 resulting a First High Power (FHP) core. This paper presents the assessment of safety parameters of the FHP core of PARR-1. (author)