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1426747 
Technical Report 
Radiological Consequence Analysis of LEU Core for Pakistan Research Reactor-1 
Khan, LA; Raza, SS; Akhtar, KM 
1991 
NTIS/02981772 
GRA and I 
GRA and I 
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. 
PARR reactor; *Fission product release; *Containment systems; *Radiation dosage; *Reactor accidents; Loss of coolant; Dispersions; Atmospheric diffusion; Risk assessment; Inhalation; Radioactive effluents; Calculation methods; Meltdown; Time dependence; Leakage; Distance; Source terms; Diffusion; Fluid filters; Fuel elements; Iodine; Foreign technology; Low enriched uranium; Plateout 
IRIS
• Uranium
     Toxline
     Merged reference set
     Secondary Refinement
          Retained for manual screening
     Excluded:
          Not chemical specific
     Uranium Literature Search Update 3/2017
          Toxnet