Dose rate measurement through MCNP

In summary, "Dose rate measurement through MCNP" discusses the use of the Monte Carlo N-Particle Transport Code (MCNP) for calculating radiation dose rates in various environments. The paper outlines the methodology for inputting geometrical configurations, material properties, and source characteristics into the MCNP software to simulate particle transport and interactions. It emphasizes the importance of accurate modeling for assessing radiation exposure and highlights the software's capabilities in providing detailed dose rate distributions. The findings demonstrate MCNP's effectiveness as a tool for radiation safety analysis in medical, industrial, and nuclear applications.
  • #1
Salman Khan
33
2
I am interested to calculate dose rate (gy/h, rad/h) from a point source at a certain distance through MCNP. If I use F6 tally it will give answer in Mev/g which can be converted to Gray or rad by using FM card, but I don't know how can I find dose rate like rad/h or g/h.?
 
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  • #2
Hi,
1 Gy = 1 J/kg
1 eV = 1.6022E-19 J
hope it's help
 
  • #3
PSRB191921 said:
Hi,
1 Gy = 1 J/kg
1 eV = 1.6022E-19 J
hope it's help
I know to convert F6 tally (Mev/g) to dose (Gray) but how to find dose rate i.e Gray/hour from MCNP ?
 
  • #4
mcnp gives the result for one particle. Simply multiply by the number of particles emitted per second
 
  • #5
Ok thanks
 

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