Absorbed dose: organ dose manual calculation

  • Thread starter Thread starter emilmammadzada
  • Start date Start date
  • Tags Tags
    Calculation Manual
AI Thread Summary
To calculate the absorbed dose for organs using radionuclides like Ra-223, the Committee on Medical Internal Radiation Dose (MIRD) provides standardized methods and mathematical models. MIRD simplifies the assessment of internal radiation doses by considering the unique characteristics of various radionuclides and their interactions within the human body. This approach aids in radiation protection, risk assessment, and treatment planning by offering relatively straightforward methods and software tools for dosimetric analysis. Resources such as PDFs and books on MIRD methodologies can be found through professional organizations. Understanding these concepts is essential for accurate dose calculations in medical applications.
emilmammadzada
Messages
129
Reaction score
19
TL;DR Summary
Absorbed dose , organ dose manual calculation
Dear Experts . How can I calculate the absorbed dose for any organ with mathematical formulas? For example, radio nuclide Ra -223 ,organ liver, time 1 hour , activity 1MBq.What methods can I use? Is there a pdf or book about it?
 
Engineering news on Phys.org
You can start here with The Committee on Medical Internal Radiation Dose (MIRD)

Committee on Medical Internal Radiation Dose (MIRD)

Radiation dosimetry provides the fundamental quantities used for radiation protection, risk assessment, and treatment planning. The MIRD Committee develops standard methods, models, assumptions, and mathematical schema for assessing internal radiation doses from administered radiopharmaceuticals. The MIRD approach simplifies the problem of assessing dose for many different radionuclides—each with its unique radiological characteristics and chemical properties as labeled compounds—in the highly diverse biological environment represented by the human body, internal organs, tissues, fluid compartments, and cells. The virtue of the MIRD approach is that it systematically reduces complex dosimetric analyses to methods that are relatively simple to use, including software tools for experimental and clinical use.

http://www.snmmi.org/AboutSNMMI/CommitteeContent.aspx?ItemNumber=12475&navItemNumber=763
 
  • Informative
  • Like
Likes Astronuc, berkeman and emilmammadzada
Hello everyone, I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information(power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.) for Material 2 is zero, while Material 1...
Hi everyone, I'm a complete beginner with MCNP and trying to learn how to perform burnup calculations. Right now, I'm feeling a bit lost and not sure where to start. I found the OECD-NEA Burnup Credit Calculational Criticality Benchmark (Phase I-B) and was wondering if anyone has worked through this specific benchmark using MCNP6? If so, would you be willing to share your MCNP input file for it? Seeing an actual working example would be incredibly helpful for my learning. I'd be really...
Back
Top