Dose calculation due to a cylindrical source using numerical computation
Creators
- 1. Health Physics Division, Bhabha Atomic Research Centre, Mumbai (India)
Description
A cylindrical radioactive source is a common occurrence in nuclear facilities like radioactive isotope handling facility, waste processing facilities, reprocessing facility etc. A quick way of estimating the dose due to such a source without using a Monte Carlo based shielding code or a deterministic code will be a useful tool. A user friendly Mathematica based code was developed for this purpose. The code evaluates the integrals occurring in the formula for such a source numerically as the integrals cannot be obtained in closed form. The results for a particular case were verified with the shielding code GUI2QAD-3D. This code can be further extended to obtain dose for line sources, truncated conical source, slab source, disc source etc. in the presence of shield or without them by evaluating the integrals involved numerically. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Proceedings of the conference on accelerator radiation safety: book of abstracts
- Imprint Pagination
- 117 p.
- Journal Page Range
- p. 74
Conference
- Title
- conference on accelerator radiation safety
- Acronym
- CARS2011
- Dates
- 16-18 Nov 2011
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 43010233
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- MONTE CARLO METHOD; NUCLEAR FACILITIES; RADIATION MONITORING; RADIOISOTOPES; SHIELDING
- Descriptors DEC
- CALCULATION METHODS; ISOTOPES; MONITORING