Calculation of thermal neutron diffusion length in a light water media using MCNP code
Creators
- 1. Atomic Energy Organization of Iran, Nuclear Science and Technology Research Institute, Reactor and Nuclear Safety Research School, Tehran (Iran, Islamic Republic of)
Description
One of the key parameters of neutron diffusing media is the thermal neutron diffusion length. The popular calculational method is founded on utilizing MCNP code and curve fitting of a mathematical function to the neutron flux distribution in the media. In this investigation, a novel method based on the PTRAC card is proposed. The thermal neutron diffusion length parameter for light and water is calculated based on the above methods. The results are compared with the reported values and significant agreement is seen. The advantage of the above method is its independence from curve fitting to calculate the neutron flux distribution. In addition, in the curve fitting method, it is assumed that there is enough distance from the source location. This affects the error of the results because the neutron flux distribution function is correct everywhere except at the neutron source location. In the present investigation, the correctness of the proposed method in light water media is evaluated numerically.
Availability note (English)
Available from Atomic Energy Organization of IranAdditional details
Additional titles
- Original title (Persian)
- Mohasebe-ye tool-e pakhsh-e notron-e hararati dar mohit-e ab-e sabok ba estefade az MCNP
Publishing Information
- Journal Title
- Journal of Nuclear Science, Engineering and Technology
- Journal Volume
- 44
- Journal Issue
- no.3
- Journal Page Range
- p. 165-170
- ISSN
- 2676-5861
INIS
- Country of Publication
- Iran, Islamic Republic of
- Country of Input or Organization
- Iran, Islamic Republic of
- INIS RN
- 56002028
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Descriptors DEI
- DIFFUSION LENGTH; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON TRANSPORT; THERMAL NEUTRONS; WATER
- Descriptors DEC
- BARYONS; CALCULATION METHODS; DIMENSIONS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; HYDROGEN COMPOUNDS; LENGTH; NEUTRAL-PARTICLE TRANSPORT; NEUTRONS; NUCLEONS; OXYGEN COMPOUNDS; RADIATION FLUX; RADIATION TRANSPORT