Published 2018
| Version v1
Journal article
Efficiency of the dose rate calculation by Monte-Carlo method and point kernel method when handling radioactive waste
- 1. V.N. Karazin Kharkiv National University, Kharkiv (Ukraine)
- 2. National Science Center ''Kharkov Institute of Physics and Technology'', 61108, Kharkov (Ukraine)
Description
For the gamma-radiation sources with the volume up to 1 m3, filled with typical radioactive waste generated at NPPs with WWER-1000 reactors, the results of the dose rate (DR) calculations made by Monte-Carlo (MCNP) and by point kernel method (MicroShield and VOLUME) are compared. It is shown that the difference of the DR calculations made by the above methods does not exceed 10%. The values of DR calculated in MicroShield and VOLUME packages for the shields made of concrete and steel for such sources overestimate the MCNP data by 20...50%. The optimal correction of the buildup factor in the VOLUME package gives an accuracy of 10% in the shield calculations.
Additional details
Publishing Information
- Journal Title
- Voprosy Atomnoj Nauki i Tekhniki
- Journal Issue
- no.2-112
- Journal Page Range
- p. 63-69
- ISSN
- 1562-6016
INIS
- Country of Publication
- Ukraine
- Country of Input or Organization
- Ukraine
- INIS RN
- 49083713
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCURACY; CALCULATION METHODS; COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; CONCRETES; DOSE RATES; GAMMA SOURCES; MONTE CARLO METHOD; POINT KERNELS; RADIOACTIVE WASTE MANAGEMENT; THICKNESS
- Descriptors DEC
- BUILDING MATERIALS; CALCULATION METHODS; DIMENSIONS; EVALUATION; KERNELS; MANAGEMENT; MATERIALS; RADIATION SOURCES; WASTE MANAGEMENT