A pure dynamic Monte Carlo code for the neutronic analysis of nuclear reactors. (January 2022)
- Record Type:
- Journal Article
- Title:
- A pure dynamic Monte Carlo code for the neutronic analysis of nuclear reactors. (January 2022)
- Main Title:
- A pure dynamic Monte Carlo code for the neutronic analysis of nuclear reactors
- Authors:
- Ajami, Mona
Kamkar, Ali
Zangian, Mahdi
Minuchehr, Abdolhamid
Zolfaghari, Ahmadreza - Abstract:
- Highlights: A pure dynamic Monte Carlo code called MC3-TD was introduced. MC3-TD is capable of modeling complex reactor core geometries. The code has the capability of tracking neutrons and precursors as particles. An appropriate simulation of delayed neutrons has been used in MC3-TD. A new approach called the dynamic control method was proposed for population control. Abstract: Transient analysis is of great significance in the safety and economic assessment of nuclear systems. This kind of analysis is generally performed using simplified models such as the time-dependent diffusion theory or the point-kinetics approximation. Therefore, applying a more accurate approach seems necessary for situations exceeding the validity range of such models. Nowadays, with increasing computational power, special attention has been focused on the use of dynamic Monte Carlo methods due to their capabilities in simulating detailed geometries and physics. Hence, this paper attempts to develop a pure time-dependent Monte Carlo code called MC3-TD that is capable of modeling complex reactor core geometries considering neutrons and delayed neutron precursors as particles. Using this viewpoint during simulation, in addition to obtaining the spatial distribution of precursors, can also facilitate modeling their movements. Moreover, a new approach called the dynamic control method has been proposed for population control and its effectiveness has been compared to conventional methods. SeveralHighlights: A pure dynamic Monte Carlo code called MC3-TD was introduced. MC3-TD is capable of modeling complex reactor core geometries. The code has the capability of tracking neutrons and precursors as particles. An appropriate simulation of delayed neutrons has been used in MC3-TD. A new approach called the dynamic control method was proposed for population control. Abstract: Transient analysis is of great significance in the safety and economic assessment of nuclear systems. This kind of analysis is generally performed using simplified models such as the time-dependent diffusion theory or the point-kinetics approximation. Therefore, applying a more accurate approach seems necessary for situations exceeding the validity range of such models. Nowadays, with increasing computational power, special attention has been focused on the use of dynamic Monte Carlo methods due to their capabilities in simulating detailed geometries and physics. Hence, this paper attempts to develop a pure time-dependent Monte Carlo code called MC3-TD that is capable of modeling complex reactor core geometries considering neutrons and delayed neutron precursors as particles. Using this viewpoint during simulation, in addition to obtaining the spatial distribution of precursors, can also facilitate modeling their movements. Moreover, a new approach called the dynamic control method has been proposed for population control and its effectiveness has been compared to conventional methods. Several transient problems, including 2D and 3D geometries, have been used to assess the performance of MC3-TD and a highly satisfactory agreement has been found between the obtained results and reference data. … (more)
- Is Part Of:
- Annals of nuclear energy. Volume 165(2022)
- Journal:
- Annals of nuclear energy
- Issue:
- Volume 165(2022)
- Issue Display:
- Volume 165, Issue 2022 (2022)
- Year:
- 2022
- Volume:
- 165
- Issue:
- 2022
- Issue Sort Value:
- 2022-0165-2022-0000
- Page Start:
- Page End:
- Publication Date:
- 2022-01
- Subjects:
- MC3 Monte Carlo Criticality Calculations (Code) -- MC3-TD Monte Carlo Criticality Calculation-Time Dependent (Code)
Neutron transport -- Dynamic Monte Carlo method -- Prompt neutron -- Delayed neutron -- Precursor -- Dynamic control method
Nuclear energy -- Periodicals
Nuclear engineering -- Periodicals
621.4805 - Journal URLs:
- http://www.sciencedirect.com/science/journal/03064549 ↗
http://catalog.hathitrust.org/api/volumes/oclc/2243298.html ↗
http://www.elsevier.com/journals ↗ - DOI:
- 10.1016/j.anucene.2021.108627 ↗
- Languages:
- English
- ISSNs:
- 0306-4549
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 1043.150000
British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 20102.xml