Investigating the in-core 60Co production assembly for open pool type reactor
-
Amr Abdelhady
Abstract
Production of high specific 60Co activity in nuclear research reactor needs long time of irradiation to reach the proper consumer demands. Cobalt device is a fixed experiment inside the core of the second research reactor (ETRR-2) that designed for production of 60Co with activity of 50,000 Ci. Cobalt device is assembly of 16 pins of aluminum cans that filling with the cobalt foils. Utilizing the programs that depend on the Monte Carlo method to estimate 60Co activity is the objective of this study. MCNP6, KENO-VI, and MAVRIC codes would be used to evaluate the time that the cobalt device has been spent inside the reactor core for reaching the proper 60Co activity considering the continuous irradiation as well as the discrete irradiation. The calculations show that nearly one year of continuous neutron irradiation is sufficient for reaching the required activity. In case of discrete irradiation, the time required for reaching the required activity would be more than a year depending on the reactor operation period.
-
Author contributions: The author has accepted responsibility for the entire content of this submitted manuscript and approved submission.
-
Research funding: None declared.
-
Conflict of interest statement: The author declares no conflicts of interest regarding this article.
References
Abdelhady, A. (2018). Dose rates from the accidental withdrawal of a fuel element from an open pool type reactor. J. Nucl. Eng. Radiat. Sci. 4: 021010–1, https://doi.org/10.1115/1.4038058.Search in Google Scholar
Abdelhady, A. (2016). Radiation dose distributions due to sudden ejection of cobalt device. Appl. Radiat. Isot. 115: 208–211, https://doi.org/10.1016/j.apradiso.2016.06.028.Search in Google Scholar PubMed
Eckerman, K. and Endo, A. (2008). ICRP publication 107, nuclear decay data for dosimetric calculations. Ann. ICRP 38: 7–96.10.1016/j.icrp.2008.10.005Search in Google Scholar
Hollenbach, D.F. (2011). KENO-VI: ageneral quadratic version of the keno program, ORNL/TM-2005/39 version 6.1 sect. F17. Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA.Search in Google Scholar
IAEA-TECDOC-1340 (2003). Manual for reactor produced radioisotopes. Iaea, Vienna.Search in Google Scholar
Pelowitz, D.B. (Ed.) (2014). MCNP6 user’s manual, code version 6.1.1beta, LA-CP-14-00745. Los Alamos National Laboratory, New Mexico, USA.Search in Google Scholar
Peplow, D.E. (2011). MAVRIC: monaco with automated variance reduction using importance calculations, ORNL/TM-2005/39 version 6.1, sect. S6. Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA.Search in Google Scholar
Scale (2011). Scale: a comprehensive modeling and simulation suite for nuclear safety analysis and design, ORNL/TM-2005/39 version 6.1. Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA.Search in Google Scholar
© 2022 Walter de Gruyter GmbH, Berlin/Boston
Articles in the same Issue
- Frontmatter
- Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants
- Improving of electric network feeding nuclear facility based on multiple types DGs placement
- Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis
- Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
- Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach
- Determination of limiter design and material composition of MT-II spherical tokamak
- Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition
- Design of an unattended ore grading measurement system in a uranium mine
- Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning
- Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network
- Investigating the in-core 60Co production assembly for open pool type reactor
- Calendar of events
Articles in the same Issue
- Frontmatter
- Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants
- Improving of electric network feeding nuclear facility based on multiple types DGs placement
- Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis
- Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
- Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach
- Determination of limiter design and material composition of MT-II spherical tokamak
- Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition
- Design of an unattended ore grading measurement system in a uranium mine
- Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning
- Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network
- Investigating the in-core 60Co production assembly for open pool type reactor
- Calendar of events
