A method to obtain radioactivity of non-๐พ nuclides by 60Co based on Monte Carlo simulations
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์ฐธ๊ณ ๋ฌธํ
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์ด๋ก
Source term investigation is a critically important aspect of reactor decommissioning, particularly as the range of nuclides under consideration expands beyond the capabilities of existing analysis methods. In this study, we try to propose a methodology to indirectly determine the radioactivity of long-lived nuclides which are non-๐พ or low energy in various nuclear waste materials by measuring the radioactivity of 60Co. The critical point of this method is to establish relationship between some easy to measure (ETM) key nuclides, such as certain ๐พ emitters (like 60Co), and the difficult to measure (DTM) nuclides to derive information for the DTM nuclides of interest. To begin, we calculate nuclide bulk densities of 55Fe, 60Co, 63Ni and 152Eu in nuclear waste materials. By constructing inversion matrices and analyzing the intensity matrices of characteristic ๐พ lines emitted by 60Co, we can extract the radioactivity of non-๐พ radionuclides (55Fe, 63Ni, and 152Eu) present in the nuclear waste materials that are contained within a specific container. Furthermore, our methodology accounts for the influence of voids within the container, thereby ensuring the reliability and validity of the obtained results. This innovative approach offers a promising avenue for efficiently sorting nuclear waste.
Abstract
Source term investigation is a critically important aspect of reactor decommissioning, particularly as the range of nuclides under consideration expands beyond the capabilities of existing analysis methods. In this study, we try to propose a methodology to indirectly determine the radioactivity of long-lived nuclides which are non-๐พ or low energy in various nuclear waste materials by measuring the radioactivity of 60Co. The critical point of this method is to establish relationship between some easy to measure (ETM) key nuclides, such as certain ๐พ emitters (like 60Co), and the difficult to measure (DTM) nuclides to derive information for the DTM nuclides of interest. To begin, we calculate nuclide bulk densities of 55Fe, 60Co, 63Ni and 152Eu in nuclear waste materials. By constructing inversion matrices and analyzing the intensity matrices of characteristic ๐พ lines emitted by 60Co, we can extract the radioactivity of non-๐พ radionuclides (55Fe, 63Ni, and 152Eu) present in the nuclear waste materials that are contained within a specific container. Furthermore, our methodology accounts for the influence of voids within the container, thereby ensuring the reliability and validity of the obtained results. This innovative approach offers a promising avenue for efficiently sorting nuclear waste.
์ฐธ๊ณ ๋ฌธํ (33)
- M. N. H. Comsan, "Nuclear electricity for sustainable development : Egypt a case study", Energy Convers. Manage, 51(9), pp.1813~1817 (2010)
- Weiming Gao, "How does nuclear energy consumption contribute to or hinder green growth in major nuclear energy-consuming countries?", Prog. Nucl. Energy, 170, pp.105~111 (2024)
- V. Yu. Litovchenko, "Using the Monte-Carlo method to optimize the radiation protection composition of containers for storing conditioned liquid waste", AIP Conference Proceedings (2022)
- Takahiro Ono, "Investigation of the chemical characteristics of individual radioactive microparticles emitted from reactor 1 by the Fukushima Daiichi nuclear power plant accident by using multiple synchrotron radiation x-ray analyse", Bunseki Kagaku, 66, pp.251~261 (2017)
- Matteo Ferrari, "Characterization of a polyphenyl ether oil irradiated at high doses in a triga mark II nuclear reactor", Nucl. Instrum. Methods Phys. Res. B, 497, pp.1~9 (2021)
- Zhongtang Wang, "Rapid determination of pu isotopes for decommission concrete samples by inductively coupled plasma mass spectrometry", J. Radioanal. Nucl. Chem, 316, pp.411~417 (2018)
- Young A. Suh, "Decisions on nuclear decommissioning strategies : Historical review", Prog. Nucl. Energy, 106, pp.34~43 (2018)
- Diletta Colette Invernizzi, "How benchmarking can support the selection, planning and delivery of nuclear decommissioning projects", Prog. Nucl. Energy, 99, pp.155~164 (2017)
- Zhaohuan Liu, "Evaluation of radioactivity and gamma spectra in the secondary coolant system of pwr", Nucl. Eng. Des, 277, pp.198~202 (2014)
- Leon Fuks, "Management of radioactive waste containing graphite: Overview of methods", Energies, 13(18) (2020)
- Jea-Ho Park, "Study of the radioactivity inventory deposited in the reactor coolant system during the decommissioning of kori unit 1", Ann. Nucl. Energy, 190, pp.109860~ (2023)
- Zekun Fang, "Theoretical analysis of long-lived radioactive waste in pressurized water reactor", Nucl. Sci. Tech, 32, pp.57~73 (2021)
- D. Z. Wang, "An improved method for the non-destructive characterization of radioactive waste by gamma scanning", Appl. Radiat. Isot, 67(10), pp.1897~1903 (2009)
- Marek Trojanowicz, "A review of flow analysis methods for determination of radionuclides in nuclear wastes and nuclear reactor coolants", Talanta, 183, pp.70~82 (2018)
- Guiping Dan, "63Ni liquid flicker determination technique in reactor core aluminum alloy samples", J. Nucl. Radiochem, 34(3), pp.185~188 (2012)
- F. Jallu, "Cleaning up of a nuclear facility : Destocking of pu radioactive waste and nuclear non-destructive assays", Nucl. Instrum. Methods Phys. Res. B, 283, pp.15~23 (2012)
- Q. Wang, "Tritium activity induced in the accelerator building and its correlation to radioactivity of gamma-nuclides", J. Radioanal. Nucl. Chem, 262, pp.587~592 (2004)
- Wang Qing-Bin, "A measurement of the residual radioactivity with NaI survey meter and its MC simulation", High Energy Phys. Nucl. Phys, 31(11), pp.1071~1075 (2007)
- International 2009 IAEA, "Determination and use of scaling factors for waste characterization in nuclear power plants, Nucl. Energy Ser", ~ (2009)
- Q. -B Wang, "Measurement of neutron spatial distribution inside concrete shield using activation foil and imaging plate technique", Atomic Energy Sci. Technol, 40, pp.650~653 (2006)
- Q. Wang, "Evaluation of the radioactivity in concrete from accelerator facilities", J. Radioanal. Nucl. Chem, 273, pp.55~58 (2007)
- H.F. Dou, "Study on Neutron Flux Distribution in SPR-300 Reactor", MA, pp.2005
- Mardiyanto Mangun Panitra, "Simulation study on the effect of ods cladding material on the criticality of nuclear reactors using MCNP5", The 4th International Conference on Nuclear Energy Technology and Sciences, 2021 (2022), ICoNETS
- Shahryar Malekie, "Comparative study of micro and nano size wo3", e44 epoxy composite as gamma radiation shielding using MCNP and experiment, 2017, pp.34(10), 108102~
- Hongbin Zhang, "Residual nuclides induced in cu target by a 250 MeV proton beam*", Chin. Phys. Lett, 32(4), pp.042501~ (2015)
- O. Bajaj Amol, "Method validation of multi-element panel in whole blood by inductively coupled plasma mass spectrometry(ICP-MS)", J. Mass Spectrom. Adv. Clin. Lab, 27, pp.33~39 (2023)
- S. Wheal Matthew, "Application of multi-isotope calibration to analysis of wine samples by ICP-MS", J. Anal. Atomic Spectrom, 36, pp.2383~2390 (2021)
- Zhizhong Sun, , Numer. Anal (2010)
- M. Di Luzio, "Vertical variations of flux parameters in irradiation channels at the triga mark II reactor of pavia", Prog. Nucl. Energy, 113, pp.247~254 (2019)
- Mohamad Hairie Rabir, "Power and neutron flux calculation for the puspati triga reactor using MCNP", J. Sains Nuklear Malays, 24(1), pp.22~32 (2017)
- Carlos Oliveira, "Monte Carlo simulation for dose distribution calculations in a ct-based phantom at the portuguese gamma irradiation facility", Nucl. Instrum. Methods Phys. Res. B, 213, pp.662~665 (2004)
- I. E. Stamatelatos, "Monte Carlo simulation of the greek research reactor neutron irradiation facilities", Nucl. Instrum. Methods Phys. Res. B, 263(1), pp.136~139 (2007)
- H. F. Dou, "Calculation of neutron flux in sprr-300 reactor irradiation channel with MCNP code, 27", 51~54 (2006)