Low and intermediate radioactive gaseous, liquid and solid waste produced at Cernavoda Nuclear Po... more Low and intermediate radioactive gaseous, liquid and solid waste produced at Cernavoda Nuclear Power Plant must be well known from the point of view of contained radionuclide activity, during all steps of their processing, storage and transport, to ensure the nuclear safety of radioactive waste management. As in intermediate storage stage, the waste activity changes by radioactive decay and nuclear transmutation, the evolution in time of these sources is necessary to be assessed, for the purpose of biological shielding determination at any time. On the other hand, during the transport of waste package at the repository, the external dose rates must meet the national and international requirements concerning radioactive materials transportation on public roads. In this paper, a calculation methodology for waste characterization based on external exposure rate measurement and on sample analysis results is presented. The time evolution of waste activity, as well as the corresponding sh...
Low and intermediate radioactive gaseous, liquid and solid waste produced at Cernavoda Nuclear Po... more Low and intermediate radioactive gaseous, liquid and solid waste produced at Cernavoda Nuclear Power Plant must be well known from the point of view of contained radionuclide activity, during all steps of their processing, storage and transport, to ensure the nuclear safety of radioactive waste management. As in intermediate storage stage, the waste activity changes by radioactive decay and nuclear transmutation, the evolution in time of these sources is necessary to be assessed, for the purpose of biological shielding determination at any time. On the other hand, during the transport of waste package at the repository, the external dose rates must meet the national and international requirements concerning radioactive materials transportation on public roads. In this paper, a calculation methodology for waste characterization based on external exposure rate measurement and on sample analysis results is presented. The time evolution of waste activity, as well as the corresponding sh...
Ultra-high intensity lasers in use are connected with ionizing radiation sources that raise a rea... more Ultra-high intensity lasers in use are connected with ionizing radiation sources that raise a real concern in relation to installations, personnel, population and environment protection. The shielding of target areas in these facilities has to be evaluated from the conceptual stage of the building design. The sizing of the protective concrete walls was determined using computer codes such as Fluka. For the experiments to be carried out in the facility of the Center for Advanced Laser Technologies (CETAL), both proton beams with the energy of 100 MeV and electron beams with 300 MeV energy were considered to calculate the dimensions of structural shielding and to establish technical solutions fulfilling the radiation protection constraints imposed by the National Commission for Nuclear Activities Control.
2019 International Conference on ENERGY and ENVIRONMENT (CIEM), 2019
The purpose of this work is to present the results of a study regarding the behaviour of fresh CA... more The purpose of this work is to present the results of a study regarding the behaviour of fresh CANDU nuclear fuel immersed in light water (H2O) following a road accident scenario. The criticality simulations were made using KENO-V.a code, one of the computational tools provided by SCALE 6.2.1. The study evaluates the criticality potential, namely the effective multiplication factor keff for two types of nuclear fuel, formed out of fuel bundles containing 37 and 43 fuel elements, with the following enrichments 0.9%, 1.1% and 1.3% U235.
Microbial Degradation Processes in Radioactive Waste Repository and in Nuclear Fuel Storage Areas, 1997
... DRY INTERIM STORAGE FACILITY FOR SPENT FUEL CERNAVODA NPP MARIA RADU, MARCELA STANCIU, ADRIAN... more ... DRY INTERIM STORAGE FACILITY FOR SPENT FUEL CERNAVODA NPP MARIA RADU, MARCELA STANCIU, ADRIAN PANAIT, TRAIAN BARBU, SILVIA MATEESCU, DOINA PANTAZI Center of ... The sealing of the basket would be done using an automatic welding machine. ...
2021 10th International Conference on ENERGY and ENVIRONMENT (CIEM)
The aim of this work is to present the results obtained from the irradiation of a CANDU 6 fuel as... more The aim of this work is to present the results obtained from the irradiation of a CANDU 6 fuel assembly within a time of 327 days with a 23,853 MW/tU cycle specific power followed by a 50-year decay, using the ORIGEN and ARP calculation codes which are included in the SCALE 6.2.2. code system. The ORIGEN library was prepared by ARP to have three sets of burnup-dependent transition cross-sections, resulting in three cases, one for each of the irradiation intervals proposed by the study: 100, 100, 127 days at a maximum fuel burnup of 7800 MW.day/tU. The input material has been specified to have 1 ton of metallic uranium with an enrichment of 0.7145% in U235. Simulating the irradiation of nuclear fuel within the reactor leads to the follow up of its radiological characteristics, required in the stages of surface storage as radioactive waste.
The modulated code system SCALE is used to perform a standardized shielding analysis for any faci... more The modulated code system SCALE is used to perform a standardized shielding analysis for any facility containing spent fuel: handling devices, transport cask, intermediate and final storage facility. The neutron and gamma sources as well as the dose rates can be obtained using either discrete-ordinates or Monte Carlo methods. The shielding analysis control modules (SAS1, SAS2H and SAS4) provide a general procedure for cross-section preparation, fuel depletion/decay calculation and general onedimensional or multi-dimensional shielding analysis. The module SAS4 used in the analysis presented in this paper, is a three-dimensional Monte Carlo shielding analysis module, which uses an automated biasing procedure specialized for a nuclear fuel transport or storage container. The Spent Fuel Interim Storage Facility in our country is projected to be a parallelepiped concrete monolithic module, consisting of an external reinforced concrete structure with vertical storage cylinders (pits) arra...
Inside the concrete used as a material for the protection shields against ionizing radiation comi... more Inside the concrete used as a material for the protection shields against ionizing radiation coming from the core of the reactor, various processes and physical and chemical reactions have to be taken into account when the efficiency of the shield is analyzed throughout the operation life of the nuclear power plant. The paper looked at how the concrete can be affected by the irradiation with neutrons and gamma radiation under conditions of possible high fluence outside an reactor core.
RADIOLOGICAL SAFETY ASSESSMENT FOR THE EXPERIMENTAL AREA OF A HYPER-INTENSE LASER WITH PEAK—POWER... more RADIOLOGICAL SAFETY ASSESSMENT FOR THE EXPERIMENTAL AREA OF A HYPER-INTENSE LASER WITH PEAK—POWER OF 1PW—CETAL M. G. Florescu1,2, O. G. Duliu3,4,*, D. Pantazi1 , C. M. Ticos5 , D. Sporea5 , R. Vasilache6 , V. Ionescu1 and M. Oane5 1 Center of Technology and Engineering for Nuclear Projects, 409 Atomistilor Str., PO Box 5204-MG-4, Magurele (Ilfov) 077125, Romania 2 University of Bucharest, Faculty of Physics, Doctoral School on Physics, 405 Atomistilor Str., PO Box MG-11, Magurele (Ilfov) 077125, Romania 3 University of Bucharest, Faculty of Physics, Department of Structure of Matter, Earth and Atmospheric Physics and Astrophysics, 405 Atomistilor Str., PO Box MG-11, Magurele (Ilfov) 077125, Romania 4 Frank Neutron Physics Laboratory, Joint Institute for Nuclear Research, 141980 Dubna, Russian Federation 5 National Institute for Laser, Plasma and Radiation Physics, 409 Atomistilor Str., 077125 Magurele (Ilfov), Romania 6 Canberra Packard SRL, 18 Clejani Str., 051036 Bucharest, Romani...
Ultra-high intensity lasers in use are connected with ionizing radiation sources that raise a rea... more Ultra-high intensity lasers in use are connected with ionizing radiation sources that raise a real concern in relation to installations , personnel, population and environment protection. The shielding of target areas in these facilities has to be evaluated from the conceptual stage of the building design. The sizing of the protective concrete walls was determined using computer codes such as Fluka. For the experiments to be carried out in the facility of the Center for Advanced Laser Technologies (CETAL), both proton beams with the energy of 100 MeV and electron beams with 300 MeV energy were considered to calculate the dimensions of structural shielding and to establish technical solutions fulfilling the radiation protection constraints imposed by the National Commission for Nuclear Activities Control.
... DRY INTERIM STORAGE FACILITY FOR SPENT FUEL CERNAVODA NPP MARIA RADU, MARCELA STANCIU, ADRIAN... more ... DRY INTERIM STORAGE FACILITY FOR SPENT FUEL CERNAVODA NPP MARIA RADU, MARCELA STANCIU, ADRIAN PANAIT, TRAIAN BARBU, SILVIA MATEESCU, DOINA PANTAZI Center of ... The sealing of the basket would be done using an automatic welding machine. ...
Low and intermediate radioactive gaseous, liquid and solid waste produced at Cernavoda Nuclear Po... more Low and intermediate radioactive gaseous, liquid and solid waste produced at Cernavoda Nuclear Power Plant must be well known from the point of view of contained radionuclide activity, during all steps of their processing, storage and transport, to ensure the nuclear safety of radioactive waste management. As in intermediate storage stage, the waste activity changes by radioactive decay and nuclear transmutation, the evolution in time of these sources is necessary to be assessed, for the purpose of biological shielding determination at any time. On the other hand, during the transport of waste package at the repository, the external dose rates must meet the national and international requirements concerning radioactive materials transportation on public roads. In this paper, a calculation methodology for waste characterization based on external exposure rate measurement and on sample analysis results is presented. The time evolution of waste activity, as well as the corresponding sh...
Low and intermediate radioactive gaseous, liquid and solid waste produced at Cernavoda Nuclear Po... more Low and intermediate radioactive gaseous, liquid and solid waste produced at Cernavoda Nuclear Power Plant must be well known from the point of view of contained radionuclide activity, during all steps of their processing, storage and transport, to ensure the nuclear safety of radioactive waste management. As in intermediate storage stage, the waste activity changes by radioactive decay and nuclear transmutation, the evolution in time of these sources is necessary to be assessed, for the purpose of biological shielding determination at any time. On the other hand, during the transport of waste package at the repository, the external dose rates must meet the national and international requirements concerning radioactive materials transportation on public roads. In this paper, a calculation methodology for waste characterization based on external exposure rate measurement and on sample analysis results is presented. The time evolution of waste activity, as well as the corresponding sh...
Ultra-high intensity lasers in use are connected with ionizing radiation sources that raise a rea... more Ultra-high intensity lasers in use are connected with ionizing radiation sources that raise a real concern in relation to installations, personnel, population and environment protection. The shielding of target areas in these facilities has to be evaluated from the conceptual stage of the building design. The sizing of the protective concrete walls was determined using computer codes such as Fluka. For the experiments to be carried out in the facility of the Center for Advanced Laser Technologies (CETAL), both proton beams with the energy of 100 MeV and electron beams with 300 MeV energy were considered to calculate the dimensions of structural shielding and to establish technical solutions fulfilling the radiation protection constraints imposed by the National Commission for Nuclear Activities Control.
2019 International Conference on ENERGY and ENVIRONMENT (CIEM), 2019
The purpose of this work is to present the results of a study regarding the behaviour of fresh CA... more The purpose of this work is to present the results of a study regarding the behaviour of fresh CANDU nuclear fuel immersed in light water (H2O) following a road accident scenario. The criticality simulations were made using KENO-V.a code, one of the computational tools provided by SCALE 6.2.1. The study evaluates the criticality potential, namely the effective multiplication factor keff for two types of nuclear fuel, formed out of fuel bundles containing 37 and 43 fuel elements, with the following enrichments 0.9%, 1.1% and 1.3% U235.
Microbial Degradation Processes in Radioactive Waste Repository and in Nuclear Fuel Storage Areas, 1997
... DRY INTERIM STORAGE FACILITY FOR SPENT FUEL CERNAVODA NPP MARIA RADU, MARCELA STANCIU, ADRIAN... more ... DRY INTERIM STORAGE FACILITY FOR SPENT FUEL CERNAVODA NPP MARIA RADU, MARCELA STANCIU, ADRIAN PANAIT, TRAIAN BARBU, SILVIA MATEESCU, DOINA PANTAZI Center of ... The sealing of the basket would be done using an automatic welding machine. ...
2021 10th International Conference on ENERGY and ENVIRONMENT (CIEM)
The aim of this work is to present the results obtained from the irradiation of a CANDU 6 fuel as... more The aim of this work is to present the results obtained from the irradiation of a CANDU 6 fuel assembly within a time of 327 days with a 23,853 MW/tU cycle specific power followed by a 50-year decay, using the ORIGEN and ARP calculation codes which are included in the SCALE 6.2.2. code system. The ORIGEN library was prepared by ARP to have three sets of burnup-dependent transition cross-sections, resulting in three cases, one for each of the irradiation intervals proposed by the study: 100, 100, 127 days at a maximum fuel burnup of 7800 MW.day/tU. The input material has been specified to have 1 ton of metallic uranium with an enrichment of 0.7145% in U235. Simulating the irradiation of nuclear fuel within the reactor leads to the follow up of its radiological characteristics, required in the stages of surface storage as radioactive waste.
The modulated code system SCALE is used to perform a standardized shielding analysis for any faci... more The modulated code system SCALE is used to perform a standardized shielding analysis for any facility containing spent fuel: handling devices, transport cask, intermediate and final storage facility. The neutron and gamma sources as well as the dose rates can be obtained using either discrete-ordinates or Monte Carlo methods. The shielding analysis control modules (SAS1, SAS2H and SAS4) provide a general procedure for cross-section preparation, fuel depletion/decay calculation and general onedimensional or multi-dimensional shielding analysis. The module SAS4 used in the analysis presented in this paper, is a three-dimensional Monte Carlo shielding analysis module, which uses an automated biasing procedure specialized for a nuclear fuel transport or storage container. The Spent Fuel Interim Storage Facility in our country is projected to be a parallelepiped concrete monolithic module, consisting of an external reinforced concrete structure with vertical storage cylinders (pits) arra...
Inside the concrete used as a material for the protection shields against ionizing radiation comi... more Inside the concrete used as a material for the protection shields against ionizing radiation coming from the core of the reactor, various processes and physical and chemical reactions have to be taken into account when the efficiency of the shield is analyzed throughout the operation life of the nuclear power plant. The paper looked at how the concrete can be affected by the irradiation with neutrons and gamma radiation under conditions of possible high fluence outside an reactor core.
RADIOLOGICAL SAFETY ASSESSMENT FOR THE EXPERIMENTAL AREA OF A HYPER-INTENSE LASER WITH PEAK—POWER... more RADIOLOGICAL SAFETY ASSESSMENT FOR THE EXPERIMENTAL AREA OF A HYPER-INTENSE LASER WITH PEAK—POWER OF 1PW—CETAL M. G. Florescu1,2, O. G. Duliu3,4,*, D. Pantazi1 , C. M. Ticos5 , D. Sporea5 , R. Vasilache6 , V. Ionescu1 and M. Oane5 1 Center of Technology and Engineering for Nuclear Projects, 409 Atomistilor Str., PO Box 5204-MG-4, Magurele (Ilfov) 077125, Romania 2 University of Bucharest, Faculty of Physics, Doctoral School on Physics, 405 Atomistilor Str., PO Box MG-11, Magurele (Ilfov) 077125, Romania 3 University of Bucharest, Faculty of Physics, Department of Structure of Matter, Earth and Atmospheric Physics and Astrophysics, 405 Atomistilor Str., PO Box MG-11, Magurele (Ilfov) 077125, Romania 4 Frank Neutron Physics Laboratory, Joint Institute for Nuclear Research, 141980 Dubna, Russian Federation 5 National Institute for Laser, Plasma and Radiation Physics, 409 Atomistilor Str., 077125 Magurele (Ilfov), Romania 6 Canberra Packard SRL, 18 Clejani Str., 051036 Bucharest, Romani...
Ultra-high intensity lasers in use are connected with ionizing radiation sources that raise a rea... more Ultra-high intensity lasers in use are connected with ionizing radiation sources that raise a real concern in relation to installations , personnel, population and environment protection. The shielding of target areas in these facilities has to be evaluated from the conceptual stage of the building design. The sizing of the protective concrete walls was determined using computer codes such as Fluka. For the experiments to be carried out in the facility of the Center for Advanced Laser Technologies (CETAL), both proton beams with the energy of 100 MeV and electron beams with 300 MeV energy were considered to calculate the dimensions of structural shielding and to establish technical solutions fulfilling the radiation protection constraints imposed by the National Commission for Nuclear Activities Control.
... DRY INTERIM STORAGE FACILITY FOR SPENT FUEL CERNAVODA NPP MARIA RADU, MARCELA STANCIU, ADRIAN... more ... DRY INTERIM STORAGE FACILITY FOR SPENT FUEL CERNAVODA NPP MARIA RADU, MARCELA STANCIU, ADRIAN PANAIT, TRAIAN BARBU, SILVIA MATEESCU, DOINA PANTAZI Center of ... The sealing of the basket would be done using an automatic welding machine. ...
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