Soils radiological characterization under a nuclear facility

2012 ◽  
pp. 52-60
Author(s):  
Emilie Aubonnet ◽  
Didier Dubot
Keyword(s):  
Nuclear Facility ◽  
Radiological Characterization

Soils Radiological Characterization Under a Nuclear Facility

2011 ◽  
Author(s):  
Emilie Aubonnet ◽  
Didier Dubot
Keyword(s):  
Surface Characterization ◽  
First Generation ◽  
Atomic Energy Commission ◽  
Nuclear Industry ◽  
Nuclear Facility ◽  
Nuclear Facilities ◽  
Alternative Energies ◽  
Radiological Characterization ◽  
Remediation Process

Nowadays, nuclear industry is facing a crucial need in establishing radiological characterization for the appraisal and the monitoring of any remediation work. Regarding its experience in this domain, the French Alternative Energies and Atomic Energy Commission (CEA) of Fontenay-aux-Roses, established an important feedback and developed over the last 10 years a sound methodology for radiological characterization. This approach is based on several steps: - historical investigations; - assumption and confirmation of the contamination; - surface characterization; - in-depth characterization; - rehabilitation objectives; - remediation process. The amount of measures, samples and analysis is optimized for data processing using geostatistics. This approach is now used to characterize soils under facilities. The paper presents the radiological characterization of soils under a facility basement. This facility has been built after the first generation of nuclear facilities, replacing a plutonium facility which has been dismantled in 1960. The presentation details the different steps of radiological characterization from historical investigations to optimization of excavation depths, impact studies and contaminated volumes.

scholarly journals Development of a Multifunctional Radiation Measurement System for the Rapid Radiological Characterization of a Decommissioned Nuclear Facility Site

2021 ◽  
Vol 2021 ◽  
pp. 1-12
Author(s):  
Han Young Joo ◽  
Jae Wook Kim ◽  
Young Seo Kim ◽  
So Yun Jeong ◽  
Bongsoo Lee ◽  
...  
Keyword(s):  
Gamma Radiation ◽  
Measurement System ◽  
Measurement Data ◽  
Soil Surface ◽  
Radiation Detectors ◽  
Radiation Measurement ◽  
Nuclear Facility ◽  
Laptop Computer ◽  
Radiological Characterization

In this study, a radiation measurement system with multifunctions for the rapid radiological characterization of a decommissioned nuclear facility site was developed and evaluated. The system remotely and simultaneously measures the beta and gamma radiation from the soil at a decommissioned nuclear facility site and wirelessly transmits the measurement data to the main server, which collects and analyzes the data. The radiation-measuring part of the system is composed of a sensing probe, multichannel analyzer (MCA), and laptop computer. The sensing probe is a phoswich radiation sensor (PHORS) consisting of two inorganic scintillators (NaI(Tl) and CaF2(Eu)), each of which simultaneously measures the count rates and energies of the beta and gamma radiation. To test the performance of the PHORS, the beta and gamma radiation from a radiation source at 0–10 cm depths (at steps of 1 cm) under a soil surface was measured. The measurements show that the radiation count rates agree well with the theoretically predicted ones; the PHORS is as good as commercial radiation detectors in providing the energy spectrum of a radionuclide. In addition, a chi-square test was conducted, and the energy resolution was evaluated. The communication part of the system consisting of a global positioning system (GPS) and long-term evolution telecommunication (LTE) modem can successfully transmit the measurement data and their location information.

Radiological Characterization Methods Specifically Applied to the Preparation of the Dismantling of PHENIX Fast Reactor

2013 ◽  
Author(s):  
J. Venara ◽  
M. Ben Mosbah ◽  
C. Mahé ◽  
M. Masson ◽  
J. L. Paul
Keyword(s):  
Gamma Spectrometry ◽  
Measurement Techniques ◽  
Small Scale ◽  
Nuclear Facility ◽  
Activity Profile ◽  
Scanning Method ◽  
Characterization Methods ◽  
Gamma Imaging ◽  
Isotopic Characterization ◽  
Radiological Characterization

Knowledge of the radiological state of processes and equipment of a nuclear facility is essential to supervise a wide variety of sensitive tasks: building of intervention scenarios in order to optimize maintenance or dismantling operations, optimization of waste categorization, monitoring the effectiveness of decontamination processes, monitoring of nuclear facility decommissioning, etc. In order to meet the diversity of the issues involved, the CEA has developed in situ radiological characterization methods and techniques to acquire reliable radiological data. The data gathered is necessary to build robust radiological models which can be used as input data for dismantling studies. Over the last 30 years, the main nuclear measurement techniques, such as gamma imaging and gamma spectrometry, have been widely deployed by the CEA on many facilities under dismantling and more recently, on the Phénix nuclear power plant. Phénix was a small-scale prototype of a sodium-cooled fast breeder reactor, located at the Marcoule nuclear site. These techniques have been implemented on this reactor in order to meet the increased need for radiological knowledge to prepare for future dismantling operations following its final shutdown in 2009. This paper will focus on the description of three radiological characterization methods which take advantage of advanced nuclear measurement techniques. For each method, an example of a specific application on the Phénix reactor will be presented. Firstly, the so-called “gamma scanning” method will be explained. The objective of this method is to determine the activity profile of equipment based on collimated gamma spectrometry measurements with compact probes like CdZnTe. This method was applied to a neutron shielding of the reactor core to estimate the 60Co activity profile. Then the measured activities helped to validate the theoretical activities resulting from neutron activation calculations. Secondly, this paper will focus on the interest of combining different measurement techniques such as gamma imaging, gamma spectrometry and collimated/uncollimated dose rate mapping to characterize complex equipment or processes. In this case, a specific methodology was developed to define the radiological state of a shielded cell used for the processing of irradiated nuclear fuels. Finally, an isotopic characterization technique using a high purity germanium detector will be discussed. This technique was applied to a non-irradiated fertile fuel sub-assembly in order to determine the level of uranium enrichment. The processing was carried out by three types of analysis: two automated, with the MGA-U and IGA software, and one manual.

Superposition of Potential Chemical Polluants and Radioisotopes and Their Influence Upon the Environment and Living Organisms

2017 ◽  
Vol 68 (9) ◽  
pp. 2189-2195
Author(s):  
Valeriu V. Jinescu ◽  
Simona Eugenia Manea ◽  
George Jinescu ◽  
Vali Ifigenia Nicolof
Keyword(s):  
Solid Waste ◽  
Critical Energy ◽  
Radioactive Isotopes ◽  
Nuclear Facility ◽  
Chemical Pollutants ◽  
Living Organisms

Following the activities developed in a nuclear facility result gaseous and liquid radioactive effluents and radioactive solid waste. All these waste contain radioactive isotopes which are potentially pollutants for the environment. In the same time chemicals are, also, pollutants. According to the legislation, discharging of chemicals and radioactive liquid and gaseous effluents into the environment, should meet the requirements of the unrestricted discharge. However, what happens when several pollutants superpose: only chemical pollutants, or only radioactive pollutants, or chemical and radioactive pollutants? Such problems have been solved in this paper on the basis of the principle of critical energy.

Retention of Some Radionuclides on Soil in Site Selection for Nuclear Facility

2020 ◽  
Vol 62 (5) ◽  
pp. 658-666
Author(s):  
D. M. Imam ◽  
M. M. Hamed ◽  
M. F. Attallah
Keyword(s):  
Site Selection ◽  
Nuclear Facility ◽  
Selection For

scholarly journals MCNP model of L-54M nuclear research reactor: validation by preliminary graphite radiological characterization

2019 ◽  
Vol 322 (3) ◽  
pp. 1341-1350
Author(s):  
Eros Mossini ◽  
Luca Codispoti ◽  
Giorgio Parma ◽  
Filippo Maria Rossi ◽  
Elena Macerata ◽  
...  
Keyword(s):  
Research Reactor ◽  
Nuclear Research ◽  
Nuclear Research Reactor ◽  
Radiological Characterization

Radiological characterization of a uranium mine with no mining activity

2000 ◽  
Vol 53 (1-2) ◽  
pp. 337-343 ◽  
Author(s):  
J.C. Lozano ◽  
F. Vera Tomé ◽  
V. Gómez Escobar ◽  
P. Blanco Rodrı́guez
Keyword(s):  
Mining Activity ◽  
Uranium Mine ◽  
Radiological Characterization

Radiological characterization of peloids obtained by maturation with Águas de Lindóia, Poços de Caldas and Peruíbe waters

2021 ◽  
Vol 9 (1A) ◽  
Author(s):  
Jefferson Koyaishi Torrecilha ◽  
Jussara Marques Oliveira Marrichi ◽  
Eduardo Aparecido Pirani de Souza ◽  
Paulo Flávio De Macedo Gouvêa ◽  
Isis Campos Alves ◽  
...  
Keyword(s):  
Poços De Caldas ◽  
Radiological Characterization

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