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1

Bahati, Ass Serge Kambale, Patrick Mumbere Mubekwa und Prof Tondozi Keto. „Valorisation Energétique Des Déchets Solides Dans La Ville De Kisangani / Commune De Makiso“. International Journal of Progressive Sciences and Technologies 41, Nr. 1 (31.10.2023): 228. http://dx.doi.org/10.52155/ijpsat.v41.1.5668.

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Le concept de « développement durable » se résume en trois « E » environnement, Energie et Economie. Il a apparu avec les problèmes de changement climatiques et l’épuisement des ressources énergétiques. Il faut trouver un équilibre entre prospérité économique, besoin énergétique et protection de l’environnement pour assurer un développement durable. L’énergie est le cerveau de l’économie mondial et permettant à des nombreuses populations de jouir de confort, de productivité et de mobilité des très hauts niveaux. De prime abord, nous avons tous besoins de l’énergie permanente, que ce soit pour cuisiner, pour éclairer, pour chauffer ou climatiser nos domiciles. L’énergie mondiale, provenant des ressources fossiles (charbon, pétrole et gaz naturel) utilisées à l’ère actuelle sont épuisables donc non renouvelable et leur utilisation sera plus coûteuse ; de plus elle est la première source d’émission des gaz à effet de serre (à savoir le 𝐶𝑂2, 𝐶𝐻4 … … ..) donc, Contribue au réchauffement climatique de la planète terrestre. Afin de résoudre ce problème d’émission, un bon nombre des personnes sont engagées dans la production d’électricité d’origine nucléaire, avec un problème de la gestion des tonnes de déchets radioactifs dégagées lors de son fonctionnement. Voilà pourquoi il est urgent de trouver des nouvelles sources énergétiques alternatives propres et inépuisables. C’est le cas des énergies issues du soleil, du vent, de l’eau, et des biomasses. Ces sources d’énergie renouvelable sont un moyen efficace de contribuer au développement durable d’un pays. A partir de ces énergies, il est possible de produire de la chaleur ou d’électricité en cogénération avec un minimum de pollution de l’environnement.
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2

Furuta, Etsuko, Yukio Yoshizawa und Tamaru Aburai. „Comparisons between radioactive and non-radioactive gas lantern mantles“. Journal of Radiological Protection 20, Nr. 4 (22.11.2000): 423–31. http://dx.doi.org/10.1088/0952-4746/20/4/305.

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3

OISHI, Tetsuya, und Makoto YOSHIDA. „Response Analysis of Radioactive Gas Monitors for Short Duration Inflow of Radioactive Gas“. Journal of Nuclear Science and Technology 38, Nr. 12 (Dezember 2001): 1115–19. http://dx.doi.org/10.1080/18811248.2001.9715144.

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4

Osada, N., Y. Oki, H. Kanda, K. Yamasaki und S. Shibata. „Application of a graded screen array for size measurements of radioactive aerosols in accelerator rooms“. Proceedings in Radiochemistry 1, Nr. 1 (01.09.2011): 251–55. http://dx.doi.org/10.1524/rcpr.2011.0044.

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Abstract A rapid measurement method for aerosol particle size is required to clarify the formation mechanism of freshly-formed radioactive aerosols in accelerator rooms. A graded screen array (GSA) method only requires brief sampling. Therefore, the GSA method is suitable for the measurement of radioactive aerosols in the accelerator rooms. In this work, a conventional GSA was applied to measure the particle size distribution of an aerosol. An influence of the radioactive gas on the GSA measurement was found. The adsorption of radioactive gases resulted in a discrepancy between the results of the GSA method and those of the diffusion battery method. An improved GSA method was developed to measure the radioactive aerosol formed in the accelerator room. The adsorption was measured by the improved GSA, and the influence of the radioactive gas was eliminated. The result of the improved GSA showed fair agreement with that of the diffusion battery system.
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5

Di Donna, Alice, Pascal Charrier, Simon Salager und Pierre Bésuelle. „Self-sealing capacity of argillite samples“. E3S Web of Conferences 92 (2019): 03005. http://dx.doi.org/10.1051/e3sconf/20199203005.

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Many countries are currently facing the issue of finding a proper solution to store radioactive wastes coming from nuclear energy production plants. The possibility to store them in underground tunnels is largely considered and investigated. In France, Andra (Agence Nationale pour la gestion des Déchets Radioactifs) selected the Callovo-Oxfordian rock clay (COx) situated in the Meuse/Haute Marne site (France) between 400 and 600 m depth as possible host rock deposit. The excavation of the storage tunnels is expected to create a fractured zone around galleries. However, the factures will be then gradually re-saturated by the underground water coming from the surrounding rock mass and the fractures are expected to self-seal in contact with water, thanks to the swelling potential of COx. The capacity of self-sealing of COx, i.e. closing of fractures after water contact and possibly restoring of hydraulic permeability, is thus of primary interest for the safety of the storage system with respect to water, gas and solutes transport. In the work presented in this paper, the self-sealing behaviour of the COx argillite was investigated through x-ray tomography. The tested samples show significantly different responses depending on the zone where they have been collected on site. The results of mineralogical analyses (x-ray diffraction) are used to understand the observed phenomena.
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6

Ann Glass Geltman, Elizabeth, und Nichole LeClair. „Variance in State Protection from Exposure to NORM and TENORM Wastes Generated During Unconventional Oil and Gas Operations: Where We Are and Where We Need to Go“. NEW SOLUTIONS: A Journal of Environmental and Occupational Health Policy 28, Nr. 2 (06.02.2018): 240–61. http://dx.doi.org/10.1177/1048291118755387.

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Radioactive materials for the medical, technological, and industrial sectors have been effectively regulated in the United States since as early as 1962. The steady increase in the exploration and production of shale gas in recent years has led to concerns about exposures to Naturally Occurring Radioactive Materials (NORM) and Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM) in oil and gas waste streams. This study applied policy surveillance methods to conduct a cross-sectional fifty-state survey of law and regulations of NORM and TENORM waste from oil and gas operations. Results indicated that seventeen states drafted express regulations to reduce exposure to oil and gas NORM and TENORM waste. States with active oil and gas drilling that lack regulations controlling exposure to NORM and TENORM may leave the public and workers susceptible to adverse health effects from radiation. The study concludes with recommendations in regard to regulating oil and gas NORM and TENORM waste.
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7

Liland, A., P. Strand, I. Amundsen, H. Natvig, M. Nilsen, R. Lystad und K. E. Frogg. „Advances in NORM management in Norway and the application of ICRP's 2007 Recommendations“. Annals of the ICRP 41, Nr. 3-4 (Oktober 2012): 332–42. http://dx.doi.org/10.1016/j.icrp.2012.06.021.

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In Norway, the largest reported quantities of radioactive discharges and radioactive waste containing naturally occurring radioactive material (NORM) come from the oil and gas sector, and smaller quantities of other NORM waste are also produced by industrial or mining processes. The Gulen final repository for radioactive waste from the oil and gas industry from the Norwegian continental shelf was opened in 2008 and has a capacity of 6000 tonnes. As of 1 January 2011, a new regulation was enforced whereby radioactive waste and radioactive pollution was integrated in the Pollution Control Act from 1981. This means that radioactive waste and radioactive pollution are now regulated under the same legal framework as all other pollutants and hazardous wastes. The regulation establishes two sets of criteria defining radioactive waste: a lower value for when waste is considered to be radioactive waste, and a higher value, in most cases, for when this waste must be disposed of in a final waste repository. For example, waste containing ≥1 Bq/g of Ra-226 is defined as radioactive waste, while radioactive waste containing ≥10 Bq/g of Ra-226 must be disposed of in a final repository. Radioactive waste between 1 and 10 Bq/g can be handled and disposed of by waste companies who have a licence for handling hazardous waste according to the Pollution Control Act. Alternatively, they will need a separate licence for handling radioactive waste from the Norwegian Radiation Protection Authority. The goal of the new regulation is that all radioactive waste should be handled and stored in a safe manner, and discharges should be controlled through a licensing regime in order to avoid/not pose unnecessary risk to humans or the environment. This paper will elaborate on the new regulation of radioactive waste and the principles of NORM management in Norway in view of the International Commission on Radiological Protection's 2007 Recommendations.
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McKay, Scott, Stuart A. Higgins und Peter Baker. „NORM inventory forecast for Australian offshore oil and gas decommissioned assets and radioactive waste disposal pathways“. APPEA Journal 60, Nr. 1 (2020): 19. http://dx.doi.org/10.1071/aj19159.

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This research establishes a decommissioning timeline for the existing oil and gas facilities across all of the Australian offshore oil and gas production basins. Minimal data exist in the public domain to estimate these decommissioning timelines and, more importantly, the significant waste volumes generated; including potentially hazardous wastes such as naturally occurring radioactive material (NORM). At this time there is no approved onshore radioactive waste disposal pathway in Australia to accommodate this material. Applying an estimation methodology, based on Norwegian decommissioning data with regional activity factors, allows a NORM waste forecast to be established for the decommissioning of Australian oil and gas offshore infrastructure. The total NORM disposal burden is estimated to be in the range of 223–1674 tonnes for decommissioning activity to 2060, with over 68% of this material generated between 2018 and 2025. Due to the sparsity of public domain data this forecast is deemed to be uncertain and excludes the NORM contamination anticipated to be present in subsea export pipelines, trunklines and well production tubing. Current regulations governing the categorisation and disposal of radioactive wastes across Australia are complex and regionally dependent. This regional variation makes the implementation of a national radioactive waste disposal facility more difficult, and encourages the export of radioactive wastes overseas for final disposal. Exporting of radioactive wastes potentially presents a higher risk compared with in-country disposal and is likely not an effective long-term proposition. A comprehensive NORM data collection and quantification assessment programme, spanning all onshore and offshore oil and gas infrastructure, needs to implemented to drive and verify a NORM waste management strategy for the wave of facility decommissioning projects that are fast approaching.
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9

Unterweger, M. P. „Primary radioactive gas standards (excluding radon)“. Metrologia 44, Nr. 4 (August 2007): S79—S81. http://dx.doi.org/10.1088/0026-1394/44/4/s10.

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10

Hayes, J. C., T. W. Bowyer, E. A. Cordova, R. R. Kirkham, A. Misner, K. B. Olsen, V. T. Woods und Dudley Emer. „Underground sources of radioactive noble gas“. Journal of Radioanalytical and Nuclear Chemistry 296, Nr. 2 (04.10.2012): 869–76. http://dx.doi.org/10.1007/s10967-012-2214-z.

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11

Salam, R. M., F. F. Nurhaini, R. Anggakusuma, A. Shidiq und B. A. N. Putra. „Iodine Gas Detection System Using Color Sensor“. Journal of Physics: Conference Series 2705, Nr. 1 (01.02.2024): 012020. http://dx.doi.org/10.1088/1742-6596/2705/1/012020.

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Abstract Iodine can exist in the form of radioactive and non-radioactive states. Radioactive Iodine-131 (I-131) has been utilized in nuclear facilities. Due to its ability to be absorbed by the thyroid gland, I-131 is used for therapy in thyroid cancer cases. Contrary to the benefit, Iodine is a volatile material that becomes a health problem if humans inhale more than a certain dose under a certain period. Thus, to prevent overexposure to Iodine, all Iodine-related facilities must equip their facilities with Iodine detection systems. The most common radioactive detection system uses an expensive Na(Tl), and HPGe detector. So, this study will build a low-cost iodine detection system by means of a low-cost color-based sensor utilizing the color property of the Iodine gasses. This finding showed that the color sensor will detect the Iodine gas leaks in the air in a range of 0 - 100 ppm, resulting in a pink-dark purple color. This finding showed that the sensor could detect low concentrations of Iodine gas in particular areas very well. Since the good resolution of this detection system, it will be promising to be applied in a real-time iodine gasses detection system.
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12

Ogawa, Hiroshi, Kenta Iyoki, Minoru Matsukura, Toru Wakihara, Ko Abe, Kentaro Miuchi und Saori Umehara. „Measurement of radon emanation and impurity adsorption from argon gas using ultralow radioactive zeolite“. Journal of Instrumentation 19, Nr. 02 (01.02.2024): P02004. http://dx.doi.org/10.1088/1748-0221/19/02/p02004.

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Abstract The amount of radioactive impurities contaminated in the detector gases is required to be kept at a very low level for rare event particle physics such as dark matter and neutrino observation experiments. Zeolite is a well-known class of materials and is one of the possible candidates for removing impurities from gases. At the same time, the amount of radioactive impurities released from the adsorbent material needs to be sufficiently small. In this paper, a development of a new ultralow radioactive zeolite as a product of the selection of ultralow radioactive materials is reported. Results on the radon emanation and impurity adsorption from argon gas measurements are also described.
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13

Tauber, Christian, David Schmoll, Johannes Gruenwald, Sophia Brilke, Peter Josef Wlasits, Paul Martin Winkler und Daniela Wimmer. „Characterization of a non-thermal plasma source for use as a mass specrometric calibration tool and non-radioactive aerosol charger“. Atmospheric Measurement Techniques 13, Nr. 11 (11.11.2020): 5993–6006. http://dx.doi.org/10.5194/amt-13-5993-2020.

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Abstract. In this study the charging efficiency of a radioactive and a non-radioactive plasma bipolar diffusion charger (Gilbert Mark I plasma charger) for sub-12 nm particles has been investigated at various aerosol flow rates. The results were compared to classic theoretical approaches. In addition, the chemical composition and electrical mobilities of the charger ions have been examined using an atmospheric pressure interface time-of-flight mass spectrometer (APi-TOF MS). A comparison of the different neutralization methods revealed an increased charging efficiency for negatively charged particles using the non-radioactive plasma charger with nitrogen as the working gas compared to a radioactive americium bipolar diffusion charger. The mobility and mass spectrometric measurements show that the generated bipolar diffusion charger ions are of the same mobilities and composition independent of the examined bipolar diffusion charger. It was the first time that the Gilbert Mark I plasma charger was characterized in comparison to a commercial TSI X-Ray (TSI Inc, Model 3088) and a radioactive americium bipolar diffusion charger. We observed that the plasma charger with nitrogen as the working gas can enhance the charging probability for sub-10 nm particles compared to a radioactive americium bipolar diffusion charger. As a result, the widely used classical charging theory disagrees for the plasma charger and for the radioactive chargers with increased aerosol flow rates. Consequently, in-depth measurements of the charging distribution are necessary for accurate measurements with differential or scanning particle sizers for laboratory and field applications.
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14

Clayton, D. D. „Condensation of Carbon in Radioactive Supernova Gas“. Science 283, Nr. 5406 (26.02.1999): 1290–92. http://dx.doi.org/10.1126/science.283.5406.1290.

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15

Clayton, Donald D., Ethan A. ‐N Deneault und Bradley S. Meyer. „Condensation of Carbon in Radioactive Supernova Gas“. Astrophysical Journal 562, Nr. 1 (20.11.2001): 480–93. http://dx.doi.org/10.1086/323467.

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16

Loncar, B., P. Osmokrovic und S. Stankovic. „Radioactive reliability of gas filled surge arresters“. IEEE Transactions on Nuclear Science 50, Nr. 5 (Oktober 2003): 1725–31. http://dx.doi.org/10.1109/tns.2003.818269.

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17

Alves, Carlos, und Jorge Sanjurjo-Sánchez. „Geological Materials as Sources of Rn Emissions“. Proceedings 24, Nr. 1 (05.06.2019): 17. http://dx.doi.org/10.3390/iecg2019-06193.

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Geological materials are a potential source of pollutants, among which there is the radioactive isotope 222Rn, which result of radioactive decay of daughter radionuclides of uranium (238U). It is emitted as a gas that it can be released to the air to enter the human body, with the potential to affect internal organs (mostly the lungs) by alpha particles production. While the presence of uranium in the materials is a necessary condition for the production of Rn-222, the amount of gas emitted by the material depends on other characteristics that allow the migration of the gas. The main aim of this communication concerns a statistical analysis of results from diverse types of rocks.
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18

Nassif, Cláudio, A. C. Amaro de Faria und Rodrigo Francisco dos Santos. „Testing Lorentz symmetry violation with an invariant minimum speed“. Modern Physics Letters A 33, Nr. 23 (29.07.2018): 1850148. http://dx.doi.org/10.1142/s0217732318501481.

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This work presents an experimental test of Lorentz invariance violation in the infrared (IR) regime by means of an invariant minimum speed in spacetime and its effects on the time when an atomic clock given by a certain radioactive single-atom (e.g. isotope Na[Formula: see text]) is a thermometer for an ultracold gas like the dipolar gas Na[Formula: see text]K[Formula: see text]. So, according to a Deformed Special Relativity (DSR) so-called Symmetrical Special Relativity (SSR), where there emerges an invariant minimum speed V in the subatomic world, one expects that the proper time of such a clock moving close to V in thermal equilibrium with the ultracold gas is dilated with respect to the improper time given in lab, i.e. the proper time at ultracold systems elapses faster than the improper one for an observer in the lab, thus leading to the so-called proper time dilation so that the atomic decay rate of an ultracold radioactive sample (e.g. Na[Formula: see text]) becomes larger than the decay rate of the same sample at room temperature. This means a suppression of the half-life time of a radioactive sample thermalized with an ultracold cloud of dipolar gas to be investigated by NASA in the Cold Atom Lab (CAL).
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Zaidan, Jamal Abdul Rahman. „Natural Occurring Radioactive Materials (NORM) in the oil and gas industry“. Journal of Petroleum Research and Studies 1, Nr. 1 (05.05.2021): 4–21. http://dx.doi.org/10.52716/jprs.v1i1.22.

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Radioactive materials which occur naturally and expose people to radiation occur widely, and are known by the acronym 'NORM'. Exposure to NORM is often increased by human activities, eg burning coal, making and using fertilisers, oil and gas production. Many natural materials contain radioactive elements (radionuclides). The earth's crust is radioactive and constantly leaks radon gas into our atmosphere. However, while the level of individual exposure from all this is usually trivial, some issues arise regarding regulation, and also perspective in relation to what is classified as radioactive waste.The radionuclides identified in oil and gas streams belong to the decay chains of the naturally occurring primordial radionuclides 238U and 232Th. Analyses of NORM from many different oil and gas fields show that the solids found in the downhole and surface structures of oil and gas production facilities do not include 238U and 232Th. gas These elements are not mobilized from the reservoir rock that contains the oil, gas and formation water. Formation water contains the radium isotopes 226Ra from the 238U series, and 228Ra and 224Ra from the 232Th series. All three radium isotopes, but not their parents, thus appear in the water co-produced with the oil or gas. The 228Th radionuclide sometimes detected in aged sludge. This causes their precipitation as sulphate and carbonate scales. The mixed stream of oil, and water also carries the noble gas 222Rn that is generated in the reservoir rock through decay of 226Ra. It would appear that the concentrations of 226Ra, 228Ra and 224Ra in scales and sludge range from less than 0.1 Bq/g up to 15 000 Bq/g. Generally, the activity concentrations of radium isotopes are lower in sludge than in scales, the opposite applies to 210Pb. The deposition of contaminated scales and sludge in pipes and vessels may produce significant dose rates inside and outside these components. Maximum dose rates are usually in the range of up to a few microsieverts per hour. In exceptional cases, dose rates measured directly on the outside surfaces of production equipment have reached several hundred microsieverts per hour, which is about 1000 times greater than normal background values due to cosmic radiation and terrestrial radiation.
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Мусаев Ровшан Али оглы und Карим Джавиди Тарзило. „ЭКОЛОГИЧЕСКОЕ СОСТОЯНИЕ АПШЕРОНСКОГО ПОЛУОСТРОВА“. World Science 2, Nr. 8(36) (30.08.2016): 63–68. http://dx.doi.org/10.31435/rsglobal_ws/30082018/6069.

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This article investigates the areas exposed to radioactive contamination in the oil-producing fields of the six regions of the Republic of Azerbaijan covering the Apsheron peninsula. As a result of these studies, radioactive crisis areas where discovered, and the specific map was created.The semi-empiric formulas were used to estimate the concentration of harmful radon gas which is the fission product of radium isotope-one of the radio-isotopes causing irradiation. It is recommended that radioactive waste in the area be used for road transport in accordance with the norms.
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Bunert, Erik, Birger Bernhold, Jan N. Woidtke, Merle Sehlmeyer und Stefan Zimmermann. „Non-radioactive electron capture detector for gas chromatography — A possible replacement for radioactive detectors“. Journal of Chromatography A 1606 (November 2019): 460384. http://dx.doi.org/10.1016/j.chroma.2019.460384.

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22

Millot, Lucie, Hanaa Houjeij, Georges Matta, Jean-Yves Ferrandis, Didier Laux und Céline Monsanglant Louvet. „Radiolysis of bituminized radioactive waste: a comprehensive review“. EPJ Nuclear Sciences & Technologies 10 (2024): 4. http://dx.doi.org/10.1051/epjn/2024004.

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In the realm of radioactive waste management, the impact of radiolysis on bitumen and bituminized radioactive waste also called bituminized waste product (BWP) is considered one of the most significant factors influencing structural changes and the generation of radiolysis gas bubbles. This review provides a comprehensive overview of several studies that have explored the intricate interaction between radiation and various types of bitumen, to gain a better understanding of how such waste ages when exposed to radiation. While these studies provide insights into the diverse effects of radiolysis on bitumen, they also highlight numerous unanswered questions. The absence of gas bubbles does not necessarily indicate an absence of gas production, leaving further research to be undertaken. The complexities of bitumen radiolysis offer multiple avenues for future investigation, aiming to enhance our understanding and provide comprehensive solutions for bituminous radioactive waste management. Among the studied types of bitumen, blown R85/40 bitumen and straight-run distilled bitumen with a penetration grade of 70/100 stands out due to their widespread use in immobilizing co-precipitated radioactive sludges. These bituminous matrices play an essential role in understanding the broader implications of radiolysis within the context of bituminous waste management. This review underscores the significance of further research into radiolysis and bitumen ageing, emphasizing the need for a more in-depth exploration of these complex phenomena and their implications for the long-term safety and efficacy of repositories and disposal facilities.
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Asker, Mohammed M., Esam S. Ali und Sarwa A. Mohammed. „Determination Radon Concentration (Radon Gas) in Urine of Patients with Cancer“. NeuroQuantology 19, Nr. 4 (18.05.2021): 87–91. http://dx.doi.org/10.14704/nq.2021.19.4.nq21041.

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The present study aims at studying the measurement radon concentration (Radon gas) in the urine of patients with cancer, that made up of (23) different samples of patients’ urine. These samples have collected from Kirkuk Oncology & Hematology Center. Chemical etching process for CR-39 track detector has used to record the traces of Alpha particles “alpha rays” or “alpha radiation” that comes from Radon included in the models. The Plastic Tubing – Tubes that contain some models in reagent irradiation process, which shaped as U letter, have been used. The results illustrated that the highest concentration of Radon is (8.9) Bq.m-1 in R14 model, as well as the lowest concentration of Radon is (1.5) Bq.m-1 in R4 model. The Radon levels that have been measured are within the natural limits of radioactive decay caused by radioactive nuclide or “radioactive isotope” in urine of patients with cancer; these are not a risk in humanity.
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Arbutina, Dalibor, Aleksandra Vasic-Milovanovic, Teodora Nedic, Aco Janicijevic und Ljubinko Timotijevic. „Possibility of achieving an acceptable response rate of gas-filled surge arresters by substitution of alpha radiation sources by selection of electrode material and the electrode surface topography“. Nuclear Technology and Radiation Protection 35, Nr. 3 (2020): 223–34. http://dx.doi.org/10.2298/ntrp2003223a.

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The possibility of substituting the usage of a radioactive ?-source to improve the characteristics of the gas surge arrester is considered in this paper. The solution to this problem is sought in the engineering of the characteristics by applying different electrode materials and varying electrode surface topography. Materials that differ in the output work value were examined. The electrode surface topographies were either polished, or with engraved regular spikes, or with polished cavities. The paper is mostly experimental in nature. The experiments were performed under well-controlled laboratory conditions. The measurement uncertainty of the experimental procedure was satisfactory. Experimental results were processed by sophisticated statistical methods of low statistical unreliability. The obtained results show that it is possible to avoid the installation of a radioactive source in the gas surge arresters and how it should be done. In this way, a possible contamination of the natural environment with extremely dangerous ??radioactive sources would be avoided.
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Shubin, Igor, Natalya Bakaeva und Alexander Kalaydo. „Protection of Indoor Air from Radioactive Gas Radon“. E3S Web of Conferences 263 (2021): 05023. http://dx.doi.org/10.1051/e3sconf/202126305023.

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A modern human receives most of the radioactive annual dose in buildings from radon and its progeny, which can cause lung cancer. In such conditions, the design of radon-safe buildings is an urgent task in the context of preserving the population collective health. The paper shows the inefficiency of using the radon flux density from the soil surface as a criterion for the potential radon hazard of a construction site due to its significant temporal and spatial variability. The design of an experimental device, which makes it possible to simulate the real conditions of radon transport in soil in laboratory conditions, is described, and the results of determining the dominant radon transport mechanism in soil by means of a laboratory experiment are presented. A method for determining the required radon resistance of the floor structure is proposed on the basis of the diffusion model of stationary transport.
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Barbin, N. M., A. M. Kobelev und D. I. Terent’ev. „Processing of radioactive graphite by gas-generating method“. Journal of Physics: Conference Series 1683 (Dezember 2020): 042025. http://dx.doi.org/10.1088/1742-6596/1683/4/042025.

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27

NOGUCHI, Hiroshi, Mikio MURATA und Katsumi SUZUKI. „Adsorption of radioactive I2 gas onto atmospheric aerosol.“ Japanese Journal of Health Physics 25, Nr. 3 (1990): 209–19. http://dx.doi.org/10.5453/jhps.25.209.

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Rehm, K. E., J. P. Greene, B. Harss, D. Henderson, C. L. Jiang, R. C. Pardo, B. Zabransky und M. Paul. „Gas cell targets for experiments with radioactive beams“. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 647, Nr. 1 (August 2011): 3–9. http://dx.doi.org/10.1016/j.nima.2011.04.011.

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29

Savard, G., S. Baker, C. Davids, A. F. Levand, E. F. Moore, R. C. Pardo, R. Vondrasek, B. J. Zabransky und G. Zinkann. „Radioactive beams from gas catchers: The CARIBU facility“. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 266, Nr. 19-20 (Oktober 2008): 4086–91. http://dx.doi.org/10.1016/j.nimb.2008.05.091.

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30

Wentworth, W. E., T. Limero, C. F. Batten und Edward C. M. Chen. „Non-radioactive electron-capture detector for gas chromatography“. Journal of Chromatography A 468 (Mai 1989): 215–24. http://dx.doi.org/10.1016/s0021-9673(00)96318-0.

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31

Husain, A., und J. P. Krasznai. „Compaction of radioactive incinerator ash: Gas generation effects“. Waste Management 14, Nr. 6 (Januar 1994): 521–30. http://dx.doi.org/10.1016/0956-053x(94)90135-x.

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32

Kosareva, I. M., M. K. Savushkina, B. G. Ershov, Yu A. Revenko, R. R. Khafizov, V. D. Akhunov und S. A. Kabakchi. „Gas release from deeply buried liquid radioactive wastes“. Atomic Energy 100, Nr. 1 (Januar 2006): 47–52. http://dx.doi.org/10.1007/s10512-006-0048-x.

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33

Adeishvili, Teimuraz. „THE EFFECT OF RADON AND GEOMAGNETIC FIELD ON BIO-SYSTEMS“. Journal Scientific and Applied Research 8, Nr. 1 (12.10.2015): 5–9. http://dx.doi.org/10.46687/jsar.v8i1.171.

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34

OSADA, Naoyuki, Yuichi OKI, Keizou YAMASAKI und Seiichi SHIBATA. „Influence of Radioactive Gas on Particle Size Measurement of Radioactive Aerosol with Diffusion Battery Method“. Progress in Nuclear Science and Technology 1 (25.02.2011): 483–86. http://dx.doi.org/10.15669/pnst.1.483.

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35

Journal, Baghdad Science. „Find the concentration of radon gas emitted naturally from the bones and skin of some kinds of birds and local and imported chicken available in the City of Baghdad“. Baghdad Science Journal 12, Nr. 4 (06.12.2015): 691–95. http://dx.doi.org/10.21123/bsj.12.4.691-695.

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In the present research we the study the deposition of radioactive elements naturally and particularly radioactive radon gas in parts of the body of organisms which are of direct relevance to human life in the city of Baghdad as the samples which were collected from the bones and skin of some kinds of birds and chicken based on the principle that radioactive elements are concentrated always on the bones. We use of this as the exercise detector impact nuclear (CR-39), using the technology Cylindrical diffusion , the results indicated that the largest concentration of radon found in the bone bird Seagull tapered as it was (625 ± 37) Bq.cm-3, and less concentration of radon gas in the chicken bones of Al-kafeel as it was (105 ± 10) Bq.cm-3 as well as in chicken bones of Al-muriad to be reached (110±10)Bq.cm-3 either in the skin reached the highest concentration in the skin of seagulls tapered(610 ± 20) Bq.cm-3 and the lowest value in the skin local chicken as it was (90 ± 9) Bq.cm-3 .
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Mryoush, Atheer Qassim. „Find the concentration of radon gas emitted naturally from the bones and skin of some kinds of birds and local and imported chicken available in the City of Baghdad“. Baghdad Science Journal 12, Nr. 4 (06.12.2015): 691–95. http://dx.doi.org/10.21123/bsj.2015.12.4.691-695.

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In the present research we the study the deposition of radioactive elements naturally and particularly radioactive radon gas in parts of the body of organisms which are of direct relevance to human life in the city of Baghdad as the samples which were collected from the bones and skin of some kinds of birds and chicken based on the principle that radioactive elements are concentrated always on the bones. We use of this as the exercise detector impact nuclear (CR-39), using the technology Cylindrical diffusion , the results indicated that the largest concentration of radon found in the bone bird Seagull tapered as it was (625 ± 37) Bq.cm-3, and less concentration of radon gas in the chicken bones of Al-kafeel as it was (105 ± 10) Bq.cm-3 as well as in chicken bones of Al-muriad to be reached (110±10)Bq.cm-3 either in the skin reached the highest concentration in the skin of seagulls tapered(610 ± 20) Bq.cm-3 and the lowest value in the skin local chicken as it was (90 ± 9) Bq.cm-3 .
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37

Harrington, J. F., C. C. Graham, R. J. Cuss und S. Norris. „Gas Network Development in Compact Bentonite: Key Controls on the Stability of Flow Pathways“. Geofluids 2019 (20.05.2019): 1–19. http://dx.doi.org/10.1155/2019/3815095.

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Compacted bentonite is proposed as an engineered barrier material within facilities for the geological disposal of radioactive waste. Barrier performance and its interaction with a free gas phase must be considered as part of sound repository design. This study involved the long-term experimental examination of gas flow in precompacted bentonite, with particular consideration of gas network stability. Results demonstrate that the stress field experienced by the clay is strongly coupled with gas flow. For the first time, three controls on this behaviour are considered: (i) injection flow rate, (ii) constant vs. variable gas pressure, and (iii) stimulation of the microfracture network. A detailed stress analysis is used to examine changes in the gas flow network. The results indicate a degree of metastability despite these changes, except in the case of stimulation of the microfracture network by removal of the primary drainage route. In this case, a rapid redevelopment of the gas flow network was observed. As such, availability of drainage pathways will represent a key control on the generation of peak gas pressures and distribution of gas within the engineered barrier. The cessation of gas flow is shown to result in crack closure and self-sealing. Observations from this study highlight that characterisation of the gas network distribution is of fundamental importance in predicting gas dissipation rates and understanding the long-term fate of gas in radioactive waste repositories.
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Williams, S. J. „An overview of gas research in support of the UK geological disposal programme“. Mineralogical Magazine 76, Nr. 8 (Dezember 2012): 3271–78. http://dx.doi.org/10.1180/minmag.2012.076.8.40.

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AbstractGases will be generated in waste packages during their transport to a geological disposal facility (GDF), this generation will continue during GDF operations and after GDF closure. The range of gases produced will include flammable, radioactive and chemotoxic species. These must be managed to ensure safety during transport and operations, and the post-closure consequences need to be understood. The two primary post-closure gas issues for a GDF are the need for the system pressure to remain below a value at which irreversible damage to the engineered barrier system and host geology could occur, and the need to ensure that any flux of gas (in particular gaseous radionuclides) to the biosphere does not result in unacceptable risk. This paper provides an overview of the research of the Nuclear Decommissioning Authority, Radioactive Waste Management Directorate into gas generation and its migration from a GDF.
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Bunert, Erik, Ansgar T. Kirk, Jens Oermann und Stefan Zimmermann. „Electron capture detector based on a non-radioactive electron source: operating parameters vs. analytical performance“. Journal of Sensors and Sensor Systems 6, Nr. 2 (14.12.2017): 381–87. http://dx.doi.org/10.5194/jsss-6-381-2017.

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Abstract. Gas chromatographs with electron capture detectors are widely used for the analysis of electron affine substances such as pesticides or chlorofluorocarbons. With detection limits in the low pptv range, electron capture detectors are the most sensitive detectors available for such compounds. Based on their operating principle, they require free electrons at atmospheric pressure, which are usually generated by a β− decay. However, the use of radioactive materials leads to regulatory restrictions regarding purchase, operation, and disposal. Here, we present a novel electron capture detector based on a non-radioactive electron source that shows similar detection limits compared to radioactive detectors but that is not subject to these limitations and offers further advantages such as adjustable electron densities and energies. In this work we show first experimental results using 1,1,2-trichloroethane and sevoflurane, and investigate the effect of several operating parameters on the analytical performance of this new non-radioactive electron capture detector (ECD).
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40

Murashova, Ekaterina, Yuriy Kulishov, Anton Tarasenko und Alena Anufrieva. „Instrumentation and Methodological Support of Radioactive Release Monitoring from the Mayak PA Nuclear Fuel Cycle Facilities“. ANRI, Nr. 1 (01.05.2022): 56–68. http://dx.doi.org/10.37414/2075-1338-2022-108-1-56-68.

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Data on instrumentation and methodological support of radioactive release monitoring are summarized. Flow charts of continuous and periodical (analytical) gas release monitoring are described. Methods used at the Mayak PA for monitoring of the air medium activity in process ducts, room active ventilation systems and gas release sources are summarized.
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Shun'ya, Yoshimi, und Shi-Lin Loh. „Radioactive Rain and the American Umbrella“. Journal of Asian Studies 71, Nr. 2 (Mai 2012): 319–31. http://dx.doi.org/10.1017/s0021911812000046.

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With the earthquake of March 11, 2011, and the expanding nuclear disaster that followed, our “affluent postwar” has finally reached a decisive end. Indeed, this closure had been clearly augured since the 1990s. The collapse of the bubble economy, the close of an era of single-party rule by the Liberal Democratic Party, and the Great Hanshin-Awaji Earthquake and Aum Shinrikyō sarin gas attacks that came in rapid succession in 1995—these events forced upon us the reality that the “affluent postwar” was over.
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42

Charles, Chris R. J., Friedhelm Ames, Oliver Kester, S. Malbrunot-Ettenauer, Carla Babcock, Brad E. Schultz, Cameron Peters et al. „Production of Radioactive Molecular Ions in Radiofrequency Quadrupole Gas-Reaction Cells“. Journal of Physics: Conference Series 2244, Nr. 1 (01.04.2022): 012100. http://dx.doi.org/10.1088/1742-6596/2244/1/012100.

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Abstract Limited types of radioactive molecules (RM) can be made inside hot-cavity targets at ISOL facilities like TRIUMF. However, extreme conditions in these targets present formidable unsolved challenges to efficient production and delivery of RM’s. Here we propose using RFQ gas-reaction cells to produce RM from radioactive ion beams (RIB) by room temperature RIB-gas chemical reactions at eV energies. Two options are possible: (1) using an ion reaction cell (IRC) that is a linear RFQ ion guide and reaction cell used as an ‘on-line ion source’, and (2) using the ARIEL RFQ cooler-buncher (ARQB). RFQ gas-cells are a controllable and efficient method to produce RM from chemical reactants that cannot be used in ISOL targets. This ‘online chemistry’ offers a way to enable groundbreaking Beyond Standard Model (BSM) physics research, using a wide diversity of new rare and exotic RM beams that would be difficult or impossible to produce in hot-cavity targets.
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43

Elsesmita, Sabrina Ermayanti und Dewi Wahyu Fitrina. „Effect of Radon and Lung Cancer Risk: A Narrative Literature Review“. Bioscientia Medicina : Journal of Biomedicine and Translational Research 6, Nr. 15 (03.11.2022): 2691–98. http://dx.doi.org/10.37275/bsm.v6i15.669.

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Exposure to cigarette smoke has been known to be a major risk factor for lung cancer. Although smoking has long been considered the main cause of lung cancer, about 5 to 25% of lung cancer cases occur in non-smokers. Radon is said to be the second most important cause of lung cancer after smoking. Radon-222 is a chemical element in the form of a highly radioactive gas that comes from the decay of the parent radioactive element, uranium, which is found in the earth's crust. Inhaled radon gas can adhere to the mucosal lining of the airways and damage the airway epithelium. The process of ionizing radiation by alpha particles due to the decay of radioactive substances can cause mutations and chromosomal aberrations, severance of DNA double chains, and formation of reactive oxygen species. (ROS) that cause cell cycle changes, up-and down-regulation of cytokines, and increased production of proteins associated with cell cycle regulation and carcinogenesis. Research on radon and lung cancer has not been widely conducted in Indonesia. This literature review aims to describe radon and its effects on lung health.
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44

Barbin, N. M., A. M. Kobelev, D. I. Terent’ev, S. G. Alexeev und S. A. Titov. „Thermodynamic simulation of radioactive graphite combustion in water vapor“. Journal of Physics: Conference Series 2233, Nr. 1 (01.04.2022): 012002. http://dx.doi.org/10.1088/1742-6596/2233/1/012002.

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Abstract The paper analyzes the gas phase, the behavior uranium, the calculation of thermophysical properties during heating of nuclear reactor graphite containing various actinides. The study was carried out by thermodynamic modeling using the TERRA software package in the range from 423 to 2123 K at a constant pressure of 0.1 MPa. Up to a temperature of 623 K, the main components of the gas phase are water vapor, carbon dioxide, methane and hydrogen. Above 1023 K, the gas phase contains predominantly carbon dioxide and monoxide. It was revealed that in the range of 423-923 K uranium is present in the form of condensed compounds - uranium dioxide and uranyl chloride. Up to a temperature of 1623 K, uranium is present in the form of condensed uranium dioxide and calcium uranate. At temperatures above 2023 K, condensed uranium compounds are converted into gaseous and ionized compounds of uranium trioxide and dioxide. The thermophysical characteristics change unevenly up to a temperature of 923 K.
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45

Barbin, N. M., A. M. Kobelev, D. I. Terent’ev, S. G. Alexeev und S. A. Titov. „Thermodynamic simulation of radioactive graphite combustion in water vapor“. Journal of Physics: Conference Series 2233, Nr. 1 (01.04.2022): 012002. http://dx.doi.org/10.1088/1742-6596/2233/1/012002.

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Abstract The paper analyzes the gas phase, the behavior uranium, the calculation of thermophysical properties during heating of nuclear reactor graphite containing various actinides. The study was carried out by thermodynamic modeling using the TERRA software package in the range from 423 to 2123 K at a constant pressure of 0.1 MPa. Up to a temperature of 623 K, the main components of the gas phase are water vapor, carbon dioxide, methane and hydrogen. Above 1023 K, the gas phase contains predominantly carbon dioxide and monoxide. It was revealed that in the range of 423-923 K uranium is present in the form of condensed compounds - uranium dioxide and uranyl chloride. Up to a temperature of 1623 K, uranium is present in the form of condensed uranium dioxide and calcium uranate. At temperatures above 2023 K, condensed uranium compounds are converted into gaseous and ionized compounds of uranium trioxide and dioxide. The thermophysical characteristics change unevenly up to a temperature of 923 K.
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McLaughlin, Molly C., Bonnie McDevitt, Hannah Miller, Kaela K. Amundson, Michael J. Wilkins, Nathaniel R. Warner, Jens Blotevogel und Thomas Borch. „Constructed wetlands for polishing oil and gas produced water releases“. Environmental Science: Processes & Impacts 23, Nr. 12 (2021): 1961–76. http://dx.doi.org/10.1039/d1em00311a.

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Produced water (PW) is the largest waste stream associated with oil and gas (O&G) operations and contains petroleum hydrocarbons, heavy metals, salts, naturally occurring radioactive materials and any remaining chemical additives.
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47

Xu, George Sikun, und Nicholas Chan. „Management of radioactive waste from application of radioactive materials and small reactors in non-nuclear industries in Canada and the implications for their new application in the future“. AIMS Environmental Science 8, Nr. 6 (2021): 619–40. http://dx.doi.org/10.3934/environsci.2021039.

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<abstract> <p>A large number of artificial-origin radionuclides from irradiation in small reactors and/or nuclear reactions in accelerators are currently used in non-nuclear industries such as education, oil and gas, consumer merchandise, research, and medicine. Radioactive wastes from the use of these radionuclides in non-nuclear industries include expired sealed radioactive sources, biological materials, radionuclide-containing chemicals, contaminated equipment, and very small quantities of used nuclear fuel. Although being less challenging and complex than nuclear energy production and research waste streams, these wastes are subject to the common nuclear regulations by the Canadian Nuclear Safety Commission, and are managed following domestic and international standards and guidelines made by the Canadian Standards Association, International Atomic Energy Agency, and International Organization for Standardization. Management practices used in the nuclear industry in Canada are commonly applied to the non-nuclear industry radioactive waste streams, such as waste handling, treatment, packaging, storage, transportation, clearance and exemptions, and disposal. The half-lives of radionuclides in non‑nuclear applications range from hours to thousands of years, and their activities in non-nuclear industrial applications can be as low as their clearance level or as high as the upper limits for intermediate level radioactive waste. Waste containing only short half-life radionuclides is placed in temporary storage to allow decay, and then is cleared and disposed of through non-radioactive waste routes. Non‑clearable waste materials are treated, consolidated, and managed along with radioactive waste generated from the nuclear industries at designated radioactive waste management sites.</p> </abstract>
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Pham, Tung Cao Thanh, Son Docao, In Chul Hwang, Mee Kyung Song, Do Young Choi, Dohyun Moon, Peter Oleynikov und Kyung Byung Yoon. „Capture of iodine and organic iodides using silica zeolites and the semiconductor behaviour of iodine in a silica zeolite“. Energy & Environmental Science 9, Nr. 3 (2016): 1050–62. http://dx.doi.org/10.1039/c5ee02843d.

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During the reprocessing of spent nuclear fuel rods, a highly moist off-gas mixture containing various volatile radioactive species, such as iodine (I2), organic iodides and nitric acid, is produced.
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49

Wojcik, M., G. Zuzel und H. Simgen. „Review of high-sensitivity Radon studies“. International Journal of Modern Physics A 32, Nr. 30 (30.10.2017): 1743004. http://dx.doi.org/10.1142/s0217751x17430047.

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A challenge in many present cutting-edge particle physics experiments is the stringent requirements in terms of radioactive background. In peculiar, the prevention of Radon, a radioactive noble gas, which occurs from ambient air and it is also released by emanation from the omnipresent progenitor Radium. In this paper we review various high-sensitivity Radon detection techniques and approaches, applied in the experiments looking for rare nuclear processes happening at low energies. They allow to identify, quantitatively measure and finally suppress the numerous sources of Radon in the detectors’ components and plants.
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50

Huda, Khoirul. „Analisis Kebutuhan Sistem Deteksi Radiasi terhadap Bahan Radioaktif di Luar Kendali Pengawasan“. Jurnal Pengawasan Tenaga Nuklir 2, Nr. 1 (29.07.2022): 18–23. http://dx.doi.org/10.53862/jupeten.v2i1.004.

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The Need Analysis of Radiation Detection System for Radioactive Materials Out of Regulatory Control. Radioactive materials out of regulatory control (MORC) can threaten human life because they can misuse these materials for terrorism or other illegal acts. Therefore, must prevention of acts of terrorism using radioactive materials by preventing the emergence of MORC itself through nuclear security means, including installing radiation detection systems at borders and entrances to the country's territory. Therefore, it is necessary to know the installation points, and the number of detection devices installed to install the detection system. However, until now, there has been no analysis of the need to install the system in Indonesia. In this study, a qualitative analysis has been carried out using secondary data on the need for a radioactive material detection system in border areas and entrances to the country. The analysis results show the high demand for installation of the detection system and the vast gap between the number of detection devices currently available and those needed. Keywords: MORC, nuclear security of MORC, radiation detection system, RPM.
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