Hybrid journal (It can contain Open Access articles) ISSN (Print) 1742-4186 - ISSN (Online) 1742-4194 Published by Inderscience Publishers[439 journals]
Please help us test our new pre-print finding feature by giving the pre-print link a rating. A 5 star rating indicates the linked pre-print has the exact same content as the published article.
Authors:Alexandr Prokopevich Elokhin, Alexandr Ivanovich Ksenofontov, Оrumo Beinmotei Kеnoll Pages: 1 - 23 Abstract: The work provides a comparative analysis of the material and financial costs for the development and operation of an Automated Radiation Monitoring System (ARMS) for monitoring of the environmental radiation situation and the damage associated with the elimination of the consequences of a radiation accident at an Atomic Energy Facility. Furthermore, we consider a brief scenario of the sequence of operations of the ARMS system related to the assessment of radioactive pollution of the environment, in the framework of a hypothetical accident of level 7, on the INES scale, and that of the Atomic Energy Facility. The work presents the main methods and means of the ARMS system. The system helps to carry out modern methods of assessing dose loads on the personnel and the population of the region exposed to a radioactive release torch. It also helps in the elimination of the effects of radioactive pollution of the environment and its damage to the population, agricultural land, parks and reserves. The maintenance work and the evacuation of the population from the contaminated area is considered. It shows that the material and financial costs of nuclear power plant equipment, which allows for radiation monitoring, maintenance, as well as work-related to prognostic assessments of radioactive pollution of the environment, are much less than the costs of eliminating the consequences of severe radiation accidents at nuclear power plants. Keywords: radiation accident; ionising radiation; radioactive contamination of the air basin; the underlying surface; dose loads; environmental damage Citation: International Journal of Nuclear Governance, Economy and Ecology, Vol. 5, No. 1 (2021) pp. 1 - 23 PubDate: 2021-07-16T23:20:50-05:00 DOI: 10.1504/IJNGEE.2021.116284 Issue No:Vol. 5, No. 1 (2021)
Please help us test our new pre-print finding feature by giving the pre-print link a rating. A 5 star rating indicates the linked pre-print has the exact same content as the published article.
Authors:Alexandr Prokopevich Elokhin, Alexandr Ivanovich Ksenofontov, Оrumo Beinmotei Kеnoll Pages: 24 - 36 Abstract: Advantages and benefits of Small Modular Reactors (SMRs) in terms of modularity, economy, augmented/inherent nuclear safety and security features and mitigating climate change effects have been assessed from the perspective of a developing country willing to invest in SMR. Further, how these 'advantages/benefits' impact nuclear safeguards, an important pillar of non-proliferation regime has also been studied. An attempt has been made in this paper to reassess the potential of SMRs from different perspectives and identify challenges, if any in deploying these reactors particularly in developing countries. The parameters considered for assessment are the 'benefits/advantages', safety and security attributes as well as siting of these reactors in countries with established nuclear infrastructure and in developing countries. In addition, feasibility of safeguards implementation is also considered. As the SMRs are still in the design stage, the reassessment may contribute to taking a fresh relook into all aspects of SMRs. Keywords: small modular reactors; modularisation; safety; security; safeguards; developing countries; NWS; NNWS; regulatory requirements; SMR; IPWR; MSR; IAEA Citation: International Journal of Nuclear Governance, Economy and Ecology, Vol. 5, No. 1 (2021) pp. 24 - 36 PubDate: 2021-07-16T23:20:50-05:00 DOI: 10.1504/IJNGEE.2021.116290 Issue No:Vol. 5, No. 1 (2021)
Please help us test our new pre-print finding feature by giving the pre-print link a rating. A 5 star rating indicates the linked pre-print has the exact same content as the published article.
Authors:A.I. Al-Shamayleh, D.A. Solovyov, A.A. Semyonov, N.V. Shchukin, B. Djaroum, H.A. Tanash Pages: 37 - 45 Abstract: Start-up to minimum controllable power level (criticality approach) is one of the most hazardous nuclear operations during operation. In particular, the spontaneous and unauthorised start-up is very dangerous, and it occurs as a result of some technological operations or changes in technological regimes. Currently, there are codes for neutron-physical calculations at NPPs with VVER, such as reactor simulator (IR) and BIPR-7A. These codes calculate the boric acid critical concentration without relying on ex-core ionisation detectors data, which may result in inaccuracies in determining the critical concentration. In addition, feeding the primary circuit with clean condensate must be stopped at least 15 minutes before is reached, and these codes do not calculate the time to reach the critical state. As a result, the idea arose to develop a code that would predict the time to reach the critical state and the critical concentration of boric acid only using the measuring equipment readings without reliance on additional calculations. Keywords: VVER-1000; water-water energetic reactor; MCL; minimum controllable power level; reactor simulator Citation: International Journal of Nuclear Governance, Economy and Ecology, Vol. 5, No. 1 (2021) pp. 37 - 45 PubDate: 2021-07-16T23:20:50-05:00 DOI: 10.1504/IJNGEE.2021.116293 Issue No:Vol. 5, No. 1 (2021)
Please help us test our new pre-print finding feature by giving the pre-print link a rating. A 5 star rating indicates the linked pre-print has the exact same content as the published article.
Authors:A.A. Batsulin, V.V. Bochkarev, B.D. Brilliantov, S.G. Klimanov, O. Yu Litvinenko, D.V. Mamai, D.E. Sliva, D.S. Smirnov, S.A. Smirnov, P.A. Stryapushkin, V.I. Tereshkin, D.T. Khanbikova Pages: 46 - 56 Abstract: The paper presents the structure of the optimal Decision Support System (DSS) for planning, preparing and implementation of nuclear facilities decommissioning. The proposed structure is intended to implement the following DSS functions: modelling of nuclear facilities and decommissioning activities carried out according to various possible decommissioning options; quantitative assessment of a specific set of partial indicators that characterise the possible decommissioning strategies; identifying the preferences of the decision-maker and redacting them to a formalised form (the quantitative restrictions on the values of partial indicators, the weighting functions of significance for partial indicators); identification of the values of the complex indicator which is a measure for optimality of the considered possible decommissioning strategies. Possible decommissioning strategies are described using a set of the following partial indicators: potential radiation hazards, decommissioning costs, duration of the decommissioning stage. The DSS is designed to be used for decommissioning of nuclear facilities in the Russian Federation. However, it can be used for decommissioning of nuclear facilities in other countries after appropriate modifications. Keywords: DSS; optimal decision support system; decommissioning; nuclear facility; multi-criteria approach; partial indicators; complex indicator; radioactive waste; nuclear and radiation safety Citation: International Journal of Nuclear Governance, Economy and Ecology, Vol. 5, No. 1 (2021) pp. 46 - 56 PubDate: 2021-07-16T23:20:50-05:00 DOI: 10.1504/IJNGEE.2021.116295 Issue No:Vol. 5, No. 1 (2021)
Please help us test our new pre-print finding feature by giving the pre-print link a rating. A 5 star rating indicates the linked pre-print has the exact same content as the published article.
Authors:S.A. Karpov, V.N. Brendakov, K.A. Ivanov, A.A. Zhuravlev Pages: 57 - 64 Abstract: The paper presents an analysis of operating parameters and optimisation of the counter-current pulsation extraction process in a liquid-liquid system. A set of factors is considered that have a significant impact on both the individual stages of the extraction process and the structure of the process as a whole. Regression dependences are obtained for the operating parameters of the extraction process in the form of functions of the input control factors. The paper solves the problem of finding the optimal values of the input parameters that provide the maximum possible efficiency under these conditions for the key component of the extraction process in the liquid-liquid system with additional external energy supply. Keywords: extraction process; dispersed and continuous phases; turbulent flow regime; external energy supply; optimal operating mode of the device Citation: International Journal of Nuclear Governance, Economy and Ecology, Vol. 5, No. 1 (2021) pp. 57 - 64 PubDate: 2021-07-16T23:20:50-05:00 DOI: 10.1504/IJNGEE.2021.116297 Issue No:Vol. 5, No. 1 (2021)
Please help us test our new pre-print finding feature by giving the pre-print link a rating. A 5 star rating indicates the linked pre-print has the exact same content as the published article.
Authors:V.N. Petrovskij, V.I. Polskij Pages: 65 - 74 Abstract: One of the tools for ensuring nuclear safety during the transportation of spent nuclear fuel is the creation of a high-strength transport container that effectively absorbs radioactive radiation from fission products. This raises the problem of creating appropriate structural materials. In this regard, it seems very promising to use a metal absorbing coating on high-strength corrosion-resistant steel, which is well mastered by the industry. However, ensuring the effectiveness of such a coating is possible only at a high concentration of neutron-absorbing elements in the cladding layer. One way to reduce the induced radioactivity of packaging sets is to use low-activated ferritic-martensitic steels such as EP450 (12Kh13M2BFR), EP823 (16Kh12SMVFBR) and 16Kh12V2FTaR. These steels have shown a high level of serviceability as structural materials for fuel element cladding and RBN fuel assemblies (BN-600, BN-350, BOR-60, etc.). Currently, a promising direction is the laser coating on the surface of transport packaging complexes. This paper explores the method of protection transport packaging sets against neutron radiation by laser surfacing of metallic powder. Keywords: transportation of spent nuclear fuel; nuclear safety; high-strength transport container; metal absorbing coating; laser surfacing Citation: International Journal of Nuclear Governance, Economy and Ecology, Vol. 5, No. 1 (2021) pp. 65 - 74 PubDate: 2021-07-16T23:20:50-05:00 DOI: 10.1504/IJNGEE.2021.116301 Issue No:Vol. 5, No. 1 (2021)
Hybrid journal (It can contain Open Access articles)
[439 journals]
