scholarly journals Operating conditions of container cars in railway trains of special formation

2021 ◽  
Vol 80 (6) ◽  
pp. 319-326
Author(s):  
A. M. Brzhezovskiy ◽  
N. M. Voluyskiy
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Operating Conditions ◽  
Rolling Stock ◽  
Test Results ◽  
Regulatory Documents ◽  
Test Loop ◽  
State Corporation ◽  
Experimental Works ◽  
The Russian Federation

Abstract. The article considers main technical characteristics, indicators of dynamic qualities and parameters of braking effciency of special railway rolling stock of container cars (container transporters) intended for the transportation of radioactive materials — spent nuclear fuel. In accordance with the current regulatory documents of JSC Russian Railways, it is currently allowed forming special trains exclusively from container transporters of any one type, which is associated with the peculiarities of the technology for handling and transporting spent nuclear fuel, which is within the competence of the state corporation Rosatom. However, this signifcantly increases the timing of the delivery of special trains due to the need to wait for the readiness of transporters, due to the non-simultaneous delivery of any one type of assembly kits with spent nuclear fuel. The practice of handling has shown that the transportation of some types of spent nuclear fuel can be carried out with a combination of the transport operation, which implies the combination of various types of container transporters in one echelon, but at the same time it is necessary to correct certain regulatory documents of Russian Railways. For this purpose, at the request of the Rosatom corporation, a necessary set of experimental works was carried out. Authors presented results of control running dynamic, stationary and running braking tests of container transporters of various types, following as part of the same echelon, on the infrastructure of the Test Loop of JSC “VNIIZHT”, including when running along the frst ring track and along various combinations of turnouts along a tangent line (main) and lateral directions. It has been experimentally proved that it is possible to operate container transporters of various types as part of the same echelon in compliance with the conditions for ensuring traffc safety in accordance with the standards of dynamic qualities and braking effciency. Based on the test results, a regulatory document of JSC Russian Railways was developed — the Regulation on the conditions for joint operation of special freight cars (transporters) as part of one echelon, approved by the order of JSC Russian Railways dated July 22, 2021 No. 1591/r. components. Interstate standard, put into effect as nat. standard of the Russian Federation by order of the Federal Agency for Technical Regulation and Metrology dated March 17, 2016 No. 162-st. Moscow, Standartinform Publ., 2016, 54 p. (in Russ.).

Research Reactor Spent Nuclear Fuel Shipment From the Czech Republic to the Russian Federation

2009 ◽  
Author(s):  
Frantisek Svitak ◽  
Karel Svoboda ◽  
Josef Podlaha
Keyword(s):  
United States ◽  
Czech Republic ◽  
Nuclear Fuel ◽  
Russian Federation ◽  
Research Reactor ◽  
Spent Nuclear Fuel ◽  
Nuclear Materials ◽  
The Czech Republic ◽  
The Russian Federation ◽  
Global Threat

In May 2004, the Global Threat Reduction Initiative agreement was signed by the governments of the United States and the Russian Federation. The goal of this initiative is to minimize, in cooperation with the International Atomic Energy Agency (IAEA) in Vienna, the existing threat of misuse of nuclear and radioactive materials for terrorist purposes, particularly highly enriched uranium (HEU), fresh and spent nuclear fuel (SNF), and plutonium, which have been stored in a number of countries. Within the framework of the initiative, HEU materials and SNF from research reactors of Russian origin will be transported back to the Russian Federation for reprocessing/liquidation. The program is designated as the Russian Research Reactor Fuel Return (RRRFR) Program and is similar to the U.S. Foreign Research Reactor Spent Nuclear Fuel Acceptance Program, which is underway for nuclear materials of United States origin. These RRRFR activities are carried out under the responsibilities of the respective ministries (i.e., U.S. Department of Energy (DOE) and Russian Federation Rosatom). The Czech Republic and the Nuclear Research Institute Rez, plc (NRI) joined Global Threat Reduction Initiative in 2004. During NRI’s more than 50 years of existence, radioactive and nuclear materials had accumulated and had been safely stored on its grounds. In 1995, the Czech regulatory body, State Office for Nuclear Safety (SONS), instructed NRI that all ecological burdens from its past activities must be addressed and that the SNF from the research reactor LVR-15 had to be transported for reprocessing. At the end of November 2007, all these activities culminated with the unique shipment to the Russian Federation of 527 fuel assemblies of SNF type EK-10 (enrichment 10% U235) and IRT-M (enrichment 36% and 80% U235) and 657 irradiated fuel rods of EK-10 fuel, which were used in LVR-15 reactor.

scholarly journals Approaches to Safety Justification for Loading of VSC-VVER Containers in ZNPP DSFSF

2019 ◽  
pp. 82-87
Author(s):  
Ya. Kostiushko ◽  
O. Dudka ◽  
Yu. Kovbasenko ◽  
A. Shepitchak
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Power Plants ◽  
Spent Nuclear Fuel ◽  
Operating Conditions ◽  
Spent Fuel ◽  
Fuel Assemblies ◽  
Fuel Storage ◽  
The Government

The introduction of new fuel for nuclear power plants in Ukraine is related to obtaining a relevant license from the regulatory authority for nuclear and radiation safety of Ukraine. The same approach is used for spent nuclear fuel (SNF) management system. The dry spent fuel storage facility (DSFSF) is the first nuclear facility created for intermediate dry storage of SNF in Ukraine. According to the design based on dry ventilated container storage technology by Sierra Nuclear Corporation and Duke Engineering and Services, ventilated storage containers (VSC-VVER) filled with SNF of VVER-1000 are used, which are located on a special open concrete site. Containers VSC-VVER are modernized VSC-24 containers customized for hexagonal VVER-1000 spent fuel assemblies. The storage safety assessment methodology was created and improved directly during the licensing process. In addition, in accordance with the Energy Strategy of Ukraine up to 2035, one of the key task is the further diversification of nuclear fuel suppliers. Within the framework of the Executive Agreement between the Government of Ukraine and the U.S. Government, activities have been underway since 2000 on the introduction of Westinghouse fuel. The purpose of this project is to develop, supply and qualify alternative nuclear fuel compatible with fuel produced in Russia for Ukrainian NPPs. In addition, a supplementary approach to safety analysis report is being developed to justify feasibility of loading new fuel into the DSFSF containers. The stated results should demonstrate the fulfillment of design criteria under normal operating conditions, abnormal conditions and design-basis accidents of DSFSF components.  Thus, the paper highlights both the main problems of DSFSF licensing and obtaining permission for placing new fuel types in DSFSF.

Support of the Nuclear Research Institute Rˇezˇ plc of the Shipment of Spent Nuclear Fuel From Research Reactors to the Russian Federation for Reprocessing in the Frame of the RRRFR Program

2010 ◽  
Author(s):  
Josef Podlaha ◽  
Karel Svoboda
Keyword(s):  
Nuclear Fuel ◽  
Russian Federation ◽  
Research Reactor ◽  
Spent Nuclear Fuel ◽  
Nuclear Research ◽  
Reactor Operation ◽  
Nuclear Research Institute ◽  
The Russian Federation ◽  
First Time ◽  
Research Institute

In 2007, spent nuclear fuel (SNF) from the Nuclear Research Institute Rˇezˇ plc (NRI) was shipped to the Russian Federation for reprocessing. A large amount of SNF of Russian origin has been accumulated after 50 years of research reactor operation. The shipment was realized in the frame of the Russian Research Reactor Fuel Return (RRRFR) program under the US-Russian Global Threat Reduction Initiative (GTRI). SNF shipment from NRI to the Russian Federation represented a very complex and complicated technical, legal and contractual scope of work. The SNF shipment has been realized under specific conditions: 1. High capacity SˇKODA VPVR/M casks were used for transportation for the first time. 2. For the first time, high enriched uranium SNF from a research reactor has been sent to the Russian Federation from a European Union country under the appropriate intergovernmental agreements, legal regulations and conditions. NRI also participates in shipments of SNF from other countries within the framework of the RRRFR program. NRI participated in shipments of SNF from Bulgaria and Hungary in 2008, from Poland in 2009 and 2010, from Ukraine in 2010. Shipments from Belarus and Serbia are planned in 2010. The second shipment of the residue of high enriched SNF from NRI after changeover of the reactor operation to low enriched fuel will be implemented in 2013. The experiences gained during the SNF transportation are described in the paper together with the present and future NRI activities in support of the SNF shipment from other countries.

scholarly journals Preliminary Assessment of Criticality Safety Constraints for Swiss Spent Nuclear Fuel Loading in Disposal Canisters

Materials ◽  
2019 ◽  
Vol 12 (3) ◽  
pp. 494
Author(s):  
Alexander Vasiliev ◽  
Jose Herrero ◽  
Marco Pecchia ◽  
Dimitri Rochman ◽  
Hakim Ferroukhi ◽  
...  
Keyword(s):  
Fuel Assembly ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Operating Conditions ◽  
Design Parameters ◽  
Fuel Loading ◽  
Pressurized Water ◽  
Fuel Assemblies ◽  
National Cooperative ◽  
Criticality Safety

This paper presents preliminary criticality safety assessments performed by the Paul Scherrer Institute (PSI) in cooperation with the Swiss National Cooperative for the Disposal of Radioactive Waste (Nagra) for spent nuclear fuel disposal canisters loaded with Swiss Pressurized Water Reactor (PWR) UO2 spent fuel assemblies. The burnup credit application is examined with respect to both existing concepts: taking into account actinides only and taking into account actinides plus fission products. The criticality safety calculations are integrated with uncertainty quantifications that are as detailed as possible, accounting for the uncertainties in the nuclear data used, fuel assembly and disposal canister design parameters and operating conditions, as well as the radiation-induced changes in the fuel assembly geometry. Furthermore, the most penalising axial and radial burnup profiles and the most reactive fuel loading configuration for the canisters were taken into account accordingly. The results of the study are presented with the help of loading curves showing what minimum average fuel assembly burnup is required for the given initial fuel enrichment of fresh fuel assemblies to ensure that the effective neutron multiplication factor, keff, of the canister would comply with the imposed criticality safety criterion.

scholarly journals ПЕРСПЕКТИВЫ АТОМНОЙ ЭНЕРГЕТИКИ В ОБЕСПЕЧЕНИИ ЭНЕРГЕТИЧЕСКОЙ И ЭКОЛОГИЧЕСКОЙ БЕЗОПАСНОСТИ РОССИИ

2021 ◽  
Vol 13 (3) ◽  
pp. 41
Author(s):  
Р.М. Яковлев ◽  
И.А. Обухова
Keyword(s):  
Nuclear Fuel ◽  
Energy Production ◽  
Nuclear Power ◽  
Large Scale ◽  
Spent Nuclear Fuel ◽  
Spent Fuel ◽  
Mox Fuel ◽  
State Corporation ◽  
The City ◽  
Nuclear Power Production

Large-scale nuclear energetics can satisfy demands for all kinds of energy, i.e. it can secure energy safety of Russia and the whole humankind; however, this is associated with a number of daunting problems. With that, this approach is a priority for Russia. The State Corporation RosAtom is involved in the development of nuclear reactors in Russia and abroad on the conditions that the reactors will be supplied with nuclear fuel from Russia and the spent fuel will be returned to Russia for conversion into mixed uranium and plutonium oxide (MOX) fuel. In the city Zheleznogorsk near Krasnoyarsk, the first production line of a plant for treating 2000 tons of spent nuclear fuel annually has been already launched. The principal strategic plan of RosAtom, which has been being realized currently, is to develop nuclear power production based on fuel recycling using fast neutron reactors for generation of plutonium, which may be used in nuclear weapons and is most hazardous for the biosphere. The possibility of accidents associated with radioactive discharges cannot be excluded, and the hazardousness of such accidents in increased by using plutonium-based fuels. The nuclear power-based approach to energy production is costly but also dangerous not only for Russia.

scholarly journals Current tasks of radiation health physics

2019 ◽  
Vol 12 (2(св)) ◽  
pp. 109-114
Author(s):  
A. V. Simakov ◽  
V. V. Romanov ◽  
Yu. V. Abramov ◽  
N. L. Proskuryakova
Keyword(s):  
Nuclear Fuel ◽  
Russian Federation ◽  
State Policy ◽  
Spent Nuclear Fuel ◽  
Radiation Safety ◽  
The State ◽  
Contaminated Sites ◽  
Nuclear Workers ◽  
State Radiation ◽  
The Russian Federation

The fundamentals of the state policy in the field of nuclear and radiation safety of the Russian Federation for the period up to 2025 and the further perspective have determined that one of the objectives of the state policy in the field of radiation safety is to maintain the risk of radiation exposure of the nuclear workers as low as possible. To achieve this goal, efforts and resources should be focused on solving a number of tasks, including: protection in accordance with the principle of acceptable risk for nuclear workers; improvement of the state management and state regulation of safety in the field of nuclear energy using; radiation safety assurance during the decommissioning of nuclear legacy facilities, management of spent nuclear fuel, remediation of radioactively contaminated sites of the Russian Federation. Today, federal authorities responsible for monitoring and supervising the health and epidemiological welfare of workers in some industries with especially hazardous working conditions, and research institutions involved in scientific and methodological support of these authorities are faced with the task of solving the following urgent problems in the field of radiation safety: to improve regulatory and methodical support of the state radiation safety regulation; to assure safety and protection of workers and the population during the decommissioning of radiation hazardous facilities and remediation of radioactively contaminated sites; to assure radiation safety during the management of spent nuclear fuel.

scholarly journals Nuclear and Radiation Safety of the Centralized Spent Fuel Storage Facility in Ukraine

2017 ◽  
pp. 3-10
Author(s):  
O. Hryhorash ◽  
O. Dybach ◽  
S. Kondratiev ◽  
O. Horbachenko ◽  
A. Panchenko ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Radiation Safety ◽  
Storage Facility ◽  
Spent Fuel ◽  
Regulatory Documents ◽  
Thermal Regimes ◽  
Fuel Storage ◽  
Nuclear And Radiation Safety ◽  
Biological Protection

The paper presents the analysis of ensuring nuclear and radiation safety in the management of spent nuclear fuel at the Centralized SFSF and activities planned for Centralized SFSF lifecycle stages. There are results of comparing requirements of U.S. regulatory documents used by the HOLTEC Company to design Centralized SFSF equipment staff with relevant requirements of Ukrainian regulations, results based on analysis of the most important factors of Centralized SFSF safety (strength and reliability, nuclear safety, thermal regimes and biological protection) and verified expert calculations of the SSTC NRS. The paper includes issues to be considered in further implementation of Centralized SFSF project.

A Comparative Evaluation of Licensing Requirements for Dry Storage of Spent Nuclear Fuel in the United States, Germany, Canada and the Russian Federation

2004 ◽  
Author(s):  
Edward Wonder ◽  
David S. Duncan ◽  
Eric A. Howden
Keyword(s):  
United States ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
The United States ◽  
Approval Process ◽  
Spent Fuel ◽  
Regulatory Requirements ◽  
Fuel Storage ◽  
The Russian Federation ◽  
The Republic

Technical activities to support licensing of dry spent nuclear fuel storage facilities are complex, with policy and regulatory requirements often being influenced by politics. Moreover, the process is often convoluted, with numerous and diverse stakeholders making the licensing activity a difficult exercise in consensus-reaching. The objective of this evaluation is to present alternatives to assist the Republic of Kazakhstan (RK) in developing a licensing approach for a planned Dry Spent Fuel Storage Facility. Because the RK lacks experience in licensing a facility of this type, there is considerable interest in knowing more about the approval process in other countries so that an effective, non-redundant method of licensing can be established. This evaluation is limited to a comparison of approaches from the United States, Germany, Russia, and Canada. For each country considered, the following areas were addressed: siting; fuel handling and cask loading; dry fuel storage; and transportation of spent fuel. The regulatory requirements for each phase of the process are presented, and a licensing approach that would best serve the RK is recommended.

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