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BN-800 reactor is a new stage in transition to innovative nuclear power
2007-07-01
This paper presents the perspectives of nuclear power development in Russia and the reasons why it is necessary to use for that fast reactor technology. Some features of fast reactor technology and main ideas and technical approaches that have been used in the design of the BN-800 sodium cooled fast reactor are given as well. The BN-800 design is based on the BN-600 design with a series of innovative modifications: -) changing the size and structure of the upper axial blanket in order to get a zero or negative sodium void reactivity effect, -) the addition of scram rods based on passive activation, -) the addition of passive system of emergency cooling with sodium-air heat exchangers, -) a special in-vessel catcher envisaged under the core to catch and retain fragments of the core in case of core disruptive accident, and -) an improved earthquake resistance of all the structures. Such issues as possible options of fuel cycle, closing fuel cycle, transuranium element burning, disposal of plutonium being withdrawn from military programs, etc. are discussed as applied to the BN-800 reactor. Some economic considerations in general outline of the BN-800 unit are presented in the paper. It is important to note that the commissioning of the BN-800 reactor was included into the Federal Goal-Oriented Program - Development of nuclear energy-industrial complex of Russia for 2007-2010 and for perspective up to 2015 -, which was approved by the Russian Government in October 2006.
BN-800 advanced nuclear power plant with fast reactor
Bn-800 reactor plant with fast reactor and sodium coolant in the primary and secondary circuits is designed for operation as part of the power units in the Yuzhno-Uralskaya nuclear power plant scheduled to be constructed in Chelyabinsk region and as part unit 4 in the Beloyarskaya nuclear power plant. Reactor operations are described.
BN-800 advanced nuclear power plant with fast reactor
1993-12-31
Bn-800 reactor plant with fast reactor and sodium coolant in the primary and secondary circuits is designed for operation as part of the power units in the Yuzhno-Uralskaya nuclear power plant scheduled to be constructed in Chelyabinsk region and as part unit 4 in the Beloyarskaya nuclear power plant. Reactor operations are described.
BN-800: Next Generation of Russian Sodium Fast Reactors
The paper gives a brief information on major characteristics of BN-800 reactor plant. It is underlined that BN-800 is relied upon technical solutions earlier implemented in the running BN-600 reactor, which are corroborated by the reactor successful operation since 1980. General safety provision principles are described along with additional design solutions aiming to enhance the reactor safety. The reactor inherent safety features are illustrated by consideration of parameters variation and radiological consequences for some characteristic beyond design basis accidents. Characteristics of the reactor core with MOX-fuel are given and the core potential for utilization of plutonium is shown. The paper describes how the nonproliferation problem can be solved and 'natural safety' principles can be realized through changing to nitride fuel. Information is given on status of activities on the project and expenses for its realization. (authors)
BN-800 as a New Stage in the Development of Fast Sodium-Cooled Reactors
2004-01-01
The role of fast reactors in a strategy for developing nuclear power in Russia because of the inevitable exhaustion of natural uranium deposits in the foreseeable future is discussed. The BN-800 reactor, which is under construction and incorporates unique solutions - greatly enhancing the safety of the reactor - to technical and constructional problems, is examined. Cost assessments taking account of the complete life cycle show that fast reactors could be no more expensive than the most widely reactors in the world - water-moderated water-cooled reactors.Closing the BN-800 nuclear fuel cycle will make it possible to solve the problem of utilizing plutonium and actinides. This makes fast reactors safer for the environment.
Evaluation of sodium void reactivity on the BN-800 fast reactor design
1996-09-01
Analysis of the last studies on sodium void reactivity as applied to the new BN-800 fast reactor core design with sodium plenum is presented. Calculations of the BN-800 fast reactor itself as well as calculational and experimental studies on the assemblies simulating fast reactors with low sodium void reactivity and results of International benchmark calculations for a fast reactor having sodium void reactivity close to zero were analyzed. On the base of the analysis carried out the sodium void reactivity value of the BN-800 fast reactor was made more precise. The first results of the BN-800 fast reactor studies with breeding-free blankets are given as well. (author)
Problems of BN-800 construction and the possibilities of developing advanced fast reactors
2007-01-01
The design features and construction status of the BN-800 reactor being built at the Beloyarskaya nuclear power plant and the main scientific and technical problems which will be solved with the construction of this reactor are examined. The most important ones are mastering a closed fuel cycle, checking new technical solutions, and testing improved fuel and construction materials. The directions for improving the technical-economic performance characteristics of fast reactors that the BN-800 and-1800 designs can provide are described. It is shown that economic performance indicators which are at least as good as those of VVÉR reactor with close power levels can be achieved.
2000-07-01
The conception of Plant was developed for MOX-fuel recycle at two BN-800 type fast reactors by pyrochemical reprocessing of irradiated nuclear fuel (INF) and production of vibro-pac fuel pins and SA. INF production process and stages of pyrochemical reprocessing were analyzed. Starting materials were chosen. Characteristics of irradiated SA and requirements for finished products were defined. Volumes of production were estimated. Procedure of waste management was defined. The following description was made: (1) general flow sheet of fuel recycling and partial schemes of single reprocessing; (2) composition of production process equipment; (3) arrangement of production process equipment; (4) lay out of Plant building and engineering communications. Principle economical assessments were made for production under design. (authors)
Concept of fast neutron plutonium storage reactor. Technical and physical problems
1996-09-01
Fast Neutron Plutonium Storage Reactor (FNPSR) concept is presented. Technological and physical problems of plutonium storage reactor development on the basis of design solutions used in BN-1600M and BN-800 type reactor plants are considered. (author)
Eleven breeder reactors in operation worldwide
Eleven LMFBR power reactors are in operation all over the world, including the largest breeder reactor power station Super Phenix 1 in France. The Indian Fast Breeder Test Reactor is starting up at the present time, and the German-Belgian-Dutch SNR 300 plant has been completed. The Japanese prototype plant Monju, the Italian experimental breeder reactor PEC and the Soviet BN-800 breeder power station are under construction. The report gives a survey of experience with the various breeder reactor and fuel cycle projects and continued R and D work forming the basis of the future breeder development.
New concept of proliferation resistant sodium cooled fast reactor
2001-07-01
The full text follows. It is proposed the concept of BN-800 sodium cooled fast reactor operating in the closed fuel cycle with special reprocessing technology. The use of nitride fuel allows improving the parameters of reactor safety (internal breeding {approx}1, zero value of sodium void reactivity effect), economy (one refueling per year), ecology (use of nitride enriched by nitrogen-15) and non-proliferation (use of reprocessing without separating the plutonium from uranium). The main difficulty of this type reactor development is that the technical project of BN-800 reactor with MOX fuel was developed. When using the nitride fuel it is necessary to serve (in max extent) the mail technical decisions of this project. This report presents first results on development and justification of the BN-800 reactor with nitride fuel core. (authors)
Some engineering problem solutions on fast reactor mounting
To reduce the construction period for a fast reactor NPP, it is suggested in parallel with the construction of the NPP main vessel to conduct enlarged assembly of the reactor vessel in the specially equipped production vessel. The calculations performed show that the assembly of the BN-600 or BN-800 reactor vessel in the special production vessel will be last 25 months. A mean number of main workers for the assembly will amount to 114 persons and the expenditures of labour for enlarged-assembly works will be reduced more than by 20% and will not exceed 65,000 mandays. The cost of the production vessel together with the equipment will constitute 5,81 million roubles. The construction period of energy units will be approximately reduced by two years.
Some engineering problem solutions on fast reactor mounting
1982-04-01
To reduce the construction period for a fast reactor NPP, it is suggested in parallel with the construction of the NPP main vessel to conduct enlarged assembly of the reactor vessel in the specially equipped production vessel. The calculations performed show that the assembly of the BN-600 or BN-800 reactor vessel in the special production vessel will be last 25 months. A mean number of main workers for the assembly will amount to 114 persons and the expenditures of labour for enlarged-assembly works will be reduced more than by 20% and will not exceed 65,000 mandays. The cost of the production vessel together with the equipment will constitute 5,81 million roubles. The construction period of energy units will be approximately reduced by two years.
Safety Analysis of Fast Reactor Core with Uranium-Free Fuel for Actinide Transmutation
The solving of ecological problems of future nuclear power is connected with the solving of long-lived radioactive waste utilization problems. This concerns primarily plutonium and minor actinides (neptunium, americium, and curium), accumulated in the spent fuel of nuclear reactors. One of the ways this can be solved is to use a fast reactor with uranium-free fuel. The physics of this type of reactor was widely investigated during the last year for the BN-800 reactor. The solutions of the most important problems were (a) a decrease in nonuniformity of the power distribution and (b) an increase of the Doppler effect. The next stage of such core investigations is an evaluation of self-protection to beyond-design accidents. Preliminary results show a high safety level of the BN-800 reactor with uranium-free fuel in unprotected loss-of-flow and unprotected transient overpower events.
Development of the scientific and engineering principles of fast power reactors
The state of investigations and developments on scientific and engineering principles of fast power reactors with sodium cooling is surveyed. The problems of determination of nuclear constants and reactor physics, sodium thermal physics, hydrodynamics and technology selection of construction materials and heat exchanging equipment, development of fuel, fuel elements and assemblies, as well as the problems of the fast reactor fuel cycle are discussed. It is noted that operation experience for control systems, loading equipment, main circulating pumps and other units and systems of the BN-600, BN-350 and BOR-60 reactors confirms correctness of the basic design solutions. The conclusion is made that in the closest 10 years investigations on fast reactors will concentrate on the BN-1600 and BN-800 reactors on the basis and with regard to BN-350, BN-600 and BOR-60 operational experience. Further investigations are required for developing nontraditional concepts: a reactor with a heterogeneous core; a reactor with metal fuel and lower temperature for heat generation; a reactor with a two-circuit thermal system.
Status of Phenix operation and of sodium fast reactors in the world
2007-07-01
The French fast breeder reactor (FBR) Phenix restarted in 2003 after 6 years of safety reevaluation procedures. The goal of the experiments performed at Phenix is, first, to demonstrate the technical feasibility of transmutation of minor actinides and long-life products in a fast reactor and secondly, to acquire knowledge on structure materials for future energy systems and on innovative nuclear fuel concepts. After several years of Generation IV discussions, many countries have announced or confirmed their priority for the fast sodium reactor as a reference design. These countries today include Japan, China, Korea, India and Russia (simultaneously with lead reactors). The United States have announced a project for a waste-burning reactor. In France, within the scope of the law of 28 June 2006, the country has announced and confirmed the decision of building a prototype scheduled for operation in 2020. These declarations are all sustained in a very practical manner by ongoing events in this field. Following the excellent results obtained by the BN-600 (600 MWe), Russia has re-launched the BN-800 project. China is currently in the process of building a 75 MWt research reactor, scheduled for divergence in 2009. In Japan, work is underway on MONJU (250 MWe) for divergence in 2008. In India, a 1200 MWt power reactor is under construction, scheduled for divergence in 2010, the first of 3 planned sodium reactors.
Fast reactor application for the fission products burning
1996-09-01
The BN-800 type fast reactor has been considered as an example for studying the possibility of the long living highly radiotoxic fission products burning-out. Application of irradiating devices containing moderator (zirconium hydride), located in the radial blanket allows burning-out of fission products from the BN-800 and VVER-1000 reactors. (author)
2004-01-01
The BN-1800 power-generating unit is designed to meet the requirements of the strategy for developing atomic energy in Russia in the first half of the 21st century. The development time is the next 15 years and construction could start after 2020. The design is innovative and includes the development of key new technical solutions as compared with the BN-800 reactor which is now under construction.The new technical solutions are based on the substantial positive experience in operating fast reactors in Russia (~125 reactoryears), specifically the BN-600 reactor. The innovations make it possible not only to solve strategic problems, such as increasing safety, improving ecology (including by burning actinides), and nonproliferation but also to make large improvements in economic performance.
2005-01-01
The results of design analyses for improving nuclear plants with fast reactors, specifically, by using cartridge-vessel generators instead of sectional-modular generators, are presented. It is shown for a nuclear power plant with a BN-800 reactor that the cartridge-vessel steam generators designed by the Special Machine Design Office substantially decrease the metal content, dimensions, mass, amount of construction work, and construction costs of the main vessel of the nuclear power plant. In the BN-800 design, a cartridge-vessel steam generator decreases the specific capital costs for constructing a power-generating unit of a nuclear power plant by approximately 8%, which substantially closes the gap between these costs for nuclear power plnats with BN-800 and VVER-1000 reactors.
Calculation results are presented for the motion of a melted, heat-releasing mass in a BN-800 reactor. The accident scenario considered involves fuel meltdown under conditions when active or passive mitigation is not possible. The calculation method uses a one-dimensional temperature distribution in the vertical direction, an effective thermal conductivity model involving only heat conduction, and the TRAMS-FDOWN program to numerically solve heat conduction with phase transition. Several case results are summarized for different initial conditions and assumptions. Calculation results indicate that at least five to five and one-half hours are required for the fuel mass to move from the core to the foundation. 5 refs., 4 figs.
Danger of Burning of Sodium Coolant
2004-01-01
The properties of sodium as a substance that can burn are described. The radiation characteristics of sodium as a first-loop coolant in a fast nuclear reactor are presented. An assessment is made of the consequences of sodium burning in various situations. First and foremost, an unanticipated accident with burning of sodium in the first loop adopted in the BN-800 design, is examined. Next, situations with hypothetical scenarios are examined to obtain the limiting data charcterizing the potential fire hazard of radioactive sodium coolant. Specifically, a hypothetical situation where all of the sodium contained in the first loop of the reactor burns is examined. The computational results are analyzed from the standpoint of the role sodium plays in the overall problem of nuclear power plant s...
1994-12-31
Different sources of uncertainties caused by different nuclear cross sections are analyzed for a few types of advanced reactors: the BN-800 FBR core, advanced FBR core with Pb-Bi coolant, modular FBR core with U-Pu and U-Th fuel, HCLWR lattices. Estimations have been made with help of the INDECS System of Codes and Archives. Constructed convariance matrices of uncertainties of the ABB-90 group constants were used for estimation of accuracy of prediction of the most important neutronics characteristics of advanced reactor cores.
1995-03-01
Calculation results are presented for the motion of a melted, heat-releasing mass in a BN-800 reactor. The accident scenario considered involves fuel meltdown under conditions when active or passive mitigation is not possible. The calculation method uses a one-dimensional temperature distribution in the vertical direction, an effective thermal conductivity model involving only heat conduction, and the TRAMS-FDOWN program to numerically solve heat conduction with phase transition. Several case results are summarized for different initial conditions and assumptions. Calculation results indicate that at least five to five and one-half hours are required for the fuel mass to move from the core to the foundation. 5 refs., 4 figs.
Experimental and calculation study of BN-800 mock-up core characteristics at BFS-2 facility
1996-09-01
The experimental and calculation studies of sodium void reactivity effect (SVRE) and other main characteristics on mock-ups of low-void fast reactor core were carried out. The influence of sodium plenum placed above the core was studied. These investigations are aimed at the further substantiation of the BN-800 new designed core with sodium plenum. (author)
1996-12-31
Experience accumulated in Russia allows to determine in different way role and place of fast reactors in modern nuclear power system. Initially, the main objective of fast reactor development was plutonium breeding to provide an alternative to natural uranium. Now the objective of plutonium breeding proved to be much less actual, and is delayed as a more distant prospect. Operation experience of the BN-600 fast reactor at the Beloyarsk NPP in Russia and development of the BN-800 fast reactor design have shown possibility to create facilities, which are not inferior to new generation of the VVER-type thermal reactors in safety and economic characteristics. This paper is based on estimates, which show that specific capital investment for NPP with the BN-800 fast reactors are going to come closer to those of NPP with VVER-type new generation thermal reactors. Estimated power production cost will be discussed for NPP with BN-800 fast reactors in comparison with those of NPP with VVER-type new generation thermal reactors. (authors). 3 refs.
Adjustable electric drives of the main circulation pumps of the BN-600 reactor of the Beloyarskaya NPP have a unique layout of asynchronous valve cascades (AVC). Twenty five years of successful operation of such drives prove the expediency of the use of AVC, which deserves study and application in the design of power units with BN-800 reactors.
2005-01-01
Adjustable electric drives of the main circulation pumps of the BN-600 reactor of the Beloyarskaya NPP have a unique layout of asynchronous valve cascades (AVC). Twenty five years of successful operation of such drives prove the expediency of the use of AVC, which deserves study and application in the design of power units with BN-800 reactors.
Neutron energy spectra for the BFS critical assemblies
A comparison is made of calculated and experimental data characterizing the neutron energy distribution in six new layouts realized in the bfs critical assemblies and simulating the bn-600 and bn-800 reactor cores. The measurements are performed using the time-of-flight method. The calculations are realized by means of the spectra program set. It is concluded that difference in calculated and experimental data for all assemblies in the 10 keV - 1 MeV energy range approximately corresponds to the double error of the experiment.
2009-01-01
The procedures of the recalculation of the multigroup equation of neutron transport in the two-dimensional r-z geometry based on the quasi-diffusion method are described. The quasi-diffusion method allows a considerable reduction of the required iterations of the source and increases accuracy of the calculation. The procedure is demonstrated on the calculation results of a two-dimensional model of the active zone of the BN-800 reactor working in the self-controlled neutron-nuclear mode.
Residual radioactivity of materials from decommissioning of fast reactors
This article examines the residual reactivity of materials from the decommissioning of fast reactors in Russian Federation states. The BN-800 reactor decommissioning is used as the basis of this paper. Based on a 40-year lifetime, the various long-lived nuclides formed by the activation process are noted, and the residual radiation effects as a function of time after decommissioning are plotted. Possibilities for optimizing construction with respect to residual radiation concerns are discussed, as are possible ways to further limit the radiation hazard during decommissioning operations.
Residual radioactivity of materials from decommissioning of fast reactors
1995-12-01
This article examines the residual reactivity of materials from the decommissioning of fast reactors in Russian Federation states. The BN-800 reactor decommissioning is used as the basis of this paper. Based on a 40-year lifetime, the various long-lived nuclides formed by the activation process are noted, and the residual radiation effects as a function of time after decommissioning are plotted. Possibilities for optimizing construction with respect to residual radiation concerns are discussed, as are possible ways to further limit the radiation hazard during decommissioning operations.
Concept of fast reactors-plutonium burners and their fuel cycle
1996-09-01
In this report the concept is considered of a closed fuel cycle of nuclear power, consisting of thermal and fast reactors, providing utilization of practically all actinides produced in the nuclear power. The major calculation results and the ways to form fast reactors cores for effective actinides burning are presented. The existing limitations on the fresh fuel composition by heat release and radiation characteristics are given. The calculation studies results on the fuel cycle characteristics at repeated fuel recycling in a system of VVER-1000 and BN-800 types reactors are presented. The calculations were carried out for different type cores of the BN-800 reactor - with oxide fuel of increased enrichment and with fuel without uranium-238, varying the burn-out level and the decay time of spent fuel. (author)
1995-12-31
Analyzing the hypothetical costs of BN-800 decommissioning reveals that they can be reduced to a great extend on the base of radioactive danger criteria design optimization. At the same time we can decrease the optimal `cooling down period`from 70-100 to 10-15 years. A lot of radioactive materials far under the level of unrestricted release in optimized variant makes it possible to `reproduce` the reactor almost in the whole provided Closed Cycle of such materials were organized. Due to that, the reliable market of low-level materials and `non-proliferation` principle for them may be put into practice. (authors) 3 refs.
2008-01-01
The transition to a closed fuel cycle after several years of operation of the BN-800 with oxide uranium fuel in an open fuel cycle is examined. It is shown that there is an advantage to using new fuel assemblies with 91 fuel elements with diameter 8.6 mm in a regime with four refuelings. On the basis of new fuel assemblies with mixed uranium-plutonium oxide fuel, transitional recycling to a closed fuel cycle without separating uranium and plutonium and without external plutonium makeup is examined. It is confirmed that a negative sodium void effect of reactivity is achieved with admissible values of the linear power density of a fuel element. It is shown that a regime with four refuelings can be obtained by adding uranium with enrichment no higher than 15% to replace the poison which is re...
Technological aspects of U and Pu recycle as most important element of closed nuclear fuel cycle
1993-12-31
The concept of nuclear power development in Russia proceeds from the need of closing its fuel cycle. Along with the solution of economical aspects (self-support with fuel) the closed cycle will significantly improve the safety due to burning Pu and other radiologically dangerous nuclides and the reliable immobilization of waste arising there from. The paper discusses conversion of Pu and secondary U into fast and light water reactor based power and results of R and D of U-Pu oxide fuel manufacture. The choice of particular methods is also related to safety: minimum dust of high toxicity materials; and remotely handled processes to be performed commercially. The scale of successful tests of MOX fuel assemblies in BN-800, BN-600, BOR-60 (more than 2,500 fuel rods) confirms the correctness of selected technological solutions.
Design and operation of fast reactors in the USSR
This article discusses fast reactors in the Union of Soviet Socialist Republic (USSR) - BR-10, BOR-60, BN-350, BN-600, BN-800, and BN-1600. Operations-related experience on the four operating facilities, BR-10, BOR-60, BN-350, and BN-600, is included; the remaining reactors, BN-800 and BN-1601, are addressed from a design and development perspective.
Design and operation of fast reactors in the USSR
This article discusses fast reactors in the Union of Soviet Socialist Republic (USSR) - BR-10, BOR-60, BN-350, BN-600, BN-800, and BN-1600. Operations-related experience on the four operating facilities, BR-10, BOR-60, BN-350, and BN-600, is included; the remaining reactors, BN-800 and BN-1601, are addressed from a design and development perspective.
Determination of the breeding characteristics of nuclear fuel in fast reactors
Formulations are presented for calculating the breeding factor of four plutonium isotopes - 239, 240, 241, and 242 - in oxide and metal fuels for fuel cycle studies in LMFBR reactors with the aim of determining the accumulation and burnup for plutonium as a whole in order to establish fuel cycle criteria of reactors with different designs and core compositions. Essential to the formulations is the establishment of a uniform asymptotic spectrum of the isotopes. Neutron losses and kinetics are also calculated. Sample date are presented for the BN-800 and BN-1600 reactors.
What You Need To Know About™ Hodgkin Lymphoma
Information about detection, symptoms, diagnosis, and treatment of Hodgkin's disease. NIH Publication No. 07-1555
What You Need To Know About™ Cancer of the Esophagus
Information about detection, symptoms, diagnosis, and treatment of esophageal cancer. NIH Publication No. 00-1557
What You Need To Know About™ Brain Tumors
Information about detection, symptoms, diagnosis, and treatment of brain tumors. NIH Publication No. 09-1558
State of the art and prospects of fast neutron reactors
1997-10-01
On the basis of experience of fast reactor design, construction and operation gained in Russia, this paper outlines their state of the art. The high maturity and efficiency of this type of nuclear power development in Russia and the equalization of the economic characteristics of thermal and fast reactors is shown, as well as the expediency of improvement of nuclear power environmental characteristics owing to fast reactors incorporation. (orig.) 7 refs.
Plutonium use in nuclear power in Russia
This paper discusses plutonium utilization in Russia. Efforts to develop a more efficient plutonium-burning core for fast reactors are outlined. The possibility of building light water reactors for effective plutonium utilization are also discussed. The status of development and implementation of technology for a safe and ecologically acceptable closed nuclear fuel cycle based on plutonium and uranium 233 is described. 4 refs., 4 figs., 1 tab.
An objective of efficient and safe utilization of the weapons grade plutonium constitutes part of the fuel reutilization problem in nuclear power engineering, and issues of safe and ecologically acceptable closed fuel cycle implementation. Therefore, we contemplate this problem relative to the general strategy of nuclear power engineering advance, with a prospect of up-grading and development of conventional reactor types and their fuel cycles.
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