International assistance to upgrade the safety of Soviet-designed nuclear power plants. Selected activities in Eastern and Central Europe and the countries of the former Soviet Union

International Nuclear Information System (INIS)

Gillen, V.

1993-12-01

The overview is merely a snapshot of nuclear safety activities to assist the countries of Eastern and Central Europe and the former Soviet Union. While many other activities are planned or ongoing, this publication is meant to provide a general overview of the world community's commitment to improving the safety of Soviet-designed nuclear reactors

Former Soviet Regulations for seismic design of NPPs and comparison with current international practice

International Nuclear Information System (INIS)

Kostarev, V.; Schukin, A.; Berkovski, A.

1997-01-01

This paper presents a summary of current earthquake design criteria used in former Soviet Regulations for equipment and piping systems of nuclear power plants in light of those used in United States and Japan. The detailed comparative seismic analysis of PWR (WWER) Primary Coolant Loop System (PCLS) according to Former Soviet (Russian) PNAE Code and ASME BPV Code with some comments regarding to Japan Code JEAG - 4601 was undertaken for better understanding of the differences and coincidences of seismic design criteria and requirements. The selection of these three guides for the study has very simple explanation: according to ASME BVPC, JEAG and PNAE the huge majority of existing NPPs has been designed. (J.P.N.)

Former Soviet Regulations for seismic design of NPPs and comparison with current international practice

Energy Technology Data Exchange (ETDEWEB)

Kostarev, V; Schukin, A; Berkovski, A [CKTI-Vibroseism Co. Ltd. (Cape Verde)

1997-03-01

This paper presents a summary of current earthquake design criteria used in former Soviet Regulations for equipment and piping systems of nuclear power plants in light of those used in United States and Japan. The detailed comparative seismic analysis of PWR (WWER) Primary Coolant Loop System (PCLS) according to Former Soviet (Russian) PNAE Code and ASME BPV Code with some comments regarding to Japan Code JEAG - 4601 was undertaken for better understanding of the differences and coincidences of seismic design criteria and requirements. The selection of these three guides for the study has very simple explanation: according to ASME BVPC, JEAG and PNAE the huge majority of existing NPPs has been designed. (J.P.N.)

Apparatus for localizing disturbances in pressurized water reactors (PWR)

International Nuclear Information System (INIS)

Sykora, D.

1989-01-01

The invention according to CS-PS 177386, entitled ''Apparatus for increasing the efficiency and passivity of the functioning of a bubbling-vacuum system for localizing disturbances in nuclear power plants with a pressurized water reactor'', concerns an important area of nuclear power engineering that is being developed in the RGW member countries. The invention solves the problems of increasing the reliability and intensification during the operation of the above very important system for guaranteeing the safety of the standard nuclear power plants of Soviet design. The essence of the invention consists in the installation of a simple passively operating supplementary apparatus. Consequently, the following can be observed in the system: first an improvement and simultaneous increase in the reliability of its function during the critical transition period, which follows the filling of the second space with air from the first space; secondly, elimination of the hitherto unavoidable initiating role of the active sprinkler-condensation device present; thirdly, a more effective performance and subjection of the elements to disintegration of the water flowing from the bubbling condenser into the first space; and fourthly, an enhanced utilization of the heat-conducting ability of the water reservoir of the bubbling condenser. Representatives of the supplementary apparatus are autonomous and local secondary systems of the sprinkler-sprayer without an insert, which spray the water under the effect of gravity. 1 fig

High temperature pressure water's blowdown into water. Experimental results

International Nuclear Information System (INIS)

Ishida, Toshihisa; Kusunoki, Tsuyoshi; Kasahara, Yoshiyuki; Iida, Hiromasa

1994-01-01

The purpose of the present experimental study is to clarify the phenomena in blowdown of high temperature and pressure water in pressure vessel into the containment water for evaluation of design of an advanced marine reactor(MRX). The water blown into the containment water flushed and formed steam jet plume. The steam jet condensed in the water, but some stream penetrated to gas phase of containment and contributed to increase of containment pressure. (author)

Conceptual design of a pressure tube light water reactor with variable moderator control

International Nuclear Information System (INIS)

Rachamin, R.; Fridman, E.; Galperin, A.

2012-01-01

This paper presents the development of innovative pressure tube light water reactor with variable moderator control. The core layout is derived from a CANDU line of reactors in general, and advanced ACR-1000 design in particular. It should be stressed however, that while some of the ACR-1000 mechanical design features are adopted, the core design basics of the reactor proposed here are completely different. First, the inter fuel channels spacing, surrounded by the calandria tank, contains a low pressure gas instead of heavy water moderator. Second, the fuel channel design features an additional/external tube (designated as moderator tube) connected to a separate moderator management system. The moderator management system is design to vary the moderator tube content from 'dry' (gas) to 'flooded' (light water filled). The dynamic variation of the moderator is a unique and very important feature of the proposed design. The moderator variation allows an implementation of the 'breed and burn' mode of operation. The 'breed and burn' mode of operation is implemented by keeping the moderator tube empty ('dry' filled with gas) during the breed part of the fuel depletion and subsequently introducing the moderator by 'flooding' the moderator tube for the 'burn' part. This paper assesses the conceptual feasibility of the proposed concept from a neutronics point of view. (authors)

Modified fuel assembly design for pressurized water reactors with improved fuel utilization

International Nuclear Information System (INIS)

Galperin, A.; Ronen, Y.

1983-01-01

A method for reactivity control through variation of the moderator content in the reactor core was proposed. The main idea is to adjust the amount of water in the core from a low value at beginning of cycle to a high value at end of cycle, so as to compensate for fissile material burnup and buildup of fission products. The possible implementation of this idea may be carried out by introducing a number of hollow tubes into the fuel assembly between the fuel rods. Then variation of the moderator content in the core may be managed through a change of the water level in these tubes. cated a potential savings in the fuel cycle requirements and costs. Preliminary steady-state thermal-hydraulic calculations indicate the possibility of implementing the proposed method in the existing pressurized water reactor plants. Feasibility of the proposed design may be finally established after rigorous thermal hydraulics as well as safety analysis calculations. Furthermore, there is need to elaborate the mechanical design of the pressure vessel internals together with cost benefit analysis

Design and analysis of pressurized water reactor systems

International Nuclear Information System (INIS)

Juhn, P.E.; Kim, Y.H.

1979-01-01

To help develop nuclear engineering technologies in local industry sectors, technical and economical data on pressurized water reactor systems and components have been collected, systematically analyzed and computerized to a certain degree. Codes and standards necessary for engineering design of PWR systems have been surveyed and clarified in terms of NSSS, turbine-generator system and BOP, then again rearranged with respect to quality classes and seismic classes. Some design manuals, criteria and guidelines regarding design, construction, test and operation of PWR plants have also been surveyed and collected. Benchmark cost calculation for the construction of a 900 MWe PWR plant, according to the standard format, was carried out, and computer model on construction costs was improved and updated by considering the local supply of labor and materials. And for the indigeneous development of PWR equipment and materials, such data as delivery schedule and manufacturers of 52 systems and 36,000 components have also been reviewed herein. (author)

Development and design of control rod drive mechanisms for pressurized water reactors

International Nuclear Information System (INIS)

Leme, Francisco Louzano

2003-01-01

The Control Rod Drive Mechanisms (CRDM) for a Pressurized Water Reactor (PWR) are equipment, integrated to the reactor pressure vessel, incorporating mechanical and electrical components designed to move and position the control rods to guarantee the control of power and shutdown of the nuclear reactor, during normal operation, either in emergency or accidental situations. The type of CRDM used in PWR reactors, whose detailed individual description will be presented in this monograph are the Roller-Nut and Magnetic-Jack. The environment, where the CRDM performs its above presented operational functions, includes direct contact with the fluid used as coolant peculiar to the interior of the reactor, and its associated chemical characteristics, the radiation field next to the reactor core, and also the temperature and pressure in the reactor pressure vessel. So the importance of the CRDM design requirements related to its safety functions are emphasized. Finally, some aspects related to the mechanical and structural design of CRDM of a case study, considering the CRDM for a PWR from the experimental nuclear plant to be applied by CTMSP (Centro Tecnologico da Marinha em Sao Paulo), are pointed out. The design and development of these equipment (author)

Analysis of French (Paluel) pressurized water reactor design differences compared to current US PWR designs

International Nuclear Information System (INIS)

1986-05-01

To understand better the regulatory approaches to reactor safety in foreign countries, the staff of the Nuclear Regulatory Commisssion has reviewed design information on the Paluel nuclear power plant, one of the current standard 1300-MWe plant operating in France. This report provides the staff's evaluation of major design differences between this standardized French plant and current US pressurized water reactor plants, as well as insights concerning French regulatory practices. The staff identified approximately 25 design differences, and an analysis of the safety significance of each of these design features is presented, along with an assessment comparing the relative safety benefit of each

Soviet Union's Nuclear Power Program

International Nuclear Information System (INIS)

Anon.

1991-01-01

Glasnost has dramatically increased the availability of information about the Soviet Union's nuclear industry. In the future, even more information is likely to become known as Soviet participation in international forums increases. Not only is much more general information now available, but up-to-date details are regularly provided, including information such as the Soviet nuclear industry's strategic direction and goals, recent reactor design changes, safety inspection results, and reports of public opposition and protest. This article summarizes the current status of the Soviet nuclear power program, reconciling the often conflicting reports from various public sources

Design of a supercritical water-cooled reactor. Pressure vessel and internals

Energy Technology Data Exchange (ETDEWEB)

Fischer, Kai

2008-08-15

The High Performance Light Water Reactor (HPLWR) is a light water reactor with supercritical steam conditions which has been investigated within the 5th Framework Program of the European Commission. Due to the supercritical pressure of 25 MPa, water, used as moderator and as coolant, flows as a single phase through the core and can be directly fed to the turbine. Using the technology of coal fired power plants with supercritical steam conditions, the heat-up in the core is done in several steps to achieve the targeted high steam outlet temperature of 500.C without exceeding available cladding material limits. Based on a first design of a fuel assembly cluster for a HPLWR with a single pass core, the surrounding internals and the reactor pressure vessel (RPV) are dimensioned for the first time, following the safety standards of the nuclear safety standards commission in Germany. Furthermore, this design is extended to the incorporation of core arrangements with two and three passes. The design of the internals and the RPV are verified using mechanical or, in the case of large thermal deformations, combined mechanical and thermal stress analyses. Additionally, a passive safety component for the feedwater inlet of the RPV of the HPLWR is designed. Its purpose is the reduction of the mass flow rate in case of a LOCA for a feedwater line break until further steps are executed. Starting with a simple vortex diode, several steps are executed to enhance the performance of the diode and adapt it to this application. Then, this first design is further optimized using combined 1D and 3D flow analyses. Parametric studies determine the performance and characteristic for changing mass flow rates for this backflow limiter. (orig.)

Design of the US-CRBRP sodium/water reaction pressure relief system

International Nuclear Information System (INIS)

Kruger, G.B.; Murdock, T.B.; Rodwell, E.; Sane, J.O.

1976-01-01

Protection against intermediate sodium system overpressure from the sodium/water reaction associated with large leaks within the CRBRP Steam Generators is provided by the sodium/water reaction pressure relief system (SWRPRS). This system consists of rupture disks connected to the intermediate sodium piping adjacent to the inlet to the superheater and outlet from the evaporator modules. The rupture discs relieve into piping that leads to reaction produce separator tanks, which in turn are vented to a centrifugal separator and flare stack arranged to burn hydrogen gas exhausting into the atmosphere. Analyses have been conducted using the TRANSWRAP Computer Code to predict the system pressures and flow rates during the large leak event. Experimental tests to be conducted in the large leak test rig (LLTR) will be used to confirm the analysis techniques used in the design

Pressurized water reactor system model for control system design and analysis

International Nuclear Information System (INIS)

Cooper, K.F.; Cain, J.T.

1975-01-01

Satisfactory operation of present generation Pressurized Water Reactor (PWR) Nuclear Power systems requires that several independent and interactive control systems be designed. Since it is not practical to use an actual PWR system as a design tool, a mathematical model of the system must be developed as a design and analysis tool. The model presented has been developed to be used as an aid in applying optimal control theory to design and implement new control systems for PWR plants. To be applicable, the model developed must represent the PWR system in its normal operating range. For safety analysis the operating conditions of the system are usually abnormal and, therefore, the system modeling requirements are different from those for control system design and analysis

Soviet civil defense is inadequate and meaningless

International Nuclear Information System (INIS)

Kaplan, F.M.

1985-01-01

In this paper, the author argues that Soviet civil defense plans exist primarily on paper and are used to pacify the Soviet people, not as plans to survive and prevail in a nuclear confrontation with the U.S. The author describes how the Soviet people have little faith in the civil defense programs. They don't believe they can survive an attack. Furthermore, he says the Soviets have never staged an evacuation exercise in any major city nor, even in smaller towns, has an entire community been evacuated. The author says there are numerous problems with the shelter programs as well. Very few existing shelters have any food stocks, only a few more have any water. There is little evidence that Soviet leaders have planned their economy with civil defense in mind. Nor - given the blatant inadequacies of Soviet civil defense programs, the marked vulnerabilities of the Soviet economy, and the intrinsic limitation and uncertainties about civil defense generally - is there much basis for claiming that Soviet leaders, even in desperate straits, would risk war with the United States while counting on civil defense measures to limit the damage wreaked on the Soviet Union

The evolution of CANDU containment design

International Nuclear Information System (INIS)

Pendergast, Duane R.; Meneley, Daniel A.

1995-01-01

This paper reviews Canadian containment design, reflects on forces which have shaped the evolving designs and contemplates future containment design subject to existing constraints of Canadian and International nuclear power regulations. The discussion mentions modifications which could play a role in easing customary restrictions on siting while meeting the intent and literal definition of Canadian licensing requirements. Many different containment concepts have been considered and deployed over the years. Professor Birkhofer points out that the earliest systems installed were 'dry containment'. These rely on large containment buildings designed to contain all the the steam from a loss of coolant. It was soon realized the large water inventory of boiling water reactors would require very large and expensive containment buildings. This led to the development of pressure suppression concepts. Various pressure suppression schemes have been devised to condense steam and thus reduce design pressure and volume requirements. Examples include the forcing of steam into condensing water pools of BWR's steam condensation by passage into arrays of ice, dousing spray systems in CANDU reactors, and the spray condenser systems of late model Soviet designed VVER - 440 reactors. The fundamental concept of energy removal by steam condensation can result in a small containment volume requiring low design pressure capability

Adapting Agricultural Water Use to Climate Change in a Post-Soviet Context: Challenges and Opportunities in Southeast Kazakhstan.

Science.gov (United States)

Barrett, Tristam; Feola, Giuseppe; Khusnitdinova, Marina; Krylova, Viktoria

2017-01-01

The convergence of climate change and post-Soviet socio-economic and institutional transformations has been underexplored so far, as have the consequences of such convergence on crop agriculture in Central Asia. This paper provides a place-based analysis of constraints and opportunities for adaptation to climate change, with a specific focus on water use, in two districts in southeast Kazakhstan. Data were collected by 2 multi-stakeholder participatory workshops, 21 semi-structured in-depth interviews, and secondary statistical data. The present-day agricultural system is characterised by enduring Soviet-era management structures, but without state inputs that previously sustained agricultural productivity. Low margins of profitability on many privatised farms mean that attempts to implement integrated water management have produced water users associations unable to maintain and upgrade a deteriorating irrigation infrastructure. Although actors engage in tactical adaptation measures, necessary structural adaptation of the irrigation system remains difficult without significant public or private investments. Market-based water management models have been translated ambiguously to this region, which fails to encourage efficient water use and hinders adaptation to water stress. In addition, a mutual interdependence of informal networks and formal institutions characterises both state governance and everyday life in Kazakhstan. Such interdependence simultaneously facilitates operational and tactical adaptation, but hinders structural adaptation, as informal networks exist as a parallel system that achieves substantive outcomes while perpetuating the inertia and incapacity of the state bureaucracy. This article has relevance for critical understanding of integrated water management in practice and adaptation to climate change in post-Soviet institutional settings more broadly.

Design of an additional heat sink based on natural circulation in pressurized water reactors

International Nuclear Information System (INIS)

Frischengruber, Kurt; Solanilla, Roberto; Fernandez, Ricardo; Blumenkrantz, Arnaldo; Castano, Jorge

1989-01-01

Residual heat removal through the steam generators in Nuclear Power Plant with pressurized water reactors (PWR) or pressurized heavy water reactors (PHWR in pressured vessel or pressured tube types) requires the maintenance of the steam generator inventory and the availability of and appropriate heat sink, which are based on the operability of the steam generators feedwater system. This paper describes the conceptual design of an assured heat removal system which includes only passive elements and is based on natural circulation. The system can supplement the original systems of the plant. The new system includes a condenser/boiler heat exchanger to condense the steam produced in the steam generator, transferring the heat to the water of an open pool at atmospheric pressure. The condensed steam flows back to the steam generators by natural circulation effects. The performance of an Atucha type PHWR nuclear power station with and without the proposed system is calculated in an emergency power case for the first 5000 seconds after the incident. The analysis shows that the proposed system offers the possibility to cool-down the plant to a low energy state during several hours and avoids the repeated actuation of the primary and secondary system safety valves. (Author) [es

Design description of the European pressurized water reactor

International Nuclear Information System (INIS)

Leverenz, R.

1999-01-01

The EPR (the European Pressurized Water Reactor) is an evolutionary PWR developed by Nuclear Power International and its parent companies, Framatome and Siemens, in co-operation with Electricite de France and German Utilities. NPI can rely on the huge experience gained by its parent companies; they have constructed more than 100 nuclear power plants throughout the world. The total installed capacity exceeds 100,000 MW - about 25% of the total world-wide figure. Following the conceptual design phase of the so-called Common Product conducted by NPI, Framatome and Siemens, from 1989 through 1991, Electricite de France (EDF) and several major German utilities decided to merge their own development programmes, - the N4 Plus and REP 2000 projects on the French side and the further development of the KONVOI technology on the German side, - with the NPI project. From that time on, the NPI project became one single common development line for both countries. In parallel, EDF and the German utilities decided to establish, together with other European utilities, specifications that would represent common utility views on the design and performance of future nuclear power plants. These are documented in the European Utility Requirements (EURs). The basic design has been completed in 1997, and in 1998 a design optimization is being carried out with the goal to even increase the economic competitiveness of nuclear power. This paper provides a brief design description of the EPR. (author)

Conceptual design of a quasi-homogeneous pressurized heavy water reactor to be operated in the closed Th-U233 fuel cycle

International Nuclear Information System (INIS)

1979-06-01

This paper deals with the heavy water reactor, which, from the neutron economy point of view, offers advantages over the light water reactor. Its capability to be fuelled with natural uranium has also been considered a desirable nuclear option by various countries with sufficient domestic uranium resources not wishing to be dependent on the import of enrichment and other fuel cycle services which, in addition, would draw on the foreign exchange reserves. Pressurized heavy water reactors have been designed and built according to two somewhat different versions. While the Canadian CANDU-PHWR concept uses pressure tubes in a nearly unpressurized moderator tank (calandria), the German development line takes advantage of the established and well proven LWR technology, and, thus, uses a pressure vessel design where coolant channels and the surrounding moderator are held at equal pressure. This pressure vessel type heavy water reactor which has been built on a commercial demonstration plant level at ATUCHA in Argentina is described in a companion paper where also a conceptual design for a 685 MWsub(e) PHWR is discussed

A reverse depletion method for pressurized water reactor core reload design

International Nuclear Information System (INIS)

Downar, T.J.; Kin, Y.J.

1986-01-01

Low-leakage fuel management is currently practiced in over half of all pressurized water reactor (PWR) cores. The large numbers of burnable poison pins used to control the power peaking at the in-board fresh fuel positions have introduced an additional complexity to the core reload design problem. In addition to determining the best location of each assembly in the core, the designer must concurrently determine the distribution of burnable poison pins in the fresh fuel. A new method for performing core design more suitable for low-leakage fuel management is reported. A procedure was developed that uses the wellknown ''Haling depletion'' to achieve an end-of-cycle (EOC) core state where the assembly pattern is configured in the absence of all control poison. This effectively separates the assembly assignment and burnable poison distribution problems. Once an acceptable pattern at EOC is configured, the burnable and soluble poison required to control the power and core excess reactivity are solved for as unknown variables while depleting the cycle in reverse from the EOC exposure distribution to the beginning of cycle. The methods developed were implemented in an approved light water reactor licensing code to ensure the validity of the results obtained and provided for the maximum utility to PWR core reload design

Elements of Design Consideration of Once-Through Cycle, Supercritical-Pressure Light Water Cooled Reactor

International Nuclear Information System (INIS)

Yoshiaki Oka; Sei-ichi Koshizuka; Yuki Ishiwatari; Akifumi Yamaji

2002-01-01

The paper describes elements of design consideration of supercritical-pressure, light water cooled reactors as well as the status and prospects of the research and development. It summarizes the results of the conceptual design study at the University of Tokyo from 1989. The research and development started in Japan, Europe and USA. The major advantages of the reactors are 1. Compact reactor and turbines due to high specific enthalpy of supercritical water 2.Simple plant system because of the once-through coolant cycle 3.Use of the experience of LWR and fossil-fired power plants. The temperatures of the major components such as reactor pressure vessel, coolant pipes, pumps and turbines are within the experience, in spite of the high outlet coolant temperature. 4.Similarity to LWR safety design and criteria, but no burnout phenomenon 5.Potential cost reduction due to smaller material expenditure and short construction period 6.The smallest reactor not in power rating, but in plant sizes. 7.High-thermal efficiency and low coolant flow rate because of high enthalpy rise. 8.Water cooled reactors potentially free from SCC (stress corrosion cracking) problems. 9.Compatibility of tight-fuel-lattice fast reactor core due to small coolant flow rate, potentially easy shift to fast breeder reactor without changing coolant technology. 10.Potential of producing energy products such as hydrogen and high quality hydro carbons. (authors)

Cogeneration in the former Soviet Union

International Nuclear Information System (INIS)

Horak, W.C.

1997-01-01

The former Soviet Union made a major commitment to Cogeneration. The scale and nature of this commitment created a system conceptually different from Cogeneration in the west. The differences were both in scale, in political commitment, and in socio economic impact. This paper addresses some of the largest scale Cogeneration programs, the technology, and the residual impact of these programs. The integration of the Cogeneration and nuclear programs is a key focus of the paper. Soviet designed nuclear power plants were designed to produce both electricity and heat for residential and industrial uses. Energy systems used to implement this design approach are discussed. The significant dependence on these units for heat created an urgent need for continued operation during the winter. Electricity and heat are also produced in nuclear weapons production facilities, as well as power plants. The Soviets also had designed, and initiated construction of a number of nuclear power plants open-quotes ATETsclose quotes optimized for production of heat as well as electricity. These were canceled

Outline of design, manufacturing and installation experience of pressure vessel structure for the prototype heavy water moderated boiling light water cooled reactor 'FUGEN'

International Nuclear Information System (INIS)

Shibato, Eizo; Oguchi, Isao; Kishi, Toshikazu; Kitagawa, Yuji

1977-01-01

After component installation completed in June 1977 and various functional tests to be conducted later, the prototype heavy water moderated, boiling light water cooled reactor ''FUGEN'' is scheduled to reach first criticality in March 1978. Since the pressure vessel of ''FUGEN'' is completely different from that of a light water reactor in structure and materials, through research and development work was carried out prior to fabrication and construction. Based on these studies, installation of the actual pressure vessel was completed. Functional tests are now under way. This article describes examples in which our research and development results are reflected on design, manufacture, and installation of the pressure vessel. Also it introduces noteworthy achievements relevant to production techniques in manufacture and installation. (auth.)

Design and safety of the Sizewell pressurized water reactor

International Nuclear Information System (INIS)

Marshall, W.

1983-01-01

The Central Electricity Generating Board propose to build a pressurized water reactor at Sizewell in Suffolk. The PWR Task Force was set up in June 1981 to provide a communications centre for developing firm design proposals for this reactor. These were to follow the Standardized Nuclear Unit Power Plant System designed by Bechtel for the Westinghouse nuclear steam supply system for reactors built in the United States. Changes were required to the design to accommodate, for example, the use of two turbine generators and to satisfy British safety requirements. Differences exist between the British and American licensing procedures. In the UK the statutory responsibility for the safety of a nuclear power station rests unambiguously with the Generating Boards. In the U.S.A. the Nuclear Regulatory Commission issues detailed written instructions, which must be followed precisely. Much of the debate on the safety of nuclear power focuses on the risks of big nuclear accidents. It is necessary to explain to the public what, in a balanced perspective, the risks of accidents actually are. The long-term consequences can be presented in terms of reduction in life expectancy, increased chance of cancer or the equivalent pattern of compulsory cigarette smoking. (author)

Frank Lloyd Wright in the Soviet Union

Directory of Open Access Journals (Sweden)

Brian A. Spencer

2017-12-01

Full Text Available In 1937 the First All-Union Congress of Soviet Architects was held in Moscow. The congress brought  architects from all areas of the  Soviet Union. Under the auspices of Vsesoiuvnoe Obshchestvo Kul'turnoi Sviazi s zagranitsei (VOKS it invited international architects from Europe and North and South America.  The Organizing Committee of the Union of Soviet Architects invited Frank Lloyd Wright from the United States. Frank Lloyd Wright presented his philosophy and exhibited his work, specifically his designs for the weekend home for E. J. Kaufmann "Fallingwater" and the drawings for the S.C. Johnson Administration. Frank Lloyd Wright's presentation did not focus heavily on the architecture but, rather the spirit of the Russian and Soviet vision.

Ecologies of socialism: Soviet Gradostroitel'stvo and late soviet socialism

Directory of Open Access Journals (Sweden)

Timothy Alexander Nunan

2012-07-01

Full Text Available The most lasting legacy of the Soviet experience, more so than institutions that persist in the Russian Federation today or the mentalities of citizens of post-Soviet states, was its transformation of Eurasia from a rural continent into an urban one. Particularly after the Great Patriotic War, the landscape of Soviet urban spaces changed as countless rows of low-quality apartment housing sprung up and a uniform socialist urban culture appeared to be forming. However, how and why this urban revolution happened, and what effect it had on the psychological makeup of Soviet citizens, remains lesser known. Meanwhile, while scholars of urban history such as Jane Jacobs, Reyner Banham, Lewis Mumford, and Mike Davis have produced fascinating tracts and monographs on the “ecologies” of American urban spaces – how, in other words, human beings in various political systems have interacted with the built urban landscape around them – limited work has been done on similar processes and histories in the Soviet world beyond the technical literature of the Cold War era. In this paper, I attempt to provide the outlines of such a history with such an approach by analyzing how changes in the Soviet urban fabric from approximately 1932 to 1980s affected social life in Soviet cities and among Soviet families. Basing my argument on close readings of Soviet books on gradostroitel'stvo (urban construction, urban studies as well as literature, and guided by the insights of the above-listed urbanist thinkers, I argue that changes in urban planning so altered the relationship between citizens, the Party, and History that the Soviet system lost key strengths that had emboldened it during the 1930s and 1940s. In particular, while new Soviet housing projects obviously raised the standard of living of a great portion of the population, in resolving the housing problem, they also dismantled the “stranger's gaze” – the everyday urban clashes that, enabled by

The future 700 MWe pressurized heavy water reactor

International Nuclear Information System (INIS)

Bhardwaj, S.A.

2006-01-01

The design of a 700 MWe pressurized heavy water reactor has been developed. The design is based on the twin 540 MWe reactors at Tarapur of which the first unit has been made critical in less than 5 years from construction commencement. In the 700 MWe design boiling of the coolant, to a limited extent, has been allowed near the channel exit. While making the plant layout more compact, emphasis has been on constructability. Saving in capital cost of about 15%, over the present units, is expected. The paper describes salient design features of 700 MWe pressurized heavy water reactor

Low cost sonoluminescence experiment in pressurized water

Energy Technology Data Exchange (ETDEWEB)

Bernal, L; Insabella, M [LADOP, University of Mar del Plata (Argentina); Bilbao, L [INFIP, University of Buenos Aires and CONICET (Argentina)

2012-06-19

We present a low cost design for demostration and mesurements of light emission from a sonoluminescence experiment. Using pressurized water introduced in an acrylic cylinder and one piezoelectric from an ultrasonic cleaner, we are able to generate cavitacion zones with emission of light. The use of argon to pressurize the water improves the emission an the light can be seen at naked eye in a softlit ambient.

Low cost sonoluminescence experiment in pressurized water

International Nuclear Information System (INIS)

Bernal, L; Insabella, M; Bilbao, L

2012-01-01

We present a low cost design for demostration and mesurements of light emission from a sonoluminescence experiment. Using pressurized water introduced in an acrylic cylinder and one piezoelectric from an ultrasonic cleaner, we are able to generate cavitacion zones with emission of light. The use of argon to pressurize the water improves the emission an the light can be seen at naked eye in a softlit ambient.

High pressure experimental water loop

International Nuclear Information System (INIS)

Grenon, M.

1958-01-01

A high pressure experimental water loop has been made for studying the detection and evolution of cladding failure in a pressurized reactor. The loop has been designed for a maximum temperature of 360 deg. C, a maximum of 160 kg/cm 2 and flow rates up to 5 m 3 /h. The entire loop consists of several parts: a main circuit with a canned rotor circulation pump, steam pressurizer, heating tubes, two hydro-cyclones (one de-gasser and one decanter) and one tubular heat exchanger; a continuous purification loop, connected in parallel, comprising pressure reducing valves and resin pots which also allow studies of the stability of resins under pressure, temperature and radiation; following the gas separator is a gas loop for studying the recombination of the radiolytic gases in the steam phase. The preceding circuits, as well as others, return to a low pressure storage circuit. The cold water of the low pressure storage flask is continuously reintroduced into the high pressure main circuit by means of a return pump at a maximum head of 160 kg /cm 2 , and adjusted to the pressurizer level. This loop is also a testing bench for the tight high pressure apparatus. The circulating pump and the connecting flanges (Oak Ridge type) are water-tight. The feed pump and the pressure reducing valves are not; the un-tight ones have a system of leak recovery. To permanently check the tightness the circuit has been fitted with a leak detection system (similar to the HRT one). (author) [fr

Soviet energy

International Nuclear Information System (INIS)

1991-05-01

As it moves from a centrally planned economy toward a market-based system, the Soviet Union will need to produce and export large quantities of oil to help finance industrial development and to purchase consumer goods from the West. Since 1988, however, Soviet oil production has fallen by about 8.8 percent. Oil exports also have declined, falling by about 15 percent from 1988 to 1990. The main reasons for the production decline are the lack of enough capital for exploration and production and the use of outdated and inefficient production practices. While U.S.-Soviet joint ventures could potentially help reverse this situation, both the United States and the Soviet Union maintain policies and practices that hinder U.S. trade and investment in Soviet oil exploration and production. Despite such difficulties, several U.S. multinational oil companies are proceeding with joint venture agreements, and progress is being made on overcoming some of the obstacles. For example, training programs in western business practices are being offered b the U.S. government, private companies, and universities. In addition, the U.S. and Soviet governments are now negotiating a tax treaty. GAO summarized this report in testimony before Congress

The pressurized water reactor

International Nuclear Information System (INIS)

Gallagher, J.L.

1987-01-01

Pressurized water reactor technology has reached a maturity that has engendered a new surge of innovation, which in turn, has led to significant advances in the technology. These advances, characterized by bold thinking but conservative execution, are resulting in nuclear plant designs which offer significant performance and safety improvements. This paper describes the innovations which are being designed into mainstream PWR technology as well as the desings which are resulting from such innovations. (author)

General design and main problems of a gas-heavy-water power reactor contained in a pressure vessel

International Nuclear Information System (INIS)

Roche, R.; Gaudez, J.C.

1964-01-01

In the framework of research carried out on a CO 2 -cooled power reactor moderated by heavy water, the so-called 'pressure vessel' solution involves the total integration of the core, of the primary circuit (exchanges and blowers) and of the fuel handling machine inside a single, strong, sealed vessel made of pre-stressed concrete. A vertical design has been chosen: the handling 'attic' is placed above the core, the exchanges being underneath. This solution makes it possible to standardize the type of reactor which is moderated by heavy-water or graphite and cooled by a downward stream of carbon dioxide gas; it has certain advantages and disadvantages with respect to the pressure tube solution and these are considered in detail in this report. Extrapolation presents in particular.problems due specifically to the heavy water (for example its cooling,its purification, the balancing of the pressures of the heavy water and of the gas, the assembling of the internal structures, the height of the attic, etc. (authors) [fr

Application-specific integrated circuit design for a typical pressurized water reactor pressure channel trip

International Nuclear Information System (INIS)

Battle, R.E.; Manges, W.W.; Emery, M.S.; Vendermolen, R.I.; Bhatt, S.

1994-01-01

This article discusses the use of application-specific integrated circuits (ASICs) in nuclear plant safety systems. ASICs have certain advantages over software-based systems because they can be simple enough to be thoroughly tested, and they can be tailored to replace existing equipment. An architecture to replace a pressurized water reactor pressure channel trip is presented. Methods of implementing digital algorithms are also discussed

Soviet steam generator technology: fossil fuel and nuclear power plants

International Nuclear Information System (INIS)

Rosengaus, J.

1987-01-01

In the Soviet Union, particular operational requirements, coupled with a centralized planning system adopted in the 1920s, have led to a current technology which differs in significant ways from its counterparts elsewhere in the would and particularly in the United States. However, the monograph has a broader value in that it traces the development of steam generators in response to the industrial requirements of a major nation dealing with the global energy situation. Specifically, it shows how Soviet steam generator technology evolved as a result of changing industrial requirements, fuel availability, and national fuel utilization policy. The monograph begins with a brief technical introduction focusing on steam-turbine power plants, and includes a discussion of the Soviet Union's regional power supply (GRES) networks and heat and power plant (TETs) systems. TETs may be described as large central co-generating stations which, in addition to electricity, provide heat in the form of steam and hot water. Plants of this type are a common feature of the USSR today. The adoption of these cogeneration units as a matter of national policy has had a central influence on Soviet steam generator technology which can be traced throughout the monograph. The six chapters contain: a short history of steam generators in the USSR; steam generator design and manufacture in the USSR; boiler and furnace assemblies for fossil fuel-fired power stations; auxiliary components; steam generators in nuclear power plants; and the current status of the Soviet steam generator industry. Chapters have been abstracted separately. A glossary is included containing abbreviations and acronyms of USSR organizations. 26 references

Evolution of general design requirements for french pressurized water reactors

International Nuclear Information System (INIS)

Gros, G.; Jalouneix, J.; Rollinger, F.

1988-10-01

The design of French pressurized water reactors is based first on deterministic principles, using the well-known defense in depth concept. This safety approach, basically reflected current American practice at that time, which consisted notably in designing engineered safeguard systems capable of limiting the consequences of accidents assumed to be credible despite the preventive measures taken. Further reflections have led to complete this approach, resulting in modifications to regulatory practice, mainly related to better practical assimilation of the problems arising during plant unit operation and reactor control after an accident and to the determination to enhance the overall consistency of the safety approach. As regards system redundancy, it should be noted that common cause failures can result in the total loss of a redundant system. System redundancy aspects will be dealt with in Chapter 2. As regards study of design basis accidents, attention was focused on the human intervention stage following automatic activation of protection and safeguard systems. This resulted, for all plant units, in the revision of operating procedures, accompanied by examination of the means required for their implementation. These subjects will be discussed in Chapter 3. Finally, as regards equipment classification, the range of equipment subjected to particular requirements, formerly limited to design basis safety classified equipment, was enlarged to include important for safety equipment. This subject will be dealt with in Chapter 5

The European Pressurized Water Reactor (EPR). State of the art after the preliminary design phase

International Nuclear Information System (INIS)

Bouteille, F.; Schneider, D.

2002-01-01

The European Pressurized Water Reactor (EPR) is an evolutionary development of the pressurized water reactor product lines built by Framatome and Siemens in France and Germany. Under the technical leadership of both nuclear power plant suppliers (now merged in Framatome ANP, a joint venture of AREVA and Siemens) the future-oriented plant concepts was developed in close cooperation with German and French utilities and in compliance with the European Utility Requirements. The EPR has safety features with which even extremely improbable, beyond design-basis events can be controlled and their effects can be limited to such an extent that no emergency response actions need be taken outside of the immediate plant site. This also means that safety systems prevent containment failure even in the improbable case of a core melt. This was confirmed by the French and German reactor safety authorities. The selected high thermal output also insures the economic viability of the innovative reactor concept, so that the power generation costs which can be achieved with the EPR will be absolutely competitive with those of fossil energy carriers. Framatome ANP has thus developed a pressurized water reactor ready for offer at the right time, which can completely fulfill the most rigorous requirements in terms of nuclear safety and economy. (Author)

The Soviet Union and Soviet citizens in Finnish magazines

Directory of Open Access Journals (Sweden)

Tuija Saarinen

2014-07-01

Full Text Available The focus of this article’s is to study Finnish popular journalism in 1970s and 1980s. A magazine studied in this article is Hymy (Smile, and it has been estimated that in the beginning of 1970s approximately the whole literary population of Finland read it. The purpose of this study is to analyze the different images Hymy created and published of the Soviet Union and the Soviet citizens. The central research question analyzes what kinds of issues Hymy published about the Soviet Union and its citizens before 1991. This study gives special attention to the reasons why the articles were written in the first place, and secondly, what was the nature of their content.        Hymy published 224 articles on the Soviet Union. The articles were mostly written in the spirit of criticism – not in the spirit of “friendship of the peoples” that was the official political stance of Finland toward the Soviet Union. Magazines had to be aware of the official Finnish political rhetoric concerning the relationship with the Soviet Union. Hymy as a popular magazine found a way to evade the official mandate. In Hymy, people were able to read anti-Soviet sentiments without any censoring. Therefore, Hymy not only provided its readers views and beliefs that expressed the popular beliefs and values, but also sympathized with them. The Cold War era in the 1970s and 1980s was still a post-traumatic period for Finns. The magazine Hymy was an important channel to publish stories on painful, embarrassing, and tragic subjects.

The max–min ant system and tabu search for pressurized water reactor loading pattern design

International Nuclear Information System (INIS)

Lin, Chaung; Chen, Ying-Hsiu

2014-01-01

Highlights: • An automatic loading pattern design tool for a pressurized water reactor is developed. • The design method consists of max–min ant system and tabu search. • The heuristic rules are developed to generate the candidates for tabu search. • The initial solution of tabu search is provided by max–min ant system. • The new algorithm shows very satisfactory results compared to the old one. - Abstract: An automatic loading pattern (LP) design tool for a pressurized water reactor is developed. The design procedure consists of two steps: first, a LP is generated using max–min ant system (MMAS) and then tabu search (TS) is adopted to search the satisfactory LP. The MMAS is previously developed and the TS process is newly-developed. The heuristic rules are implemented to generate the candidate LP in TS process. The heuristic rules are comprised of two kinds of action, i.e., a single swap in the location of two fuel assemblies and rotation of fuel assembly. Since developed TS process is a local search algorithm, it is efficient for the minor change of LP. It means that a proper initial LP should be provided by the first step, i.e., by MMAS. The design requirements such as hot channel factor, the hot zero power moderator temperature coefficient, and cycle length are formulated in the objective function. The results show that the developed tool can obtain the satisfactory LP and dramatically reduce the computation time compared with previous tool using ant system alone

Economical opportunities on advanced conventional island design for the European pressurized water reactor (EPR) based on Konvoi design. Annex 6

International Nuclear Information System (INIS)

Kremayr, A.; Wagner, K.; Schuberth, U.

2002-01-01

Design of the European Pressurized Water Reactor (EPR) has been finalized by the end of 1998. In parallel with these efforts, the German utilities group contracted the Siemens AG Power generation Group (KWU) to develop an advanced and optimized conventional island for the EPR. The main objectives for improving the conventional island design were determined on the basis of experience of the Konvoi series plants and advanced fossil plants. This paper describes the innovations introduced to the conventional island and presents the reasons for the resultant cost reductions. (author)

Functional systems of a pressurized water reactor

International Nuclear Information System (INIS)

Heinzel, V.

1982-01-01

The main topics, discussed in the present paper, are: - Principle design of the reactor coolant system - reactor pressure vessel with internals - containment design - residual heat removal and emergency cooling systems - nuclear component cooling systems - emergency feed water systems - plant electric power supply system. (orig./RW)

The Soviet RBMK-1000 containment system

International Nuclear Information System (INIS)

Joosten, J.K.

1988-01-01

Following the accident in April, 1986, considerable attention was focused on the failure of the containment at the Chernobyl RBMK-1000 nuclear power plant. Conflicting statements arose regarding the nature of the plant's containment system primarily because of terminology differences, translation difficulties and lack of reliable information. This article, based on reports and briefings by the Soviet delegation, during the post-accident review meetings in Vienna and prior publications is intended to clarify perceptions of the Soviet RMBK-1000 nuclear power plant containment system design, and its relevance to containment management concepts. (author)

Supercritical-pressure light water cooled reactors

CERN Document Server

Oka, Yoshiaki

2014-01-01

This book focuses on the latest reactor concepts, single pass core and experimental findings in thermal hydraulics, materials, corrosion, and water chemistry. It highlights research on supercritical-pressure light water cooled reactors (SCWRs), one of the Generation IV reactors that are studied around the world. This book includes cladding material development and experimental findings on heat transfer, corrosion and water chemistry. The work presented here will help readers to understand the fundamental elements of reactor design and analysis methods, thermal hydraulics, materials and water

Methodology for surge pressure evaluation in a water injection system

Energy Technology Data Exchange (ETDEWEB)

Meliande, Patricia; Nascimento, Elson A. [Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil). Dept. de Engenharia Civil; Mascarenhas, Flavio C.B. [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Lab. de Hidraulica Computacional; Dandoulakis, Joao P. [SHELL of Brazil, Rio de Janeiro, RJ (Brazil)

2009-07-01

Predicting transient effects, known as surge pressures, is of high importance for offshore industry. It involves detailed computer modeling that attempts to simulate the complex interaction between flow line and fluid in order to ensure efficient system integrity. Platform process operators normally raise concerns whether the water injection system is adequately designed or not to be protected against possible surge pressures during sudden valve closure. This report aims to evaluate the surge pressures in Bijupira and Salema water injection systems due to valve closure, through a computer model simulation. Comparisons among the results from empirical formulations are discussed and supplementary analysis for Salema system were performed in order to define the maximum volumetric flow rate for which the design pressure was able to withstand. Maximum surge pressure values of 287.76 bar and 318.58 bar, obtained in Salema and Bijupira respectively, using empirical formulations have surpassed the operating pressure design, while the computer model results have pointed the greatest surge pressure value of 282 bar in Salema system. (author)

Flooding of a large, passive, pressure-tube light water reactor

International Nuclear Information System (INIS)

Hejzlar, P.; Todreas, N.E.; Driscoll, M.J.

1997-01-01

A reactor concept has been developed which can survive loss of coolant accidents without scram and without replenishing primary coolant inventory, while maintaining safe temperature limits on the fuel and pressure tubes. The proposed concept is a pressure tube type reactor of similar design to CANDU reactors, but differing in three key aspects. First, a solid SiC-coated graphite fuel matrix is used in place of fuel pin bundles to enable the dissipation of decay heat from the fuel in the absence of primary coolant. Second, the heavy water coolant in the pressure tubes is replaced by light water, which also serves as the moderator. Finally, the calandria tank, surrounded by a graphite reflector, contains a low pressure gas instead of heavy water moderator, and this normally-voided calandria is connected to a light water heat sink. The cover gas displaces the light water from the calandria during normal operation, while during loss of coolant or loss of heat sink accidents it allows passive calandria flooding. Calandria flooding also provides redundant and diverse reactor shutdown. This paper describes the thermal hydraulic characteristics of the passively initiated, gravity driven calandria flooding process. Flooding the calandria space with light water is a unique and very important feature of the proposed pressure-tube light water reactor (PTLWR) concept. The flooding of the top row of fuel channels must be accomplished fast enough so that in the total loss of coolant, none of the critical components of the fuel channel, i.e. the pressure tube, the calandria tube, the matrix and the fuel, exceed their design limits. The flooding process has been modeled and shown to be rapid enough to maintain all components within their design limits. (orig.)

Soviet debate on missile defense

Energy Technology Data Exchange (ETDEWEB)

Parrott, B.

1987-04-01

Although the Strategic Defense Initiative (SDI) is meant to cope with the danger of a Soviet nuclear attack, the recent US debate over SDI has paid surprisingly little attention to Soviet views of ballistic missile defense. Despite the existence of a substantial body of pertinent scholarship, the debate has failed to take adequate account of major changes in Soviet ballistic missile defense policy since the mid-1960s. It has also neglected the links between current Soviet military policy and broader Soviet political and economic choices. The Soviets regard SDI not as a novel undertaking to reduce the risks of nuclear war but as an extension of the geopolitical competition between the superpowers. This competition has been dominated in the 1980s, in the Soviet view, by sharply increased US assertiveness and the decline of detente. Viewing SDI as a manifestation of these general trends, Soviet decision makers find the prospect of an unregulated race in ballistic missile defenses and military space technologies deeply unsettling. The deterioration of superpower relations has raised serious doubts in Moscow about the wisdom of Soviet external policy during the 1970s and has provoked sharp internal differences over policy toward the US. Already highly suspicious of the Reagan administration, the elite is united by a general conviction that SDI is an American gambit that may ultimately undercut past Soviet strategic gains and pose a grave new threat to Soviet security. 14 references.

Multiobjective pressurized water reactor reload core design by nondominated genetic algorithm search

International Nuclear Information System (INIS)

Parks, G.T.

1996-01-01

The design of pressurized water reactor reload cores is not only a formidable optimization problem but also, in many instances, a multiobjective problem. A genetic algorithm (GA) designed to perform true multiobjective optimization on such problems is described. Genetic algorithms simulate natural evolution. They differ from most optimization techniques by searching from one group of solutions to another, rather than from one solution to another. New solutions are generated by breeding from existing solutions. By selecting better (in a multiobjective sense) solutions as parents more often, the population can be evolved to reveal the trade-off surface between the competing objectives. An example illustrating the effectiveness of this novel method is presented and analyzed. It is found that in solving a reload design problem the algorithm evaluates a similar number of loading patterns to other state-of-the-art methods, but in the process reveals much more information about the nature of the problem being solved. The actual computational cost incurred depends on the core simulator used; the GA itself is code independent

Atlas of the Soviet Union.

Science.gov (United States)

Young, Harry F.

This atlas consists of 20 maps, tables, charts, and graphs with complementary text illustrating Soviet government machinery, trade and political relations, and military stance. Some topics depicted by charts and graphs include: (1) Soviet foreign affairs machinery; (2) Soviet intelligence and security services; (4) Soviet position in the United…

Performance Evaluation of Pressure Transducers for Water Impacts

Science.gov (United States)

Vassilakos, Gregory J.; Stegall, David E.; Treadway, Sean

2012-01-01

The Orion Multi-Purpose Crew Vehicle is being designed for water landings. In order to benchmark the ability of engineering tools to predict water landing loads, test programs are underway for scale model and full-scale water impacts. These test programs are predicated on the reliable measurement of impact pressure histories. Tests have been performed with a variety of pressure transducers from various manufacturers. Both piezoelectric and piezoresistive devices have been tested. Effects such as thermal shock, pinching of the transducer head, and flushness of the transducer mounting have been studied. Data acquisition issues such as sampling rate and anti-aliasing filtering also have been studied. The response of pressure transducers have been compared side-by-side on an impulse test rig and on a 20-inch diameter hemisphere dropped into a pool of water. The results have identified a range of viable configurations for pressure measurement dependent on the objectives of the test program.

Optimization of core reload design for low leakage fuel management in pressurized water reactors

International Nuclear Information System (INIS)

Kim, Y.J.

1986-01-01

A new method was developed to optimize pressurized water reactor core reload design for low leakage fuel management, a strategy recently adopted by most utilities to extend cycle length and mitigate pressurized thermal shock concerns. The method consists of a two-stage optimization process which provides the maximum cycle length for a given fresh fuel loading subject to power peaking constraints. In the first stage, a best fuel arrangement is determined at the end of cycle in the absence of burnable poisons. A direct search method is employed in conjunction with a constant power, Haling depletion. In the second stage, the core control poison requirements are determined using a linear programming technique. The solution provides the fresh fuel burnable poison loading required to meet core power peaking constraints. An accurate method of explicitly modeling burnable absorbers was developed for this purpose. The design method developed here was implemented in a currently recognized fuel licensing code, SIMULATE, that was adapted to the CYBER-205 computer. This methodology was applied to core reload design of cycles 9 and 10 for the Commonwealth Edison Zion, Unit-1 Reactor. The results showed that the optimum loading pattern for cycle 9 yielded almost a 9% increase in the cycle length while reducing core vessel fluence by 30% compared with the reference design used by Commonwealth Edison

Soviet test yields

Science.gov (United States)

Vergino, Eileen S.

Soviet seismologists have published descriptions of 96 nuclear explosions conducted from 1961 through 1972 at the Semipalatinsk test site, in Kazakhstan, central Asia [Bocharov et al., 1989]. With the exception of releasing news about some of their peaceful nuclear explosions (PNEs) the Soviets have never before published such a body of information.To estimate the seismic yield of a nuclear explosion it is necessary to obtain a calibrated magnitude-yield relationship based on events with known yields and with a consistent set of seismic magnitudes. U.S. estimation of Soviet test yields has been done through application of relationships to the Soviet sites based on the U.S. experience at the Nevada Test Site (NTS), making some correction for differences due to attenuation and near-source coupling of seismic waves.

Developments in Soviet Journalism.

Science.gov (United States)

Gaunt, Philip

1987-01-01

Studies the news values, practices, and role of journalists in the Soviet Union. Claims that, although the Soviet press currently resembles a corporate public relations department, there are signs of change because of public demands. States that journalistic practices in the U.S. and Soviet Union are similar in their reliance on routine and…

Trends in Design of Water Hydraulics

DEFF Research Database (Denmark)

Conrad, Finn

2005-01-01

ordinary tap water and the range of application areas are illustrated with examples, in particular within the food processing industry, humidification operations, water mist systems for fire fighting, high water pressure cleaners, water moisturising systems for wood processing, lumber drying process...... operate with pure water from the tap without additives of any kind. Hence water hydraulics takes the benefit of pure water as fluid being environmentally friendly, easy to clean sanitary design, non-toxic, non-flammable, inexpensive, readily available and easily disposable. The low-pressure tap water...... and accessories running with sea-water as fluid are available. A unique solution is to use reverse osmosis to generate drinking water from sea-water, and furthermore for several off-shore applications. Furthermore, tap water hydraulic components of the Nessie® family and examples of measured performance...

Soviet Marxism and population policy.

Science.gov (United States)

Vonfrank, A

1984-01-01

American demographers have maintained that Marxism, notably Soviet Marxism, is consistently pronatalist. The Soviet view is said to be that population growth is not a problem and that birth control policies in either developed or developing societies are to be rejected; the "correct" (i.e., socialist) socioeconomic structure is the true solution to alleged population problems. Such representations of Soviet thought greatly oversimplify the Soviet position as well as fail to discern the changes in Soviet thought that have been occurring. Since the 1960s Soviet writers have increasingly acknowledged that population growth is, to a considerable degree, independent of the economic base of society and that conscious population policies may be needed to either increase or decrease the rate of population growth. Even socialist societies can have population problems. And where population growth is too rapid, as in the developing countries, policies to slow such growth are needed because of the threat to economic development. However, the Soviets continue to stress that birth control policies must go hand-in-hand with social and economic development policies if they are to be effective.

Technology transfer of the systematic approach to training to Soviet designed nuclear power plants

International Nuclear Information System (INIS)

Haber, S.B.; Yoder, J.A.

1998-01-01

International Nuclear Safety Program initiated by US DOE in 1992 in Russia and Ukraine was expanded to include Armenia (together with IAEA), Bulgaria, Lithuania and Slovak Republic. Presentation describes the background, objectives, activities and key accomplishments of technology transfer of SAT to Soviet designed NPPs. High level of cooperation between countries was achieved showing mutual commitment of US and the countries involved to improve the quality of training of NPP personnel. Technology transfer will succeed because of the efforts and dedication of personnel from the initial sites in Russia and Ukraine

Pressure vessel design manual

CERN Document Server

Moss, Dennis R

2013-01-01

Pressure vessels are closed containers designed to hold gases or liquids at a pressure substantially different from the ambient pressure. They have a variety of applications in industry, including in oil refineries, nuclear reactors, vehicle airbrake reservoirs, and more. The pressure differential with such vessels is dangerous, and due to the risk of accident and fatality around their use, the design, manufacture, operation and inspection of pressure vessels is regulated by engineering authorities and guided by legal codes and standards. Pressure Vessel Design Manual is a solutions-focused guide to the many problems and technical challenges involved in the design of pressure vessels to match stringent standards and codes. It brings together otherwise scattered information and explanations into one easy-to-use resource to minimize research and take readers from problem to solution in the most direct manner possible. * Covers almost all problems that a working pressure vessel designer can expect to face, with ...

Low cost sonoluminescence experiment in pressurized water

Science.gov (United States)

Bernal, L.; Insabella, M.; Bilbao, L.

2012-06-01

We present a low cost design for demostration and mesurements of light emmision from a sonoluminescence experiment. Using presurized water introduced in an acrylic cylinder and one piezoelectric from an ultrasonic cleaner, we are able to generate cavitacion zones with emission of light. The use of argon to pressurize the water improves the emission an the light can be seen at naked eye in a softlit ambient.

Advancing further the history of Soviet psychology: moving forward from dominant representations in Western and Soviet psychology.

Science.gov (United States)

González Rey, Fernando L

2014-02-01

This article discusses the works of some Soviet scholars of psychology, their theoretical positions, and the times within which their works were developed. Dominant representations of Soviet psychology and some of the main Soviet authors are revisited in the light of a blending of facts actively associated with their emergence in both Soviet and Western psychology. From the beginning, Soviet psychology was founded upon Marxism. However, the ways by which that psychology pretended to become Marxist in its philosophical basis were diverse and often contradictory. Other philosophical and theoretical positions also influenced Soviet psychologists. Different moments of that contradictory process are discussed in this article, and through this, I bring to light their interrelations and the consequences for the development of Soviet psychology. This article reinterprets several myths found within Soviet psychology, in which different theoretical representations have become institutionalized for long periods in both Soviet and Western psychology. Particular attention is given to identifying the conditions that presented Vygotsky, Luria, and Leontiev as part of the same paradigm, and which paved the way for a perception of Leontiev and his group as paralleling Vygotsky's importance among American psychologists. Many of the sources that are used in this article were published in Soviet psychology only after the 1970s. Unlike the different and interesting works that began to appear on diverse trends in Soviet psychology, this article details in depth the articulation of topics and questions that still now are presented as different chapters in the analysis of Soviet psychology.

Soviet Cultural Diplomacy towards Denmark during the Cold War, 1945-1991

DEFF Research Database (Denmark)

Frederichsen, Kim

bacteriological warfare in Korea, or the campaign against (West) German rearmament.Regarding reception and impact, it is concluded that the Soviet direct and supported activities were aimed at influencing public opinion and thereby give the impression of a public pressure that would in turn affect policy makers...... of the dissertation is that despite some success stories, including a wider audience form the mid-1970s on, it proved very difficult for the Soviet Union to achieve broad public sympathy for its messages as they more often than not seemed alien to the majority of the Danish public and therefore failed to influence...

JPRS Report Soviet Union Political Affairs.

Science.gov (United States)

1990-07-26

the right of immunity and can be removed from his post only by the Azerbaijan SSR Supreme Soviet in case of a violation by him of the constitution...ities of judges and people’s assessors and their execution of justice is inadmissible and is punishable by law. The immunity of judges and people’s...ecologically clean water to be sold in bottles and cardboard containers- -like kefir . Understandably, this beverage will cost more than tap water, but is

A Rocket Powered Single-Stage-to-Orbit Launch Vehicle With U.S. and Soviet Engineers

Science.gov (United States)

MacConochie, Ian O.; Stnaley, Douglas O.

1991-01-01

A single-stage-to-orbit launch vehicle is used to assess the applicability of Soviet Energia high-pressure-hydrocarbon engine to advanced U.S. manned space transportation systems. Two of the Soviet engines are used with three Space Shuttle Main Engines. When applied to a baseline vehicle that utilized advanced hydrocarbon engines, the higher weight of the Soviet engines resulted in a 20 percent loss of payload capability and necessitated a change in the crew compartment size and location from mid-body to forebody in order to balance the vehicle. Various combinations of Soviet and Shuttle engines were evaluated for comparison purposes, including an all hydrogen system using all Space Shuttle Main Engines. Operational aspects of the baseline vehicle are also discussed. A new mass properties program entitles Weights and Moments of Inertia (WAMI) is used in the study.

Thermal Hydraulic Integral Effect Tests for Pressurized Water Reactors

Energy Technology Data Exchange (ETDEWEB)

Baek, W. P.; Song, C. H.; Kim, Y. S. and others

2005-02-15

The objectives of the project are to construct a thermal-hydraulic integral effect test facility and to perform various integral effect tests for design, operation, and safety regulation of pressurized water reactors. During the first phase of this project (1997.8{approx}2002.3), the basic technology for thermal-hydraulic integral effect tests was established and the basic design of the test facility was accomplished: a full-height, 1/300-volume-scaled full pressure facility for APR1400, an evolutionary pressurized water reactor that was developed by Korean industry. Main objectives of the present phase (2002.4{approx}2005.2), was to optimize the facility design and to construct the experimental facility. We have performed following researches: 1) Optimization of the basic design of the thermal-hydraulic integral effect test facility for PWRs - ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) - Reduced height design for APR1400 (+ specific design features of KSNP safety injection systems) - Thermal-hydraulic scaling based on three-level scaling methodology by Ishii et al. 2) Construction of the ATLAS facility - Detailed design of the test facility - Manufacturing and procurement of components - Installation of the facility 3) Development of supporting technology for integral effect tests - Development and application of advanced instrumentation technology - Preliminary analysis of test scenarios - Development of experimental procedures - Establishment and implementation of QA system/procedure.

Study on low pressure evaporation of fresh water generation system model

Energy Technology Data Exchange (ETDEWEB)

Chung, Han Shik; Wibowo, Supriyanto; Shin, Yong Han; Jeong, Hyo Min [Gyeongsang National University, Tongyeong (Korea, Republic of); Fajar, Berkah [University of Diponegoro, Semarang (Indonesia)

2012-02-15

A low pressure evaporation fresh water generation system is designed for converting brackish water or seawater into fresh water by distillation in low pressure and temperature. Distillation through evaporation of feed water and subsequent vapor condensation as evaporation produced fresh water were studied; tap water was employed as feed water. The system uses the ejector as a vacuum creator of the evaporator, which is one of the most important parts in the distillation process. Hence liquid can be evaporated at a lower temperature than at normal or atmospheric conditions. Various operating conditions, i.e. temperature of feed water and different orifice diameters, were applied in the experiment to investigate the characteristics of the system. It was found that these parameters have a significant effect on the performance of fresh water generation systems with low pressure evaporation.

A Mixed-Oxide Assembly Design for Rapid Disposition of Weapons Plutonium in Pressurized Water Reactors

International Nuclear Information System (INIS)

Alonso, Gustavo; Adams, Marvin L.

2002-01-01

We have created a new mixed-oxide (MOX) fuel assembly design for standard pressurized water reactors (PWRs). Design goals were to maximize the plutonium throughput while introducing the lowest perturbation possible to the control and safety systems of the reactor. Our assembly design, which we call MIX-33, offers some advantages for the disposition of weapons-grade plutonium; it increases the disposition rate by 8% while increasing the worth of control material, compared to a previous Westinghouse design. The MIX-33 design is based upon two ideas: the use of both uranium and plutonium fuel pins in the same assembly, and the addition of water holes in the assembly. The main result of this paper is that both of these ideas are effective at increasing Pu throughput and increasing the worth of control material. With this new design, according to our analyses, we can transition smoothly from a full low-enriched-uranium (LEU) core to a full MIX-33 core while meeting the operational and safety requirements of a standard PWR. Given an interruption of the MOX supply, we can transition smoothly back to full LEU while meeting safety margins and using standard LEU assemblies with uniform pinwise enrichment distribution. If the MOX supply is interrupted for only one cycle, the transition back to a full MIX-33 core is not as smooth; high peaking could cause power to be derated by a few percent for a few weeks at the beginning of one transition cycle

Fundamentals of pressurized water reactors

International Nuclear Information System (INIS)

Murray, L.

1982-01-01

In many countries, the pressurized water reactor (PWR) is the most widely used, even though it requires enrichment of the uranium to about 3% in U-235 and the moderator-coolant must be maintained at a high pressure, about 2200 pounds per square inch. Our objective in this series of seven lectures is to describe the design and operating characteristics of the PWR system, discuss the reactor physics methods used to evaluate performance, examine the way fuel is consumed and produced, study the instrumentation system, review the physics measurements made during initial startup of the reactor, and outline the administrative aspects of starting up a reactor and operating it safely and effectively

Startup of a high-temperature reactor cooled and moderated by supercritical-pressure light water

International Nuclear Information System (INIS)

Yi, Tin Tin; Ishiwatari, Yuki; Koshizuka, Seiichi; Oka, Yoshiaki

2003-01-01

The startup schemes of high-temperature reactors cooled and moderated by supercritical pressure light water (SCLWR-H) with square lattice and descending flow type water rods are studied by thermal-hydraulic analysis. In this study, two kinds of startup systems are investigated. In the constant pressure startup system, the reactor starts at a supercritical pressure. A flash tank and pressure reducing valves are necessary. The flash tank is designed so that the moisture content in the steam is less than 0.1%. In sliding pressure startup system, the reactor starts at a subcritical pressure. A steam-water separator and a drain tank are required for two-phase flow at startup. The separator is designed by referring to the water separator used in supercritical fossil-fired power plants. The maximum cladding surface temperature during the power-raising phase of startup is restricted not to exceed the rated value of 620degC. The minimum feedwater flow rate is 25% for constant pressure startup and 35% for sliding pressure startup system. It is found that both constant pressure startup system and sliding pressure startup system are feasible in SCLWR-H from the thermal hydraulic point of view. The core outlet temperature as high as 500degC can be achieved in the present design of SCLWR-H. Since the feedwater flow rate of SCLWR-H (1190 kg/s) is lower than that of the previous SCR designs the weight of the component required for startup is reduced. The sliding pressure startup system is better than constant pressure startup system in order to reduce the required component weight (and hence material expenditure) and to simplify the startup plant system. (author)

The secret of the Soviet hydrogen bomb

Science.gov (United States)

Wellerstein, Alex; Geist, Edward

2017-11-01

Was the first Soviet thermonuclear device really a step in the wrong direction? No bomb design has been as much maligned or otherwise disparaged as the first Soviet thermonuclear weapon. Detonated in August 1953, the bomb, officially tested under the name RDS-6s but usually known as Sloika or "layer cake" (the name Andrei Sakharov coined for it), was nothing to sneeze at. Shown in Figure 1 and able to be dropped from aircraft, it released the explosive equivalent, or yield, of almost half a megaton of TNT. The result was a blazing fireball with 20 times the power of the bomb that leveled Nagasaki, Japan.

Criminal-legal prohibitions in the soviet juridical discourse

Directory of Open Access Journals (Sweden)

Andrey V. Skorobogatov

2014-01-01

Full Text Available Objective to determine the place of criminal law prohibitions in the formation development and functioning of the Soviet legal discourse. Methods dialectic approach to the research of social phenomena which allows to analyze them in historical development and functioning in the context of the unity of the objective and subjective factors as well as postmodern paradigm giving the opportunity to explore the legal reality at different levels including the lawinterpretation one. Dialectical approach and postmodern paradigm have determined the choice of specific research methods comparative hermeneutics discursive formally legal. Results basing on the analysis of normativelegal acts regulating criminal legal relations in the USSR the development of the Soviet criminal law was considered since its emergence to termination of existence. Conclusion on its restrictive nature was made which was in line with the main task of this sector of law ndash the protection of the Soviet system and socialist property from criminal encroachments. The normative regulatory basis of criminal law prohibitions determined the general nature of the Soviet legal discourse which was designed to prove the necessity and expediency of such means of protecting public and state interests in the period of building communism. Scientific novelty on the basis of use of the complex classical and postclassical methods the article for the first time studies the role of criminal law prohibitions in the development of Soviet legal discourse. Practical value the key issues and conclusions of the article can be used in scientific and pedagogical activity while researching the issues of the nature and trends of development of the Soviet criminal law.

Water-Based Pressure-Sensitive Paints

Science.gov (United States)

Jordan, Jeffrey D.; Watkins, A. Neal; Oglesby, Donald M.; Ingram, JoAnne L.

2006-01-01

Water-based pressure-sensitive paints (PSPs) have been invented as alternatives to conventional organic-solvent-based pressure-sensitive paints, which are used primarily for indicating distributions of air pressure on wind-tunnel models. Typically, PSPs are sprayed onto aerodynamic models after they have been mounted in wind tunnels. When conventional organic-solvent-based PSPs are used, this practice creates a problem of removing toxic fumes from inside the wind tunnels. The use of water-based PSPs eliminates this problem. The waterbased PSPs offer high performance as pressure indicators, plus all the advantages of common water-based paints (low toxicity, low concentrations of volatile organic compounds, and easy cleanup by use of water).

Design and development of low pressure evaporator/condenser unit for water-based adsorption type climate control systems

Science.gov (United States)

Venkataramanan, Arjun; Rios Perez, Carlos A.; Hidrovo, Carlos H.

2016-11-01

Electric vehicles (EVs) are the future of clean transportation and driving range is one of the important parameters which dictates its marketability. In order to increase driving range, electrical battery energy consumption should be minimized. Vapor-compression refrigeration systems currently employed in EVs for climate control consume a significant fraction of the battery charge. Thus, by replacing this traditional heating ventilation and air-conditioning system with an adsorption based climate control system one can have the capability of increasing the drive range of EVs.The Advanced Thermo-adsorptive Battery (ATB) for climate control is a water-based adsorption type refrigeration cycle. An essential component of the ATB is a low pressure evaporator/condenser unit (ECU) which facilitates both the evaporation and condensation processes. The thermal design of the ECU relies predominantly on the accurate prediction of evaporation/boiling heat transfer coefficients since the standard correlations for predicting boiling heat transfer coefficients have large uncertainty at the low operating pressures of the ATB. This work describes the design and development of a low pressure ECU as well as the thermal performance of the actual ECU prototype.

Study on the pressure self-adaptive water-tight junction box in underwater vehicle

Directory of Open Access Journals (Sweden)

Haocai Huang

2012-09-01

Full Text Available Underwater vehicles play a very important role in underwater engineering. Water-tight junction box (WJB is one of the key components in underwater vehicle. This paper puts forward a pressure self-adaptive water-tight junction box (PSAWJB which improves the reliability of the WJB significantly by solving the sealing and pressure problems in conventional WJB design. By redundancy design method, the pressure self-adaptive equalizer (PSAE is designed in such a way that it consists of a piston pressure-adaptive compensator (PPAC and a titanium film pressure-adaptive compensator (TFPAC. According to hydro-mechanical simulations, the operating volume of the PSAE is more than or equal to 11.6 % of the volume of WJB liquid system. Furthermore, the required operating volume of the PSAE also increases as the gas content of oil, hydrostatic pressure or temperature difference increases. The reliability of the PSAWJB is proved by hyperbaric chamber tests.

LINEAR KERNEL SUPPORT VECTOR MACHINES FOR MODELING PORE-WATER PRESSURE RESPONSES

Directory of Open Access Journals (Sweden)

KHAMARUZAMAN W. YUSOF

2017-08-01

Full Text Available Pore-water pressure responses are vital in many aspects of slope management, design and monitoring. Its measurement however, is difficult, expensive and time consuming. Studies on its predictions are lacking. Support vector machines with linear kernel was used here to predict the responses of pore-water pressure to rainfall. Pore-water pressure response data was collected from slope instrumentation program. Support vector machine meta-parameter calibration and model development was carried out using grid search and k-fold cross validation. The mean square error for the model on scaled test data is 0.0015 and the coefficient of determination is 0.9321. Although pore-water pressure response to rainfall is a complex nonlinear process, the use of linear kernel support vector machine can be employed where high accuracy can be sacrificed for computational ease and time.

Steam condensation behavior of high pressure water's blow down directly into water in containment under LOCA

International Nuclear Information System (INIS)

Kusunoki, Tsuyoshi; Ishida, Toshihisa; Yoritsune, Tsutomu; Kasahara, Y.

1995-01-01

JAERI has been conducting a design study of an advanced type Marine Reactor X (MRX) for merchant ships. By employing 'Integral type PWR', In-vessel type control rod drive systems', 'Water filled containment system' and 'Decay heat removal system by natural convection', MRX achieved a compact, light weight and highly safe plant. Experiments on steam condensation behavior of high pressure water's blow down into water have been conducted in order to investigate a major safety issue related to the design decision of 'Water filled containment system'. (author)

“Creative Industries” Strategies in Soviet Lithuania: Packages of Mass Consumption Goods

Directory of Open Access Journals (Sweden)

Eglė Jaškūnienė

2015-07-01

Full Text Available The article explores the Soviet mechanism of including the creative potentials into formation of economical and ideological policy strategies. Research aims to examine, how mass media and culture theories of Walter Benjamin, Frankfurt school and British Culture studies reflect the situation of mass culture in Soviet system. Case study is based on Lithuanian package design of 1960–1970s.

Summary of the contractor information exchange meeting for improving the safety of Soviet-Designed Nuclear Power Plants, February 19, 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

This report summarizes a meeting held on February 19, 1997, in Washington, D.C. The meeting was held primarily to exchange information among the contractors involved in the U.S. Department of Energy`s efforts to improve the safety of Soviet-designed nuclear power plants. Previous meetings have been held on December 5-6, 1995, and May 22, 1996. The meetings are sponsored by the U.S. Department of Energy and coordinated by the Pacific Northwest National Laboratory. The U.S. Department of Energy works with countries to increase the level of safety at 63 Soviet-designed nuclear reactors operating in Armenia, Bulgaria, the Czech Republic, Hungary, Lithuania, Russia, Slovakia, and Ukraine. The work is implemented largely by commercial companies and individuals who provide technologies and services to the countries with Soviet-designed nuclear power plants. Attending the meeting were 71 representatives of commercial contractors, the U.S. Department of Energy, the U.S. Department of State, national laboratories, and other federal agencies. The presentations and discussions that occurred during the exchange are summarized in this report. While this report captures the general presentation and discussion points covered at the meeting, it is not a verbatim, inclusive record. To make the report useful, information presented at the meeting has been expanded to clarify issues, respond to attendees` requests, or place discussion points in a broader programmatic context. Appendixes A through F contain the meeting agenda, list of attendees, copies of presentation visuals and handouts, the Strategy Document discussed at the meeting, and a summary of attendees` post-meeting evaluation comments. As with past information exchanges, the participants found this meeting valuable and useful. In response to the participant`s requests, a fourth information exchange will be held later in 1997.

Summary of the contractor information exchange meeting for improving the safety of Soviet-Designed Nuclear Power Plants, February 19, 1997

International Nuclear Information System (INIS)

1997-04-01

This report summarizes a meeting held on February 19, 1997, in Washington, D.C. The meeting was held primarily to exchange information among the contractors involved in the U.S. Department of Energy's efforts to improve the safety of Soviet-designed nuclear power plants. Previous meetings have been held on December 5-6, 1995, and May 22, 1996. The meetings are sponsored by the U.S. Department of Energy and coordinated by the Pacific Northwest National Laboratory. The U.S. Department of Energy works with countries to increase the level of safety at 63 Soviet-designed nuclear reactors operating in Armenia, Bulgaria, the Czech Republic, Hungary, Lithuania, Russia, Slovakia, and Ukraine. The work is implemented largely by commercial companies and individuals who provide technologies and services to the countries with Soviet-designed nuclear power plants. Attending the meeting were 71 representatives of commercial contractors, the U.S. Department of Energy, the U.S. Department of State, national laboratories, and other federal agencies. The presentations and discussions that occurred during the exchange are summarized in this report. While this report captures the general presentation and discussion points covered at the meeting, it is not a verbatim, inclusive record. To make the report useful, information presented at the meeting has been expanded to clarify issues, respond to attendees' requests, or place discussion points in a broader programmatic context. Appendixes A through F contain the meeting agenda, list of attendees, copies of presentation visuals and handouts, the Strategy Document discussed at the meeting, and a summary of attendees' post-meeting evaluation comments. As with past information exchanges, the participants found this meeting valuable and useful. In response to the participant's requests, a fourth information exchange will be held later in 1997

Scientific research in the Soviet Union

International Nuclear Information System (INIS)

Mtingwa, S.K.

1990-01-01

I report on the scientific aspects of my US/USSR Interacademy Exchange Visit to the Soviet Union. My research was conducted at three different institutes: the Lebedev Physical Institute in Moscow, the Leningrad Nuclear Physics Institute in Gatchina, and the Yerevan Physics Institute in Soviet Armenia. I included relevant information about the Soviet educational system, salaries of Soviet physicists, work habits and research activities at the three institutes, and the relevance of that research to work going on in the United States. 18 refs

SCW Pressure-Channel Nuclear Reactor Some Design Features

Science.gov (United States)

Pioro, Igor L.; Khan, Mosin; Hopps, Victory; Jacobs, Chris; Patkunam, Ruban; Gopaul, Sandeep; Bakan, Kurtulus

Concepts of nuclear reactors cooled with water at supercritical pressures were studied as early as the 1950s and 1960s in the USA and Russia. After a 30-year break, the idea of developing nuclear reactors cooled with SuperCritical Water (SCW) became attractive again as the ultimate development path for water cooling. The main objectives of using SCW in nuclear reactors are: 1) to increase the thermal efficiency of modern Nuclear Power Plants (NPPs) from 30-35% to about 45-48%, and 2) to decrease capital and operational costs and hence decrease electrical energy costs (˜1000 US/kW or even less). SCW NPPs will have much higher operating parameters compared to modern NPPs (pressure about 25 MPa and outlet temperature up to 625°C), and a simplified flow circuit, in which steam generators, steam dryers, steam separators, etc., can be eliminated. Also, higher SCW temperatures allow direct thermo-chemical production of hydrogen at low cost, due to increased reaction rates. Pressure-tube or pressure-channel SCW nuclear reactor concepts are being developed in Canada and Russia for some time. Some design features of the Canadian concept related to fuel channels are discussed in this paper. The main conclusion is that the development of SCW pressure-tube nuclear reactors is feasible and significant benefits can be expected over other thermal-energy systems.

Frictional pressure drop of high pressure steam-water two-phase flow in internally helical ribbed tubes

International Nuclear Information System (INIS)

Tingkuan, C.; Xuanzheng, C.

1987-01-01

It is well known that the internally helical ribbed tubes are effective in suppressing the dry-out in boiling tubes at high pressures, so they are widely used as furnace water wall tubes in modern large steam power boilers. Design of the boilers requires the data on frictional pressure drop characteristics of the ribbed tubes, but they are not sufficient now. This paper describes the experimental results on the adiabatic frictional pressure drop in both horizontal ribbed tubes with measured mean inside diameter of 11.69 mm and 35.42 mm at high pressure from 10 to 21 MPa, mass flow rate from 350 to 3800 kg/m/sup 2/s and steam quality from 0 to 1 in our high pressure electrically heated water loop. Simultaneously, both smooth tubes under the same conditions for comparison. Based on the tests the correlation for determining the frictional pressure drop of internally ribbed tubes are proposed

Mineral production statistics of the former Soviet Union

International Nuclear Information System (INIS)

Anon.

1993-01-01

Four tables show, for each of the years 1980 to 1991 Soviet oil production, Soviet gas production, Soviet coal production and Soviet steel production. Total figures are given along with a regional breakdown. 4 refs

Simulation of low pressure water hammer

Science.gov (United States)

Himr, D.; Habán, V.

2010-08-01

Numerical solution of water hammer is presented in this paper. The contribution is focused on water hammer in the area of low pressure, which is completely different than high pressure case. Little volume of air and influence of the pipe are assumed in water, which cause sound speed change due to pressure alterations. Computation is compared with experimental measurement.

Lessons learned from the safety assistance program for soviet-designed reactors

International Nuclear Information System (INIS)

Steinberg, N.

1999-01-01

Two examples of nuclear power situation were compared in this conference paper - the situation in Lithuania and the situation in the Ukraine. Based on the examples mentioned, author conclude that the effectiveness of the Multi-National Safety Assistance Program for Soviet -Designed Reactors in a given recipient country does not depend, in practice, on engineering issues. The principal aspects that determine this effectiveness are: first, the level of safety culture in the country, beginning at the Governmental level but also at the level of the senior managers of nuclear power. The other important factor which contributes is the availability of a well-developed national program for upgrading NPP safety. The economical well-being of nuclear power and of the country as a whole also has a major effect on the effectiveness of the western technical assistance programs that are trying to upgrade reactor safety in a particular recipient country. And finally, international community should have well coordinated and well substantiated safety assistance program for specific country

ITER cryostat main chamber and vacuum vessel pressure suppression system design

International Nuclear Information System (INIS)

Ito, Akira; Nakahira, Masataka; Takahashi, Hiroyuki; Tada, Eisuke; Nakashima, Yoshitane; Ueno, Osamu

1999-03-01

Design of Cryostat Main Chamber and Vacuum Vessel Pressure Suppression System (VVPS) of International Thermonuclear Experimental Reactor (ITER) has been conducted. The cryostat is a cylindrical vessel that includes in-vessel component such as vacuum vessel, superconducting toroidal coils and poloidal coils. This cryostat provides the adiabatic vacuum about 10 -4 Pa for the superconducting coils operating at 4 K and forms the second confinement barrier to tritium. The adiabatic vacuum is to reduce thermal loads applied to the superconducting coils and their supports so as to keep their temperature 4 K. The VVPS consists of a suppression tank located under the lower bio-shield and 4 relief pipes to connect the vacuum vessel and the suppression tank. The VVPS is to keep the maximum pressure rise of the vacuum vessel below the design value of 0.5 MPa in case of the in-vessel LOCA (water spillage from in-vessel component). The spilled water and steam are lead to the suppression tank through the relief pipes when the internal pressure of vacuum vessel is over 0.2 MPa, and then the internal pressure is kept below 0.5 MPa. This report summarizes the structural design of the cryostat main chamber and pressure suppression system, together with their fabrication and installation. (author)

ITER cryostat main chamber and vacuum vessel pressure suppression system design

Energy Technology Data Exchange (ETDEWEB)

Ito, Akira; Nakahira, Masataka; Takahashi, Hiroyuki; Tada, Eisuke [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Nakashima, Yoshitane; Ueno, Osamu

1999-03-01

Design of Cryostat Main Chamber and Vacuum Vessel Pressure Suppression System (VVPS) of International Thermonuclear Experimental Reactor (ITER) has been conducted. The cryostat is a cylindrical vessel that includes in-vessel component such as vacuum vessel, superconducting toroidal coils and poloidal coils. This cryostat provides the adiabatic vacuum about 10{sup -4} Pa for the superconducting coils operating at 4 K and forms the second confinement barrier to tritium. The adiabatic vacuum is to reduce thermal loads applied to the superconducting coils and their supports so as to keep their temperature 4 K. The VVPS consists of a suppression tank located under the lower bio-shield and 4 relief pipes to connect the vacuum vessel and the suppression tank. The VVPS is to keep the maximum pressure rise of the vacuum vessel below the design value of 0.5 MPa in case of the in-vessel LOCA (water spillage from in-vessel component). The spilled water and steam are lead to the suppression tank through the relief pipes when the internal pressure of vacuum vessel is over 0.2 MPa, and then the internal pressure is kept below 0.5 MPa. This report summarizes the structural design of the cryostat main chamber and pressure suppression system, together with their fabrication and installation. (author)

Soviet New Thinking: Perspectives and Implications

Science.gov (United States)

1990-03-29

and leading military theorist, as quoted in Steven P. Adragna , "A New Soviet Military? Doctrine and Strategy", Orbis, Spring, 1989, p. 166. 22... Adragna , pp. 166-68. 22. Soviet Battlefield Development Plan. Vol I: Soviet General Doctrine for War, p.1-8. 24. Goure, pp. 36-37. 25. William E. Odom

Optimization of core reload design for low-leakage fuel management in pressurized water reactors

International Nuclear Information System (INIS)

Kim, Y.J.; Downar, T.J.; Sesonske, A.

1987-01-01

A method was developed to optimize pressurized water reactor low-leakage core reload designs that features the decoupling and sequential optimization of the fuel arrangement and control problems. The two-stage optimization process provides the maximum cycle length for a given fresh fuel loading subject to power peaking constraints. In the first stage, a best fuel arrangement is determined at the end of cycle (EOC) in the absence of all control poisons by employing a direct search method. The constant power, Haling depletion is used to provide the cycle length and EOC power peaking for each candidate core fuel arrangement. In the second stage, the core control poison requirements to meet the core peaking constraints throughout the cycle are determined using an approximate nonlinear programming technique

Identity and Othering in Past and Present: Representations of the Soviet Era in Estonian Post-Soviet Textbooks

Directory of Open Access Journals (Sweden)

Katrin Kello

2018-02-01

Full Text Available This paper analyses representations of the ‘core Soviet era’ (1945-1985 in Estonian post-Soviet history textbooks (1989-2016. Attitudes towards the Soviet system have been a rich resource for identity building, and hence a powerful political tool across the whole of the post-Soviet block. Based on an analysis of sections about the Soviet era in Estonia in 21 textbooks, the paper takes a look at how textbooks reflect broader processes of social meaning making, identity building and othering after a profound social and political turn. In 1989 and during the early 1990s, perspectives and narratives in Estonian history textbooks were closely related to social memory and national politics, enacting a specific social representation of the Soviet era that dominated the Estonian-speaking public space during the 1990s. The Soviet era, Russia and local Russians became the main Others for Estonia and Estonians. Over time, public discourse has diversified. The national curriculum and textbooks, however, still maintain the canon that formed in 1990s and thus reflect earlier sentiments. Apart from the increasing salience of Soviet-era daily life in more recent textbooks, the thematic choices and emphases have changed little since the 1990s. Therefore, even if the style of writing has ‘cooled down’, issues of identity preservation, resistance and accommodation, together with a saliently negative representation of wrongdoings by the Soviet system, still prevail. On the one hand, this testifies to the resilience of an established tradition in the textbook genre in general. On the other hand, it reflects the dominance of an ethnocentric tradition in Estonian history textbook writing. The paper discusses the implications of these findings for interethnic relations in Estonia.

Flashing of high-pressure saturated water into the pool water

International Nuclear Information System (INIS)

Takamasa, Tomoji; Kondo, Koichi; Aya, Izuo.

1997-01-01

This paper presents an experimental study on a saturated high-pressure water discharging into a water pool. The purpose of the experiment is to clarify the phenomena that occur by a blow-down of the water from the pressure vessel into the water-filled containment in the case of a wall-crack accident or a LOCA in a passive safety reactor. The results show that a flashing oscillation (FO) occurs when the water discharges into the pool, under specified experimental conditions. The range of the flashing location oscillates between a point very close to and some distance away from the vent hole. The pressures in the vent tube and water pool constantly fluctuate due to the flashing oscillation. The pressure oscillation and alternating flashing location might be caused by the balancing action between the supply of saturated water, flashing at the control volume and steam condensation on the steam-water interface. The frequencies of FO, or frequencies of pressure oscillation and alternating flashing location, increased as water subcooling increased, and as discharging pressure and vent hole diameter decreased. A linear analysis was conducted using a spherical flashing bubble model in which the motion of bubble is controlled by steam condensation. The effects of these parameters on the period of FO in the experiments can be predicted well by the analysis. (author)

The Soviet center of astronomical data

International Nuclear Information System (INIS)

Dluzhnevskaya, O.B.

1982-01-01

On the basis of the current French-Soviet cooperation in science and technology, the Astronomical Council of the U.S.S.R. Academy of Sciences and the Strasbourg Center signed in 1977 an agreement on setting up the Soviet Center of Astronomical Data as its filial branch. The Soviet Center was created on the basis of a computation center at the Zvenigorod station of the Astronomical Council of the U.S.S.R. Academy of Sciences, which had already had considerable experience of working with stellar catalogues. In 1979 the Center was equipped with a EC-1033 computer. In 1978-1979 the Soviet Center of Astronomical Data (C.A.D.) received from Strasbourg 96 of the most important catalogues. By September 1981 the list of catalogues available at the Soviet Center has reached 140 catalogues some of which are described. (Auth.)

AUTOLOAD, an automatic optimal pressurized water reactor reload design system with an expert module

International Nuclear Information System (INIS)

Li, Z.; Levine, S.H.

1994-01-01

An automatic optimal pressurized water reactor (PWR) reload design expert system AUTOLOAD has been developed. It employs two important new techniques. The first is a new loading priority scheme that defines the optimal placement of the fuel in the core that has the maximum end-of-cycle state k eff . The second is a new power-shape-driven progressive iteration method for automatically determining the burnable poison (BP) loading in the fresh fuel assemblies. The Haling power distribution is used in converting the theoretically optimal solution into the practical design, which meets the design constraints for the given fuel assemblies. AUTOLOAD is a combination of C and FORTRAN languages. It requires only the required cycle length, the maximum peak normalized power, the BP type, the number of fresh fuel assemblies, the assembly burnup, and BP histories of the available fuel assemblies as its input. Knowledge-based modules have been built into the expert system computer code to perform all of the tasks involved in reloading a PWR. AUTOLOAD takes only ∼ 30 CPU min on an IBM 3090 600s mainframe to accomplish a practical reload design. A maximum of 12.5% fresh fuel enrichment saving is observed compared with the core used by the utility

Risk and Soviet Security Decisions

National Research Council Canada - National Science Library

Hull, Andrew

1990-01-01

.... There are several exceptions to general Soviet risk aversion in using military power. But in each instance, the Soviet Union has fared rather badly when it chanced large risks in pursuit of correspondingly high potential gains...

Physical protection design and analysis training for the former Soviet Union

International Nuclear Information System (INIS)

Soo Hoo, M.S.; Chapek, J.F.; Ebel, P.E.

1996-01-01

Since 1978, Sandia National Laboratories has provided training courses in the systematic design of Physical Protection Systems (PPS). One such course, the International Training Course (TC) on the Physical Protection of Nuclear Facilities and Materials, is sponsored by the Department of Energy's International Safeguards Division , the International Atomic Energy Agency, and the Department of State. Since 1978, twelve 3- and 4-week classes have been conducted by Sandia for these sponsors. One- and two-week adaptations of this course have been developed for other customers, and, since 1994, nine of these abbreviated courses have been presented in the Russian language to participants from the Former Soviet Union (SU). These courses have been performed in support of the Department of Energy's program on Material Protection, Control and Accounting (MPC ampersand A) for the Russian Federation and the Newly Independent States. MPC ampersand A physical protection training assumes participants have more narrowly defined backgrounds. In using affective approaches, the overall goal of training in the context of the MPC ampersand A Program is to develop modern and effective, indigenous capabilities for physical protection system design and analysis within the SU. This paper contrasts the cognitive and affective approaches to training and indicates why different approaches are required for the ITC and the MPC ampersand A Programs

Kimchi, seaweed, and seasoned carrot in the Soviet culinary culture: the spread of Korean food in the Soviet Union and Korean diaspora

Directory of Open Access Journals (Sweden)

Changzoo Song

2016-03-01

Full Text Available The half-million Soviet Koreans (or Koryŏ saram in the former Soviet Union are the descendants of the ethnic Koreans who migrated to the Russian Far East in the late 19th and early 20th centuries from the northern parts of the Korean peninsula. Their settlements were established in the wide areas of the Russian Far East, including the urban areas around Vladivostok. They were, however, forced-migrated to Central Asia in late 1937 under Stalin's rule. From Central Asia, these Soviet Koreans were further dispersed to other parts of the Soviet Union in the post-Stalin era. These multiple dispersions of Soviet Koreans not only transformed their culinary habit, but also helped Korean food spread among the peoples of the Soviet Union. As a result, Korean food, such as kimchi, miyŏk (edible kelp, and others, were introduced and widely consumed throughout the Soviet Union. This paper explores this unusual spread and popularity of Korean food in the Soviet Union, focusing on the migration history of the Soviet Koreans and Soviet culinary culture. This work is based on the author's fieldwork in the Soviet Union in the early 1900s and again in mid-2000s. The unusual diffusion and popularity of the Korean food in the former Soviet Union provides us with important insights on migration and globalization of ethnic food.

Water cycle and its management for plant habitats at reduced pressures

Science.gov (United States)

Rygalov, Vadim Y.; Fowler, Philip A.; Wheeler, Raymond M.; Bucklin, Ray A.

2004-01-01

Experimental and mathematical models were developed for describing and testing temperature and humidity parameters for plant production in bioregenerative life support systems. A factor was included for analyzing systems operating at low (10-101.3 kPa) pressure to reduce gas leakage and structural mass (e.g., inflatable greenhouses for space application). The expected close relationship between temperature and relative humidity was observed, along with the importance of heat exchanger coil temperature and air circulation rate. The presence of plants in closed habitats results in increased water flux through the system. Changes in pressure affect gas diffusion rates and surface boundary layers, and change convective transfer capabilities and water evaporation rates. A consistent observation from studies with plants at reduced pressures is increased evapotranspiration rates, even at constant vapor pressure deficits. This suggests that plant water status is a critical factor for managing low-pressure production systems. The approach suggested should help space mission planners design artificial environments in closed habitats.

The politics of Soviet strategic defense: Political strategies, organization politics, and Soviet strategic thought. (Volumes I and II)

International Nuclear Information System (INIS)

Kaufman, S.J.

1991-01-01

This study formulates three different unitary rational-actor models and an organizational model that can be used to explain Soviet policy in strategic defense from 1966-1980, then tests the models to determine which most successfully explains Soviet behavior. The only rational-actor model that can explain the Soviet force posture for air defense relies on demonstrably false assumptions. A well-formulated organizational model can explain these facts, as well as some organizational pathologies shown by the Soviet National Air Defense Forces. The findings suggest that military services, even when ostensibly closely directed by civilian and military superiors, often manage to pursue their own interests rather than the requirements of higher policy. Soviet civilian leaders generally had limited control over the formulation of military doctrine or over the force posture of Soviet military services, but arms control (especially the ABM Treaty) offered a policy handle which helped them to affect doctrine and force posture to a substantial degree

Soviet science

International Nuclear Information System (INIS)

Medvedev, Z.A.

1979-01-01

In this brief history of science in the Soviet Union the emphasis is on the interaction between scientific and technological developments and the political objectives of the Soviet government Reference is made to the development of nuclear energy for military and for peaceful purposes. In an appendix, a rather detailed account is given of a 'nuclear disaster in the South Urals area'; reference is made to ecological, genetic and population researches in the areas contaminated by long-lived products of radioactive waste (e.g. Sr-90 and Cs-137). Section headings are: lakes; mammals; population genetics and radiation genetics (covering plants, animals and soil activity). (U.K.)

Soviet Nuclear Strategy form Stalin to Gorbachev

International Nuclear Information System (INIS)

Catudal, H.M.

1989-01-01

This book examines the nature of the Soviet nuclear threat and how it has evolved over the years. Too often in the past U.S. officials, in shaping and directing plans for American nuclear forces, have tended to see Soviet military forces and strategy as a reflection of their own stance or simply as projecting the worst plausible case of Soviet intentions and capabilities. The result has been a distorted if not dangerous portrayal of the real threat. Soviet nuclear strategy, as explained in this detailed book, has evolved significantly since the days when the Soviets first possessed nuclear weapons under Joseph Stalin. Today there is in development a new Soviet military and strategic doctrine reflected in Gorbachev's words, We require a radical break with traditions of political thinking. This new doctrine promises to have a profound impact on European security and the overall East-West relationship

Analysis of quench-vent pressures for present design of ITER [International Thermonuclear Experimental Reactor] TF [toroidal field] coils

International Nuclear Information System (INIS)

Slack, D.S.

1989-01-01

The International Thermonuclear Experimental Reactor (ITER) is a new tokamak design project with joint participation from Japan, the European Community, the Union of the Soviet Union, and the United States. This paper examines the effects of a quench within the toroidal field (TF) coils based on current ITER design. It is a preliminary, rough analysis. Its intent is to assist ITER designers while more accurate computer codes are being developed and to provide a check against these more rigorous solutions. Rigorous solutions to the quench problem are very complex involving three-dimensional heat transfer, extreme changes in heat capacities and copper resistivity, and varying flow dynamics within the conductors. This analysis addresses all these factors in an approximate way. The result is much less accurate than a rigorous analysis. Results here could be in error as much as 30 to 40 percent. However, it is believed that this paper can still be very useful to the coil designer. Coil pressures and temperatures vs time into a quench are presented. Rate of helium vent, energy deposition in the coil, and depletion of magnetic stored energy are also presented. Peak pressures are high (about 43 MPa). This is due to the very long vent path length (446 m), small hydraulic diameters, and high current densities associated with ITER's cable-in-conduit design. The effects of these pressures as well as the ability of the coil to be self protecting during a quench are discussed. 3 refs., 3 figs., 1 tab

Pressurized-water reactors

International Nuclear Information System (INIS)

Bush, S.H.

1983-03-01

An overview of the pressurized-water reactor (PWR) pressure boundary problems is presented. Specifically exempted will be discussions of problems with pumps, valves and steam generators on the basis that they will be covered in other papers. Pressure boundary reliability is examined in the context of real or perceived problems occurring over the past 5 to 6 years since the last IAEA Reliability Symposium. Issues explicitly covered will include the status of the pressurized thermal-shock problem, reliability of inservice inspections with emphasis on examination of the region immediately under the reactor pressure vessel (RPV) cladding, history of piping failures with emphasis on failure modes and mechanisms. Since nondestructive examination is the topic of one session, discussion will be limited to results rather than techniques

Development of plant dynamic analysis code for integrated self-pressurized water reactor (ISPDYN), and comparative study of pressure control methods

International Nuclear Information System (INIS)

Kusunoki, Tsuyoshi; Yokomura, Takeyoshi; Nabeshima, Kunihiko; Shimazaki, Junya; Shinohara, Yoshikuni.

1988-01-01

This report describes the development of plant dynamic analysis code (ISPDYN) for integrated self-pressurized water reactor, and comparative study of pressure control methods with this code. ISPDYN is developed for integrated self-pressurized water reactor, one of the trial design by JAERI. In the transient responses, the calculated results by ISPDYN are in good agreement with the DRUCK calculations. In addition, this report presents some sensitivity studies for selected cases. Computing time of this code is very short so as about one fifth of real time. The comparative study of self-pressurized system with forced-pressurized system by this code, for rapid load decrease and increase cases, has provided useful informations. (author)

Core design concepts for high performance light water reactors

International Nuclear Information System (INIS)

Schulenberg, T.; Starflinger, J.

2007-01-01

Light water reactors operated under supercritical pressure conditions have been selected as one of the promising future reactor concepts to be studied by the Generation IV International Forum. Whereas the steam cycle of such reactors can be derived from modern fossil fired power plants, the reactor itself, and in particular the reactor core, still need to be developed. Different core design concepts shall be described here to outline the strategy. A first option for near future applications is a pressurized water reactor with 380 .deg. C core exit temperature, having a closed primary loop and achieving 2% pts. higher net efficiency and 24% higher specific turbine power than latest pressurized water reactors. More efficiency and turbine power can be gained from core exit temperatures around 500 .deg. C, which require a multi step heat up process in the core with intermediate coolant mixing, achieving up to 44% net efficiency. The paper summarizes different core and assembly design approaches which have been studied recently for such High Performance Light Water Reactors

Soviet satellite communications science and technology

Energy Technology Data Exchange (ETDEWEB)

Birch, J.N.; Campanella, S.J.; Gordon, G.D.; McElroy, D.R.; Pritchard, W.L.; Stamminger, R.

1991-08-01

This is a report by six US scientists and engineers concerning the current state of the art and projections of future Soviet satellite communications technologies. The panel members are experts in satellite stabilization, spacecraft environments, space power generation, launch systems, spacecraft communications sciences and technologies, onboard processing, ground stations, and other technologies that impact communications. The panel assessed the Soviet ability to support high-data-rate space missions at 128 Mbps by evaluating current and projected Soviet satellite communications technologies. A variety of space missions were considered, including Earth-to-Earth communications via satellites in geostationary or highly elliptical orbits, those missions that require space-to-Earth communications via a direct path and those missions that require space-to-Earth communications via a relay satellite. Soviet satellite communications capability, in most cases, is 10 years behind that of the United States and other industrialized nations. However, based upon an analysis of communications links needed to support these missions using current Soviet capabilities, it is well within the current Soviet technology to support certain space missions outlined above at rates of 128 Mbps or higher, although published literature clearly shows that the Soviet Union has not exceeded 60 Mbps in its current space system. These analyses are necessary but not sufficient to determine mission data rates, and other technologies such as onboard processing and storage could limit the mission data rate well below that which could actually be supported via the communications links. Presently, the Soviet Union appears to be content with data rates in the low-Earth-orbit relay via geostationary mode of 12 Mbps. This limit is a direct result of power amplifier limits, spacecraft antenna size, and the utilization of K{sub u}-band frequencies. 91 refs., 16 figs., 15 tabs.

Applying risk insights in US NRC reviews of integral pressurized water reactor designs

International Nuclear Information System (INIS)

Caruso, M.A.; Hilsmeier, T.; Kevern, T.A.

2012-01-01

In its Staff Requirements Memorandum (SRM) on COMGBJ-10-0004/COMGEA-10-0001, 'Use of Risk Insights to Enhance Safety Focus of Small Modular Reactor Reviews,' dated August 31, 2010 (ML102510405), the U.S. Nuclear Regulatory Commission (NRC) directed the NRC staff to more fully integrate the use of risk insights into pre-application activities and the review of small modular reactor (SMR) applications with near-term focus on integral pressurized water reactor (iPWR) designs. The Commission's objective is to align the review focus and resources with the risk-significant systems, structures, and components (SSCs) and other aspects of the design, that contribute most to safety in order to enhance the efficiency of the review process while still enabling a decision of reasonable assurance of the design's safety. The staff was directed to develop a design-specific, risk-informed review plan for each SMR to address pre-application and application review activities. The NRC staff submitted a response to the Commission which describes its approach for (1) using risk insights, consistent with current regulatory requirements, to assign SSCs to one of a limited set of graded categories, and (2) adjusting the scope and depth of current review plans--where possible--consistent with regulatory requirements and consistent with the applicable graded category. Because the staff's review constitutes an independent audit of the application, the staff may emphasize or de-emphasize particular aspects of its review guidance (i.e., Standard Review Plan), as appropriate and consistent with regulatory requirements, for the application being reviewed. The staff may propose justifications for not performing certain sections of the reviews called for by the applicable review plan. Examples of acceptable variations in the scope of a review can include reduced emphasis on SSC attributes such as reliability, availability, or functional performance when the SSC will be in the scope of a program

On Ideology, Language, and Identity: Language Politics in the Soviet and Post-Soviet Lithuania

Science.gov (United States)

Balockaite, Rasa

2014-01-01

The paper illuminates links between state politics and language politics in Lithuania during different historical periods: (a) the thaw period, (b) the stagnation period, (c) the liberalization periods of Soviet socialism, and (d) the two post-Soviet decades characterized by both nationalism and liberalization. Based on analysis of the texts by…

Critical Design Issues of Tokamak Cooling Water System of ITER's Fusion Reactor

International Nuclear Information System (INIS)

Kim, Seokho H.; Berry, Jan

2011-01-01

U.S. ITER is responsible for the design, engineering, and procurement of the Tokamak Cooling Water System (TCWS). The TCWS transfers heat generated in the Tokamak to cooling water during nominal pulsed operation 850 MW at up to 150 C and 4.2 MPa water pressure. This water contains radionuclides because impurities (e.g., tritium) diffuse from in-vessel components and the vacuum vessel by water baking at 200 240 C at up to 4.4MPa, and corrosion products become activated by neutron bombardment. The system is designated as safety important class (SIC) and will be fabricated to comply with the French Order concerning nuclear pressure equipment (December 2005) and the EU Pressure Equipment Directive using ASME Section VIII, Div 2 design codes. The complexity of the TCWS design and fabrication presents unique challenges. Conceptual design of this one-of-a-kind cooling system has been completed with several issues that need to be resolved to move to next stage of the design. Those issues include flow balancing between over hundreds of branch pipelines in parallel to supply cooling water to blankets, determination of optimum flow velocity while minimizing the potential for cavitation damage, design for freezing protection for cooling water flowing through cryostat (freezing) environment, requirements for high-energy piping design, and electromagnetic impact to piping and components. Although the TCWS consists of standard commercial components such as piping with valves and fittings, heat exchangers, and pumps, complex requirements present interesting design challenges. This paper presents a brief description of TCWS conceptual design and critical design issues that need to be resolved.

Design and analysis of hydraulic ram water pumping system

Science.gov (United States)

Hussin, N. S. M.; Gamil, S. A.; Amin, N. A. M.; Safar, M. J. A.; Majid, M. S. A.; Kazim, M. N. F. M.; Nasir, N. F. M.

2017-10-01

The current pumping system (DC water pump) for agriculture is powered by household electricity, therefore, the cost of electricity will be increased due to the higher electricity consumption. In addition, the water needs to be supplied at different height of trees and different places that are far from the water source. The existing DC water pump can pump the water to 1.5 m height but it cost money for electrical source. The hydraulic ram is a mechanical water pump that suitable used for agriculture purpose. It can be a good substitute for DC water pump in agriculture use. The hydraulic ram water pumping system has ability to pump water using gravitational energy or the kinetic energy through flowing source of water. This project aims to analyze and develop the water ram pump in order to meet the desired delivery head up to 3 meter height with less operation cost. The hydraulic ram is designed using CATIA software. Simulation work has been done using ANSYS CFX software to validate the working concept. There are three design were tested in the experiment study. The best design reached target head of 3 m with 15% efficiency and flow rate of 11.82l/min. The results from this study show that the less diameter of pressure chamber and higher supply head will create higher pressure.

On-off controller for installation to test the pressurized water reactor material

International Nuclear Information System (INIS)

Zauq, M.H.

1982-05-01

This report describes the design of an ON-OFF controller based on the 6800 microprocessor in its assembly language and its interfacing with its environment (sensors, periphery, etc). The controller is meant to control the temperature and the pressure inside an experimental chamber in which the material under test is placed. The ''Design basis accident'' conditions (e.g., LOCA) for a pressurized water reactor are simulated in the experimental chamber [fr

Automated corrosion fatigue crack growth testing in pressurized water environments

International Nuclear Information System (INIS)

Ceschini, L.J.; Liaw, P.K.; Rudd, G.E.; Logsdon, W.A.

1984-01-01

This paper describes in detail a novel approach to construct a test facility for developing corrosion fatigue crack growth rate (FCGR) properties in aggressive environments. The environment studied is that of a pressurized water reactor (PWR) at 288 0 C (550 0 F) and 13.8 MPa (200 psig). To expedite data generation, each chamber was designed to accommodate two test specimens. A common water recirculation and pressurization system was employed to service two test chambers. Thus, four fatigue crack propagation rate tests could be conducted simultaneously in the pressurized water environment. The data analysis was automated to minimize the typically high labor costs associated with corrosion fatigue crack propagation testing. Verification FCGR tests conducted on an ASTM A469 rotor steel in a room temperature air environment as well as actual PWR environment FCGR tests performed on an ASTM A533 Grade B Class 2 pressure vessel steel demonstrated that the dual specimen test facility is an excellent system for developing the FCGR properties of materials in adverse environments

JPRS Report. Soviet Union: Political Affairs.

Science.gov (United States)

1990-07-10

Soviets? The absurdity of a classified dissertation in pedagogy is intensified by the additional fact that given the truly impoverished posi- tion in...Khakass. These are our Soviet kids , the graduates of our Soviet schools. Together, they listen to the same lectures as the people their own age who...4,267. They are in training at 12 VUZs, 8 technical schools, and one professional- technical college. Four boarding schools have admitted Afghan kids

Pressurized-water-reactor station blackout

International Nuclear Information System (INIS)

Dobbe, C.A.

1983-01-01

The purpose of the Severe Accident Sequence Analysis (SASA) Program was to investigate accident scenarios beyond the design basis. The primary objective of SASA was to analyze nuclear plant transients that could lead to partial or total core melt and evaluate potential mitigating actions. The following summarizes the pressurized water reactor (PWR) SASA effort at the Idaho National Engineering Laboratory (INEL). The INEL is presently evaluating Unresolved Safety Issue A-44 - Station Blackout from initiation of the transient to core uncovery. The balance of the analysis from core uncovery until fission product release is being performed at Sandia National Laboratory (SNL). The current analyses involve the Bellefonte Nuclear Steam Supply System (NSSS), a Babcock and Wilcox (B and W) 205 Fuel Assembly (205-FA) raised loop design to be operated by the Tennessee Valley Authority

United States Department of Energy's reactor core protection evaluation methodology for fires at RBMK and VVER nuclear power plants. Revision 1

International Nuclear Information System (INIS)

1997-06-01

This document provides operators of Soviet-designed RBMK (graphite moderated light water boiling water reactor) and VVER (pressurized light water reactor) nuclear power plants with a systematic Methodology to qualitatively evaluate plant response to fires and to identify remedies to protect the reactor core from fire-initiated damage

Soviet Cybernetics: Recent News Items, Number Thirteen.

Science.gov (United States)

Holland, Wade B.

An issue of "Soviet Cybernetics: Recent News Items" consists of English translations of the leading recent Soviet contributions to the study of cybernetics. Articles deal with cybernetics in the 21st Century; the Soviet State Committee on Science and Technology; economic reforms in Rudnev's ministry; an interview with Rudnev; Dnepr-2; Dnepr-2…

Agreement of 27 September 1988 between the International Atomic Energy Agency and the Government of India for the application of safeguards in connection with the supply of a nuclear power station from the Union of Soviet Socialist Republics

International Nuclear Information System (INIS)

1989-01-01

The full text of the Agreement of 27 September 1988 between the Agency and the Government of India for the application of safeguards in connection with the supply of a nuclear power station composed of two pressurized light water reactors, each of 1000 MW(e) from the Union of Soviet Socialist Republics is reproduced

Esthetic Education in Soviet Schools.

Science.gov (United States)

Soviet Education, 1980

1980-01-01

This issue of Soviet Education examines esthetic education in Soviet schools, including ways of raising the level of esthetic education, the factor of labor, research on the relationship between the atheistic and esthetic education, ways of amplifying interrelationship between theory and practice in teacher education and psychological principles…

Review of possible peaceful applications of nuclear explosions in the national economy of the Soviet Union

International Nuclear Information System (INIS)

Witherspoon, Paul A.

1970-01-01

The following review will give some of the current thinking of Soviet scientists and engineers on the possibilities of using nuclear explosions for peaceful purposes in the Soviet Union. This review is taken from a more detailed report that was presented under the same title by Soviet participants at an information-exchange meeting that was held in Vienna between the Soviet Union and the United States in April, 1969. Aside from a very brief review of one explosion in salt, the report does not give details on nuclear explosion effects (mechanical, seismic, radiation, or thermal). Rather, the report summarizes the results of design calculations and indicates the direction of Soviet planning for a variety of industrial applications. A complete translation of this report will be published by the Division of Technical Information and Education of AEC at Oakridge. (author)

Review of possible peaceful applications of nuclear explosions in the national economy of the Soviet Union

Energy Technology Data Exchange (ETDEWEB)

Witherspoon, Paul A [University of California, Berkeley (United States)

1970-05-15

The following review will give some of the current thinking of Soviet scientists and engineers on the possibilities of using nuclear explosions for peaceful purposes in the Soviet Union. This review is taken from a more detailed report that was presented under the same title by Soviet participants at an information-exchange meeting that was held in Vienna between the Soviet Union and the United States in April, 1969. Aside from a very brief review of one explosion in salt, the report does not give details on nuclear explosion effects (mechanical, seismic, radiation, or thermal). Rather, the report summarizes the results of design calculations and indicates the direction of Soviet planning for a variety of industrial applications. A complete translation of this report will be published by the Division of Technical Information and Education of AEC at Oakridge. (author)

BWR [boiling-water reactor] and PWR [pressurized-water reactor] off-normal event descriptions

International Nuclear Information System (INIS)

1987-11-01

This document chronicles a total of 87 reactor event descriptions for use by operator licensing examiners in the construction of simulator scenarios. Events are organized into four categories: (1) boiling-water reactor abnormal events; (2) boiling-water reactor emergency events; (3) pressurized-water reactor abnormal events; and (4) pressurized-water reactor emergency events. Each event described includes a cover sheet and a progression of operator actions flow chart. The cover sheet contains the following general information: initial plant state, sequence initiator, important plant parameters, major plant systems affected, tolerance ranges, final plant state, and competencies tested. The progression of operator actions flow chart depicts, in a flow chart manner, the representative sequence(s) of expected immediate and subsequent candidate actions, including communications, that can be observed during the event. These descriptions are intended to provide examiners with a reliable, performance-based source of information from which to design simulator scenarios that will provide a valid test of the candidates' ability to safely and competently perform all licensed duties and responsibilities

Perestroika, Soviet oil, and joint ventures

International Nuclear Information System (INIS)

Churkin, M. Jr.

1991-01-01

Glaznost, the freedom of expression in both the public and private sectors of the Soviet Union, has rapidly transformed the country form a largely isolated and closed society to one that is rapidly becoming more cosmopolitan and open to the West. Now that the Soviet Union is moving toward a free-market economy, a number of new laws are being generated to create a favorable environment for Western investment, especially joint ventures. First, crude oil sales have provided over 75% of much-needed hard currency, and oil has been the principal barter for manufactured goods produced in eastern Europe. Second, joint oil ventures with Western companies can reverse declining production levels and provide sufficient stimulus to turn around the economic recession. The Soviet Union has a very large inventory of discovered but undeveloped oil and gas fields. Most of these fields are difficult for the Soviets to produce technically, financially, and environmentally safely, and they are actively seeking appropriate Western partners. From an exploration point of view, the Soviet Union has probably the largest number of undrilled and highly prospective oil basins, which may replenish declining reserves in the West. Finally, the Soviet Union represents in the long term a large unsaturated market eager to absorb the surplus of goods and services in the Western world. Again, joint oil ventures could provide the convertible currency to increase East-West trade

Design of a water-powered DTH hammer for deep drilling application

Science.gov (United States)

Cho, Min Jae; Kim, Donguk; Oh, Joo Young; Yook, Se-Jin; Kim, Young Won

2017-11-01

A DTH (Down-the-hole) hammer powered by highly pressurized fluid is a drilling tool using the motion of percussion of a drill bit. In retrospect, a DTH by using compressed air as a power source has been widely used in drilling industries such as applications of mining, geothermal etc. On the other hand, another type of a DTH that uses pressurized water, called a water hammer, has recently seen deep drilling applications, while it has been rarely investigated. In this study, we designed a water-powered DTH hammer which mainly consists of several components such as a piston, a poppet valve, a cap and a bit for deep drilling applications. We optimized the components of the hammer on the basis of the results of 1D analysis using commercial software of AMESIM. An experimental study has been also conducted to investigate a performance of the designed water hammer. We measured a pressure distribution inside the hammer system as a function of time, and it thus estimates a frequency of impaction of the bit, which has been also analyzed in frequency domain. In addition, some important parameters have been discussed in conjunction with a limitation of impaction frequency as input pressure. We believe that this study provides design rules of a water-based DTH for deep drilling applications. This work is supported by KITECH of Korean government.

The Origins of Soviet Sociolinguistics.

Science.gov (United States)

Brandist, Craig

2003-01-01

Discusses the origins of Soviet sociolinguistics and suggests that the historical significance of the reception and reinterpretation of these ideas is considerable, leading to a reconsideration of the origins of sociolinguistics and the relationship between Marxism and the language sciences in the early years of the Soviet Union. (Author/VWL)

Evaluation of water cooled supersonic temperature and pressure probes for application to 1366 K flows

Science.gov (United States)

Lagen, Nicholas; Seiner, John M.

1990-01-01

Water cooled supersonic probes are developed to investigate total pressure, static pressure, and total temperature in high-temperature jet plumes and thereby determine the mean flow properties. Two probe concepts, designed for operation at up to 1366 K in a Mach 2 flow, are tested on a water cooled nozzle. The two probe designs - the unsymmetric four-tube cooling configuration and the symmetric annular cooling design - take measurements at 755, 1089, and 1366 K of the three parameters. The cooled total and static pressure readings are found to agree with previous test results with uncooled configurations. The total-temperature probe, however, is affected by the introduction of water coolant, and effect which is explained by the increased heat transfer across the thermocouple-bead surface. Further investigation of the effect of coolant on the temperature probe is proposed to mitigate the effect and calculate more accurate temperatures in jet plumes.

Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) are compared

International Nuclear Information System (INIS)

Greneche, D.

2014-01-01

This article compares the 2 types of light water reactors that are used to produce electricity: the Pressurized Water Reactor (PWR) and the Boiling Water Reactor (BWR). Historically the BWR concept was developed after the PWR concept. Today 80% of light water reactors operating in the world are of PWR-type. This comparison is comprehensive and detailed. First the main technical features are reviewed and compared: reactor architecture, core and fuel design, reactivity control, reactor vessel, cooling systems and reactor containment. Secondly, various aspects concerning reactor operations like reactor control, fuel management, maintenance, inspections, radiation protection, waste generation and reactor reliability are presented and compared for both reactors. As for the issue of safety, it is highlighted that the accidental situations are too different for the 2 reactors to be compared. The main features of reactor safety are explained for both reactors

Water-Pressure Distribution on Seaplane Float

Science.gov (United States)

Thompson, F L

1929-01-01

The investigation presented in this report was conducted for the purpose of determining the distribution and magnitude of water pressures likely to be experienced on seaplane hulls in service. It consisted of the development and construction of apparatus for recording water pressures lasting one one-hundredth second or longer and of flight tests to determine the water pressures on a UO-1 seaplane float under various conditions of taxiing, taking off, and landing. The apparatus developed was found to operate with satisfactory accuracy and is suitable for flight tests on other seaplanes. The tests on the UO-1 showed that maximum pressures of about 6.5 pounds per square inch occur at the step for the full width of the float bottom. Proceeding forward from the step the maximum pressures decrease in magnitude uniformly toward the bow, and the region of highest pressures narrows toward the keel. Immediately abaft the step the maximum pressures are very small, but increase in magnitude toward the stern and there once reached a value of about 5 pounds per square inch. (author)

Microwave measurements of water vapor partial pressure at high temperatures

International Nuclear Information System (INIS)

Latorre, V.R.

1991-01-01

One of the desired parameters in the Yucca Mountain Project is the capillary pressure of the rock comprising the repository. This parameter is related to the partial pressure of water vapor in the air when in equilibrium with the rock mass. Although there are a number of devices that will measure the relative humidity (directly related to the water vapor partial pressure), they generally will fail at temperatures on the order of 150C. Since thee author has observed borehole temperatures considerably in excess of this value in G-Tunnel at the Nevada Test Site (NTS), a different scheme is required to obtain the desired partial pressure data at higher temperatures. This chapter presents a microwave technique that has been developed to measure water vapor partial pressure in boreholes at temperatures up to 250C. The heart of the system is a microwave coaxial resonator whose resonant frequency is inversely proportional to the square root of the real part of the complex dielectric constant of the medium (air) filling the resonator. The real part of the dielectric constant of air is approximately equal to the square of the refractive index which, in turn, is proportional to the partial pressure of the water vapor in the air. Thus, a microwave resonant cavity can be used to measure changes in the relative humidity or partial pressure of water vapor in the air. Since this type of device is constructed of metal, it is able to withstand very high temperatures. The actual limitation is the temperature limit of the dielectric material in the cable connecting the resonator to its driving and monitoring equipment-an automatic network analyzer in our case. In the following sections, the theory of operation, design, construction, calibration and installation of the microwave diagnostics system is presented. The results and conclusions are also presented, along with suggestions for future work

Soviet Development of Gyrotrons

Science.gov (United States)

1986-05-01

Relationship Type of Device Remarks V, - Vc, anomalous Doppler Capable of 100 percent efficiency, CRM but more cumbersome than Cheren- kov devices V...authors; and discusses inlividual Soviet reseaLc- groups, the basic organizational units responAiLle for the CRM and gyrotron research and development. The...maintained a cCnEistEnt iecord of significant achievements; it has managed to overcome the systenic yeaxness of the Soviet R&C systeg in teimg atle to

Implementation of utilities operation and maintenance experience into the European pressurized water reactor design

International Nuclear Information System (INIS)

Zaiss, W.; Lallier, M.

1999-01-01

Since 1992 Electricite de France EDF and German Utilities GU work together with Nuclear Power International NPI, a subsidiary of Framatome and Siemens, in the development of the future European Pressurized Water Reactor EPR. The EPR is an evolutionary concept, based on the French N4 plants and the German KONVOI plants. From the beginning, experienced operation and maintenance people from the precursor plants participate at the design process. Their experience will lead to a plant, which is not only characterised by low investment costs, but also by good operability, high availability and low operation and maintenance costs. No expensive back-fittings should be necessary after commissioning, to reach these availability and maintenance targets. The utility specialists give design requirements for outage performance, system design, and layout. These design requirements are really determining the system performances, and not what was design basis before. It does not necessarily lead to system increases. Mainly it is a shifting of the emphasis to other items. There are even cases, where the system performances can be reduced. Mostly very small modifications, which are nearly cost neutral when implemented early in the design, have big impact on the further operation. If there are big cost influences, a sound balance between investment and gained availability is made together with the designers. There is very fruitful discussion between designers and operators, which is highly estimated by both sides. In this frame also new, revolutionary ideas are coming up, which are going mostly in the direction of investment cost reduction, without loosing operation freedom. It is the first time in Europe, that designers and operators are working so close together. It is also the first time, that the management and the decision making is dominated by the utilities. (author)

High Pressure Industrial Water Facility

Science.gov (United States)

1992-01-01

In conjunction with Space Shuttle Main Engine testing at Stennis, the Nordberg Water Pumps at the High Pressure Industrial Water Facility provide water for cooling the flame deflectors at the test stands during test firings.

Contribution of water vapor pressure to pressurization of plutonium dioxide storage containers

Science.gov (United States)

Veirs, D. Kirk; Morris, John S.; Spearing, Dane R.

2000-07-01

Pressurization of long-term storage containers filled with materials meeting the US DOE storage standard is of concern.1,2 For example, temperatures within storage containers packaged according to the standard and contained in 9975 shipping packages that are stored in full view of the sun can reach internal temperatures of 250 °C.3 Twenty five grams of water (0.5 wt.%) at 250 °C in the storage container with no other material present would result in a pressure of 412 psia, which is limited by the amount of water. The pressure due to the water can be substantially reduced due to interactions with the stored material. Studies of the adsorption of water by PuO2 and surface interactions of water with PuO2 show that adsorption of 0.5 wt.% of water is feasible under many conditions and probable under high humidity conditions.4,5,6 However, no data are available on the vapor pressure of water over plutonium dioxide containing materials that have been exposed to water.

The choice between two designs for the safety-injection system of a pressurized-water reactor, using probabilistic methods

International Nuclear Information System (INIS)

Villemeur, Alain

1982-01-01

A probabilistic study has been carried out to compare two designs for the safety-injection circuit of a pressurized-water reactor. It appears that unavailability of the circuit after an accident involving loss of coolant decreases little when one moves from a 2-line to a 3-line system. These results are compared with the disadvantages arising from increased redundancy, and in particular the increased cost of the installations. The 2-line circuit appears the optimum one on the basis of cost and reliability criteria. It has been chosen for the 1300-MWe units [fr

Design principles for high–pressure force fields: Aqueous TMAO solutions from ambient to kilobar pressures

Energy Technology Data Exchange (ETDEWEB)

Hölzl, Christoph; Horinek, Dominik, E-mail: dominik.horinek@ur.de [Institut für Physikalische und Theoretische Chemie, Universität Regensburg, 93040 Regensburg (Germany); Kibies, Patrick; Frach, Roland; Kast, Stefan M., E-mail: stefan.kast@tu-dortmund.de [Physikalische Chemie III, Technische Universität Dortmund, 44227 Dortmund (Germany); Imoto, Sho, E-mail: sho.imoto@theochem.rub.de; Marx, Dominik [Lehrstuhl für Theoretische Chemie, Ruhr-Universität Bochum, 44780 Bochum (Germany); Suladze, Saba; Winter, Roland [Physikalische Chemie I, Technische Universität Dortmund, 44227 Dortmund (Germany)

2016-04-14

Accurate force fields are one of the major pillars on which successful molecular dynamics simulations of complex biomolecular processes rest. They have been optimized for ambient conditions, whereas high-pressure simulations become increasingly important in pressure perturbation studies, using pressure as an independent thermodynamic variable. Here, we explore the design of non-polarizable force fields tailored to work well in the realm of kilobar pressures – while avoiding complete reparameterization. Our key is to first compute the pressure-induced electronic and structural response of a solute by combining an integral equation approach to include pressure effects on solvent structure with a quantum-chemical treatment of the solute within the embedded cluster reference interaction site model (EC-RISM) framework. Next, the solute’s response to compression is taken into account by introducing pressure-dependence into selected parameters of a well-established force field. In our proof-of-principle study, the full machinery is applied to N,N,N-trimethylamine-N-oxide (TMAO) in water being a potent osmolyte that counteracts pressure denaturation. EC-RISM theory is shown to describe well the charge redistribution upon compression of TMAO(aq) to 10 kbar, which is then embodied in force field molecular dynamics by pressure-dependent partial charges. The performance of the high pressure force field is assessed by comparing to experimental and ab initio molecular dynamics data. Beyond its broad usefulness for designing non-polarizable force fields for extreme thermodynamic conditions, a good description of the pressure-response of solutions is highly recommended when constructing and validating polarizable force fields.

Design principles for high-pressure force fields: Aqueous TMAO solutions from ambient to kilobar pressures.

Science.gov (United States)

Hölzl, Christoph; Kibies, Patrick; Imoto, Sho; Frach, Roland; Suladze, Saba; Winter, Roland; Marx, Dominik; Horinek, Dominik; Kast, Stefan M

2016-04-14

Accurate force fields are one of the major pillars on which successful molecular dynamics simulations of complex biomolecular processes rest. They have been optimized for ambient conditions, whereas high-pressure simulations become increasingly important in pressure perturbation studies, using pressure as an independent thermodynamic variable. Here, we explore the design of non-polarizable force fields tailored to work well in the realm of kilobar pressures--while avoiding complete reparameterization. Our key is to first compute the pressure-induced electronic and structural response of a solute by combining an integral equation approach to include pressure effects on solvent structure with a quantum-chemical treatment of the solute within the embedded cluster reference interaction site model (EC-RISM) framework. Next, the solute's response to compression is taken into account by introducing pressure-dependence into selected parameters of a well-established force field. In our proof-of-principle study, the full machinery is applied to N,N,N-trimethylamine-N-oxide (TMAO) in water being a potent osmolyte that counteracts pressure denaturation. EC-RISM theory is shown to describe well the charge redistribution upon compression of TMAO(aq) to 10 kbar, which is then embodied in force field molecular dynamics by pressure-dependent partial charges. The performance of the high pressure force field is assessed by comparing to experimental and ab initio molecular dynamics data. Beyond its broad usefulness for designing non-polarizable force fields for extreme thermodynamic conditions, a good description of the pressure-response of solutions is highly recommended when constructing and validating polarizable force fields.

Design principles for high–pressure force fields: Aqueous TMAO solutions from ambient to kilobar pressures

International Nuclear Information System (INIS)

Hölzl, Christoph; Horinek, Dominik; Kibies, Patrick; Frach, Roland; Kast, Stefan M.; Imoto, Sho; Marx, Dominik; Suladze, Saba; Winter, Roland

2016-01-01

Accurate force fields are one of the major pillars on which successful molecular dynamics simulations of complex biomolecular processes rest. They have been optimized for ambient conditions, whereas high-pressure simulations become increasingly important in pressure perturbation studies, using pressure as an independent thermodynamic variable. Here, we explore the design of non-polarizable force fields tailored to work well in the realm of kilobar pressures – while avoiding complete reparameterization. Our key is to first compute the pressure-induced electronic and structural response of a solute by combining an integral equation approach to include pressure effects on solvent structure with a quantum-chemical treatment of the solute within the embedded cluster reference interaction site model (EC-RISM) framework. Next, the solute’s response to compression is taken into account by introducing pressure-dependence into selected parameters of a well-established force field. In our proof-of-principle study, the full machinery is applied to N,N,N-trimethylamine-N-oxide (TMAO) in water being a potent osmolyte that counteracts pressure denaturation. EC-RISM theory is shown to describe well the charge redistribution upon compression of TMAO(aq) to 10 kbar, which is then embodied in force field molecular dynamics by pressure-dependent partial charges. The performance of the high pressure force field is assessed by comparing to experimental and ab initio molecular dynamics data. Beyond its broad usefulness for designing non-polarizable force fields for extreme thermodynamic conditions, a good description of the pressure-response of solutions is highly recommended when constructing and validating polarizable force fields.

Soviet nostalgia and Russian politics

Directory of Open Access Journals (Sweden)

Stephen White

2010-01-01

Full Text Available Communist rule did not end suddenly in 1989, or in 1991. And for many, at least in Russia, there was no radical break but a complex evolution in which many of the former ruling group, and many of the values of the Soviet period, remained intact. According to the evidence of national representative surveys, levels of support for the principle of a union state have consistently been very high. In 2008 survey, more than half (57% largely or entirely agreed that the demise of the USSR had been a ‘disaster’, and nearly two-thirds (64% thought the former Soviet republics that had established a Commonwealth of Independent States should reconstitute a single state or at least cooperate more closely. Across the three Slavic republics, Russia, Ukraine and Belarus, it was guaranteed employment that was seen as the most positive feature of the old regime, and economic stagnation as its most serious shortcoming. Comparing the present and the Soviet period as they recalled it, ordinary Russians thought they had more opportunity to practise a religion, and to express their opinions. But ordinary people had (in their own view no more influence over the making of public policy than in the communist period, and they thought they were less likely to be treated fairly and equally by government. Age and living standards were the most powerful predictors of Soviet nostalgia when other variables were held constant. Nostalgics were much more likely to support parties of the left, or at least those that favoured public ownership, a Soviet or ‘more democratic Soviet’ system of government, and a closer association among the former Soviet republics; they were much less likely to support the parties that favoured the dissolution of the CIS, a wholly market economy, or Western-style democracy.

Passive containment cooling system with drywell pressure regulation for boiling water reactor

Science.gov (United States)

Hill, P.R.

1994-12-27

A boiling water reactor is described having a regulating valve for placing the wetwell in flow communication with an intake duct of the passive containment cooling system. This subsystem can be adjusted to maintain the drywell pressure at (or slightly below or above) wetwell pressure after the initial reactor blowdown transient is over. This addition to the PCCS design has the benefit of eliminating or minimizing steam leakage from the drywell to the wetwell in the longer-term post-LOCA time period and also minimizes the temperature difference between drywell and wetwell. This in turn reduces the rate of long-term pressure buildup of the containment, thereby extending the time to reach the design pressure limit. 4 figures.

PWR [pressurized water reactor] pressurizer transient response: Final report

International Nuclear Information System (INIS)

Murphy, S.I.

1987-08-01

To predict PWR pressurizer transients, Ahl proposed a three region model with a universal coefficient to represent condensation on the water surface. Specifically, this work checks the need for three regions and the modeling of the interfacial condensation coefficient. A computer model has been formulated using the basic mass and energy conservation laws. A two region vapor and liquid model was first used to predict transients run on a one-eleventh scale Freon pressurizer. These predictions verified the need for a second liquid region. As a result, a three region model was developed and used to predict full-scale pressurizer transients at TMI-2, Shippingport, and Stade. Full-scale pressurizer predictions verified the three region model and pointed out the shortcomings of Ahl's universal condensation coefficient. In addition, experiments were run using water at low pressure to study interface condensation. These experiments showed interface condensation to be significant only when spray flow is turned on; this result was incorporated in the final three region model

The Westinghouse Advanced Passive Pressurized Water Reactor, AP1000

International Nuclear Information System (INIS)

Schene, R.

2009-01-01

Featuring proven technology and innovative passive safety systems, the Westinghouse AP1000 pressurized water reactor can achieve competitive generation costs in the current electricity market without emitting harmful greenhouse gases and further harming the environment. Westinghouse Electric Company, the pioneer in nuclear energy once again sets a new industry standard with the AP1000. The AP1000 is a two-loop pressurized water reactor that uses simplified, innovative and effective approach to safety. With a gross power rating of 3415 megawatt thermal and a nominal net electrical output of 1117 megawatt electric, the AP1000 is ideal for new base load generation. The AP1000 is the safest and most economical nuclear power plant available in the worldwide commercial marketplace, and is the only Generation III+ reactor to receive a design certification from the U.S. Nuclear Regulatory Commission (NRC). Based on nearly 20 years of research and development, the AP1000 builds and improves upon the established technology of major components used in current Westinghouse designed plants. These components, including steam generators, digital instrumentation and controls, fuel, pressurizers, and reactor vessels, are currently in use around the world and have years of proven, reliable operating experience. Historically, Westinghouse plant designs and technology have forged the cutting edge technology of nuclear plant around the world. Today, nearly 50 percent of the world's 440 nuclear plants are based on Westinghouse technology. Westinghouse continues to be the nuclear industry's global leader. (author)

Soviet Space Program Handbook.

Science.gov (United States)

1988-04-01

in advance and some events were even broadcast live. Immediately following the first success- ful launch of their new Energia space launch vehicle in...early 1988. Just as a handbook written a couple of years ago would need updating with Mir, Energia , and the SL-16, this handbook will one day need up...1986. Johnson, Nicholas L. The Soviet Year in Space 1983. Colorado Springs, CO: Teledyne Brown Engineering, 1984. Lawton, A. " Energia - Soviet Super

A hybrid method for in-core optimization of pressurized water reactor reload core design

International Nuclear Information System (INIS)

Stevens, J.G.

1995-05-01

The objective of this research is the development of an accurate, practical, and robust method for optimization of the design of loading patterns for pressurized water reactors, a nonlinear, non-convex, integer optimization problem. The many logical constraints which may be applied during the design process are modeled herein by a network construction upon which performance objectives and safety constraints from reactor physics calculations are optimized. This thesis presents the synthesis of the strengths of previous algorithms developed for reload design optimization and extension of robustness through development of a hybrid liberated search algorithm. Development of three independent methods for reload design optimization is presented: random direct search for local improvement, liberated search by simulated annealing, and deterministic search for local improvement via successive linear assignment by branch and bound. Comparative application of the methods to a variety of problems is discussed, including an exhaustive enumeration benchmark created to allow comparison of search results to a known global optimum for a large scale problem. While direct search and determinism are shown to be capable of finding improvement, only the liberation of simulated annealing is found to perform robustly in the non-convex design spaces. The hybrid method SHAMAN is presented. The algorithm applies: determinism to shuffle an initial solution for satisfaction of heuristics and symmetry; liberated search through simulated annealing with a bounds cooling constraint treatment; and search bias through relational heuristics for the application of engineering judgment. The accuracy, practicality, and robustness of the SHAMAN algorithm is demonstrated through application to a variety of reload loading pattern optimization problems

Conceptual designing of reduced-moderation water reactor with heavy water coolant

Energy Technology Data Exchange (ETDEWEB)

Hibi, Kohki; Shimada, Shoichiro; Okubo, Tsutomu E-mail: okubo@hems.jaeri.go.jp; Iwamura, Takamichi; Wada, Shigeyuki

2001-12-01

The conceptual designing of reduced-moderation water reactors, i.e. advanced water-cooled reactors using plutonium mixed-oxide fuel with high conversion ratios more than 1.0 and negative void reactivity coefficients, has been carried out. The core is designed on the concept of a pressurized water reactor with a heavy water coolant and a triangular tight lattice fuel pin arrangement. The seed fuel assembly has an internal blanket region inside the seed fuel region as well as upper and lower blanket regions (i.e. an axial heterogeneous core). The radial blanket fuel assemblies are introduced in a checkerboard pattern among the seed fuel assemblies (i.e. a radial heterogeneous core). The radial blanket region is shorter than the seed fuel region. This study shows that the heavy water moderated core can achieve negative void reactivity coefficients and conversion ratios of 1.06-1.11.

Loose Soviet nukes: A mountain or a molehill?

International Nuclear Information System (INIS)

Morrison, D.C.

1991-01-01

For almost four decades, US national security alarmists have tossed and turned in the night fretting about the atomic plots that might be hatching behind the Kremlin's impenetrable walls. A secretly deployed antimissile shield? An unanswerable first strike? When Cold War fevers were spiking, no Soviet action was too dire to ponder. Now that the Cold War has been declared over and won, ironically, the focus of US concern has shifted to a new danger that has nothing to do with deliberate Soviet schemes. Rather, as Secretary of Defense Dick Cheney suggested in February 7 remarks to the House Armed Services Committee, the collapse of central authority in the Soviet Union means that the greatest threat to the neighbors of the Soviet Union in the future may well come more from the Soviet inability to control events inside the Soviet Union than it will from any conscious policy of seeking to expand their influence by military means

Soviet Union oil sector outlook grows bleaker still

International Nuclear Information System (INIS)

Anon.

1991-01-01

This paper reports on the outlook for the U.S.S.R's oil sector which grows increasingly bleak and with it prospects for the Soviet economy. Plunging Soviet oil production and exports have analysts revising near term oil price outlooks, referring to the Soviet oil sector's self-destructing and Soviet oil production in a freefall. County NatWest, Washington, citing likely drops in Soviet oil production and exports (OGJ, Aug. 5, p. 16), has jumped its projected second half spot price for West Texas intermediate crude by about $2 to $22-23/bbl. Smith Barney, New York, forecasts WTI postings at $24-25/bbl this winter, largely because of seasonally strong world oil demand and the continued collapse in Soviet oil production. It estimates the call on oil from the Organization of Petroleum Exporting Countries at more than 25 million b/d in first quarter 1992. That would be the highest level of demand for OPEC oil since 1980, Smith Barney noted

Development of alternative fuel for pressurized water reactors

International Nuclear Information System (INIS)

Cardoso, P.E.; Ferreira, R.A.N.; Ferraz, W.B.; Lameiras, F.S.; Santos, A.; Assis, G. de; Doerr, W.O.; Wehner, E.L.

1984-01-01

The utilization of alternative fuel cycles in Pressurized Water Reactors (PWR) such as Th/U and Th/Pu cycles can permit a better utilization of uranium reserves without the necessity of developing new power reactor concepts. The development of the technology of alternative fuels for PWR is one of the objectives of the 'Program on Thorium Utilization in Pressurized Water Reactors' carried out jointly by Empresas Nucleares Brasileiras S.A. (NUCLEBRAS), through its Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) and by German institutions, the Julich Nuclear Research Center (KFA), the Kraftwerk Union A.G. (KWU) and NUKEM GmbH. This paper summarizes the results so far obtained in the fuel technology. The development of a fabrication process for PWR fuel pellets from gel-microspheres is reported as well as the design, the specification, and the fabrication of prototype fuel rods for irradiation tests. (Author) [pt

Soviet histories of love on the American line-up: the phenomenon to the repair-man in modern cinema aesthetics

Directory of Open Access Journals (Sweden)

O. V. Diomina

2014-04-01

Full Text Available The post­Soviet culture is characterized by a deep nostalgia for the Soviet era. The manifestation of that nostalgia is a constant circulation of the Soviet themes in the post­Soviet media space. Classic Soviet romantic comedies are traditionally being showing on the national television during national holidays year by year. There are a lot of remakes of the cult Soviet films released in post­Soviet times. The movie “Office Romance. Modern Time”(2011 is an adaptation of the classic love story of Soviet film “Office Romance”(1977 to the realities of contemporary culture. Remakes adapt Soviet stable movie­plots for contemporary post­Soviet generation. Remake has an interpretive nature. Remake of “Office Romance” had the impact of the Hollywood genre conventions on cinema representation narrative and life style of the characters. Two versions of the same stories that belong to two cultural epochs, show the gradual assimilation of Soviet and post­Soviet cinema of Hollywood genre and mental patterns of American culture. The Soviet “Office Romance” (1977 genre conventions of romantic comedies were adapted to Soviet realities at the semantic level. The heroes of post­Soviet version of “Office Romance” (2011 have incorporated the mental patterns of American culture. The main heroes belief that identity and its representation in the society are not stable and established. On the representation of society and we must take care to design it so that it was clear to people around. This model has been played on the material of (PostSoviet culture in the analyzed films and effectiveness of the model is shown by the happy­ending.

Research on Water Resources Design Carrying Capacity

Directory of Open Access Journals (Sweden)

Guanghua Qin

2016-04-01

Full Text Available Water resources carrying capacity (WRCC is a recently proposed management concept, which aims to support sustainable socio-economic development in a region or basin. However, the calculation of future WRCC is not well considered in most studies, because water resources and the socio-economic development mode for one area or city in the future are quite uncertain. This paper focused on the limits of traditional methods of WRCC and proposed a new concept, water resources design carrying capacity (WRDCC, which incorporated the concept of design. In WRDCC, the population size that the local water resources can support is calculated based on the balance of water supply and water consumption, under the design water supply and design socio-economic development mode. The WRDCC of Chengdu city in China is calculated. Results show that the WRDCC (population size of Chengdu city in development modeI (II, III will be 997 ×104 (770 × 104, 504 × 104 in 2020, and 934 × 104 (759 × 104, 462 × 104 in 2030. Comparing the actual population to the carrying population (WRDCC in 2020 and 2030, a bigger gap will appear, which means there will be more and more pressure on the society-economic sustainable development.

Water-Based Pressure Sensitive Paint

Science.gov (United States)

Oglesby, Donald M.; Ingram, JoAnne L.; Jordan, Jeffrey D.; Watkins, A. Neal; Leighty, Bradley D.

2004-01-01

Preparation and performance of a water-based pressure sensitive paint (PSP) is described. A water emulsion of an oxygen permeable polymer and a platinum porphyrin type luminescent compound were dispersed in a water matrix to produce a PSP that performs well without the use of volatile, toxic solvents. The primary advantages of this PSP are reduced contamination of wind tunnels in which it is used, lower health risk to its users, and easier cleanup and disposal. This also represents a cost reduction by eliminating the need for elaborate ventilation and user protection during application. The water-based PSP described has all the characteristics associated with water-based paints (low toxicity, very low volatile organic chemicals, and easy water cleanup) but also has high performance as a global pressure sensor for PSP measurements in wind tunnels. The use of a water-based PSP virtually eliminates the toxic fumes associated with the application of PSPs to a model in wind tunnels.

The inner containment of an EPR trademark pressurized water reactor

Energy Technology Data Exchange (ETDEWEB)

Ostermann, Dirk; Krumb, Christian; Wienand, Burkhard [AREVA GmbH, Offenbach (Germany)

2014-08-15

On February 12, 2014 the containment pressure and subsequent leak tightness tests on the containment of the Finnish Olkiluoto 3 EPR trademark reactor building were completed successfully. The containment of an EPR trademark pressurized water reactor consists of an outer containment to protect the reactor building against external hazards (such as airplane crash) and of an inner containment that is subjected to internal overpressure and high temperature in case of internal accidents. The current paper gives an overview of the containment structure, the design criteria, the validation by analyses and experiments and the containment pressure test.

High-pressure water facility

Science.gov (United States)

2006-01-01

NASA Test Operations Group employees, from left, Todd Pearson, Tim Delcuze and Rodney Wilkinson maintain a water pump in Stennis Space Center's high-pressure water facility. The three were part of a group of employees who rode out Hurricane Katrina at the facility and helped protect NASA's rocket engine test complex.

USSR Local War Doctrine as Rationale for the Development of the Soviet CTOL Aircraft Carrier.

Science.gov (United States)

1985-06-01

Soviet Union. [Ref. 11: p. 252] The peacetime Red naval mission is not entirely one of blissful exchanges of pleasantries. Its utility during distant...expended toward gift presentation and the exchange of pleasantries. Such visits were designed as feelers to divine Russian acceptance by the developing...How- * ever, the presence of military forces displaying the capa- * bilities to intervene may have affected the perceptions of * Soviet clinets

Skill Formation and Utilisation in the Post-Soviet Transition: Higher Education Planning in Post-Soviet Georgia

Science.gov (United States)

Gvaramadze, Irakli

2010-01-01

Changes in the former Soviet system had a dramatic influence on higher education in Georgia. The main objective of the current article is to analyse implications of the post-Soviet transition for the skill formation and skill utilisation system in Georgia. In particular, the study analyses recent trends in Georgian higher education including…

SOVIET POSTERS IN LITHUANIA IN 1940–1953

Directory of Open Access Journals (Sweden)

Bajoraite, Alma

2006-12-01

Full Text Available The Soviet occupation and their ideology brought to Lithuania a new poster quality. The paper analyzes the problem of posters propaganda and manipulation, the inheritance of the not traditional documents and their inventory. The goal of this paper is to analyze the soviet posters in Lithuania in 1940–1953.The principal problems of this paper are to research the formation and the domination of the posters in Lithuania: which role they had in the politics. The paper also analyzes the soviet posters impact on farming and their influence to the society.To sum up, the new trend of art appeared in 1940 in Lithuania, which had the principal goal to propagate the soviet ideology in all the political and social spheres. The goal of the soviet posters as the media of information was to provide the distorted view of the reality. The soviet posters had dominated in Lithuania in 1940–1953. This period had left a very interesting and rich heritage. It is the importatant part of the cultural and historical heritage.

Pump selection and application in a pressurized water reactor electric generating plant

International Nuclear Information System (INIS)

Kitch, D.M.

1985-01-01

Various pump applications utilized in a nuclear pressurized water reactor electric generating plant are described. Emphasis is on pumps installed in the auxiliary systems of the primary nuclear steam supply system. Hydraulic and mechanical details, the ASME Code (Nuclear Design), materials, mechanical seals, shaft design, seismic qualification, and testing are addressed

Pressure pressure-balanced pH sensing system for high temperature and high pressure water

International Nuclear Information System (INIS)

Tachibana, Koji

1995-01-01

As for the pH measurement system for high temperature, high pressure water, there have been the circumstances that first the reference electrodes for monitoring corrosion potential were developed, and subsequently, it was developed for the purpose of maintaining the soundness of metallic materials in high temperature, high pressure water in nuclear power generation. In the process of developing the reference electrodes for high temperature water, it was clarified that the occurrence of stress corrosion cracking in BWRs is closely related to the corrosion potential determined by dissolved oxygen concentration. As the types of pH electrodes, there are metal-hydrogen electrodes, glass electrodes, ZrO 2 diaphragm electrodes and TiO 2 semiconductor electrodes. The principle of pH measurement using ZrO 2 diaphragms is explained. The pH measuring system is composed of YSZ element, pressure-balanced type external reference electrode, pressure balancer and compressed air vessel. The stability and pH response of YSZ elements are reported. (K.I.)

Thermohydraulic analysis of pressurized water reactors

International Nuclear Information System (INIS)

Veloso, M.A.

1980-01-01

The computer program PANTERA is applied in the thermo-hydraulic analysis of Pressurized Water Reactor Cores (PWR). It is a version of COBRA-IIIC in which a new thermal conduction model for fuel rods was introduced. The results calculated by this program are compared with experimental data obtained from bundles of fuel rods, simulating reactor conditions. The validity of the new thermal model is checked too. The PANTERA code, through a simplified procedure of calculation, is used in the thermo-hydraulic analysis of Indian Point, Unit 2, reactor core, in stationary conditions. The results are discussed and compared with design data. (Autor) [pt

Managing water pressure for water savings in developing countries

African Journals Online (AJOL)

2014-03-03

Mar 3, 2014 ... effort into providing customers with a reliable level of service, often via poor water ... budgets. There are many factors contributing to water losses in water .... given relationship does not reflect the impact of pressure on.

Soviet experience with peaceful uses of nuclear explosions

International Nuclear Information System (INIS)

Nordyke, M.D.

1976-01-01

The Soviet Union is pursuing an active program for developing peaceful uses of nuclear explosions (PNE). They have reported 16 explosions, with applications ranging from putting out oil-well fires and stimulating oil recovery to creating instant dams and canals. The data reported generally agree with U.S. experience. Seismic data collected by western sources on explosions outside the known Soviet test sites indicate that the Soviet program is at least twice as large as they have reported. The accelerated pace of these events suggests that in some applications the Soviet PNE program is approaching routine industrial technology

Development of a higher capacity, lower pressure drop steam/water separator with reduced primary-to-secondary spacing

International Nuclear Information System (INIS)

Pruster, W.P.; Kidwell, J.H.; Eaton, A.M.; Wall, J.R.

1985-01-01

The goal of this development effort was to double the steam flow capacity of an existing module steam/water separator design without significantly increasing the pressure drop while simultaneously minimizing the vertical distance (spacing) between the primary and secondary separation stages. The development work included extensive air/water and steam/water testing. The steam/water tests were performed at a common pressure of 300 psia (2.1 MPa) with comparable water and steam flows

Pressurized water-reactor feedwater piping response to water hammer

International Nuclear Information System (INIS)

Arthur, D.

1978-03-01

The nuclear power industry is interested in steam-generator water hammer because it has damaged the piping and components at pressurized water reactors (PWRs). Water hammer arises when rapid steam condensation in the steam-generator feedwater inlet of a PWR causes depressurization, water-slug acceleration, and slug impact at the nearest pipe elbow. The resulting pressure pulse causes the pipe system to shake, sometimes violently. The objective of this study is to evaluate the potential structural effects of steam-generator water hammer on feedwater piping. This was accomplished by finite-element computation of the response of two sections of a typical feedwater pipe system to four representative water-hammer pulses. All four pulses produced high shear and bending stresses in both sections of pipe. Maximum calculated pipe stresses varied because the sections had different characteristics and were sensitive to boundary-condition modeling

Liquid radioactive waste processing system for pressurized water reactor plants

International Nuclear Information System (INIS)

Anon.

1976-01-01

This Standard sets forth design, construction, and performance requirements, with due consideration for operation, of the Liquid Radioactive Waste Processing System for pressurized water reactor plants for design basis inputs. For the purpose of this Standard, the Liquid Radioactive Waste Processing System begins at the interfaces with the reactor coolant pressure boundary and the interface valve(s) in lines from other systems, or at those sumps and floor drains provided for liquid waste with the potential of containing radioactive material; and it terminates at the point of controlled discharge to the environment, at the point of interface with the waste solidification system, and at the point of recycle back to storage for reuse

Indigeneous design and development of differential pressure reducing valves for PHWRs (Paper No. 055)

International Nuclear Information System (INIS)

Soni, N.L.; Agrawal, R.C.; Chandra, Rajesh

1987-02-01

On load fuelling of Pressurised Heavy Water Reactors (PHWRs) is being achieved with the help of Fuelling Machine (F/M). Various actuations are to be carried out inside the F/M magazine pressure housing with the help of high pressure water hydraulic actuators. A constant differential pressure is required to be maintained between pressurized magazine housing and the actuators-supply line for proper operation of the actuators which are to be located inside it. This is achieved with the help of the Differential Pressure Reducing Valve (DPRV). So far these valves have been procured only from a single foreign supplier. In March 1980, the price of each valve was US dollars 3100.00. Dependence on a single foreign supplier may create problems of timely procurement. An effort was made to design and manufacture the DPRV indigensouly meeting the stringent specifications. Theoretical study of single acting DPRV was carried out and design criteria were established. The valve was tested for its performance and was found satisfactory. (author). 8 figs

Meshed-Pumpkin Super-Pressure Balloon Design

Science.gov (United States)

Jones, Jack; Yavrouian, Andre

2003-01-01

An improved, lightweight design has been proposed for super-pressure balloons used to carry scientific instruments at high altitudes in the atmosphere of Earth for times as long as 100 days. [A super-pressure balloon is one in which the pressure of the buoyant gas (typically, helium) is kept somewhat above ambient pressure in order to maintain approximately constant density and thereby regulate the altitude.] The proposed design, called "meshed pumpkin," incorporates the basic concept of the pumpkin design, which is so named because of its appearance. The pumpkin design entails less weight than does a spherical design, and the meshed-pumpkin design would reduce weight further. The basic idea of the meshed-pumpkin design is to reinforce the membrane of a pumpkin balloon by attaching a strong, lightweight fabric mesh to its outer surface. The reinforcement would make it possible to reduce the membrane mass to one-third or less of that of the basic pumpkin design while retaining sufficient strength to enable the balloon to remain at approximately constant altitude for months.

Former Soviet refineries face modernization, restructuring

International Nuclear Information System (INIS)

Anon.

1993-01-01

A massive modernization and restructuring program is under way in the refining sector of Russia and other former Soviet republics. Economic reforms and resulting economic dislocation following the collapse of the Soviet Union has left refineries in the region grappling with a steep decline and changes in product demand. At the same time, rising oil prices and an aging, dilapidated infrastructure promise a massive shakeout. Even as many refineries in the former Soviet Union (FSU) face possible closure because they are running at a fraction of capacity, a host of revamps, expansions, and grass roots refineries are planned or under way. The paper discusses plans

Education in the Soviet Baltic Republics.

Science.gov (United States)

Soviet Education, 1981

1981-01-01

Includes 11 articles about education in the Soviet Baltic Republics. The articles include historical studies of Estonian and Latvian schools and medieval Estonian folk games. The impact of Marxist educational theories and Soviet policies on educational research, teacher education, and teaching methods in the Baltic region from 1920-50 is…

Excess pore water pressure induced in the foundation of a tailings dyke at Muskeg River Mine, Fort McMurray

Energy Technology Data Exchange (ETDEWEB)

Eshraghian, A.; Martens, S. [Klohn Crippen Berger Ltd., Calgary, AB (Canada)

2010-07-01

This paper discussed the effect of staged construction on the generation and dissipation of excess pore water pressure within the foundation clayey units of the External Tailings Facility dyke. Data were compiled from piezometers installed within the dyke foundation and used to estimate the dissipation parameters for the clayey units for a selected area of the foundation. Spatial and temporal variations in the pore water pressure generation parameters were explained. Understanding the process by which excess pore water pressure is generated and dissipates is critical to optimizing dyke design and performance. Piezometric data was shown to be useful in improving estimates of the construction-induced pore water pressure and dissipation rates within the clay layers in the foundation during dyke construction. In staged construction, a controlled rate of load application is used to increase foundation stability. Excess pore water pressure dissipates after each application, so the most critical stability condition happens after each load. Slow loading allows dissipation, whereas previous load pressure remains during fast loading. The dyke design must account for the rate of loading and the rate of pore pressure dissipation. Controlling the rate of loading and the rate of stress-induced excess pore water pressure generation is important to dyke stability during construction. Effective stress-strength parameters for the foundation require predictions of the pore water pressure induced during staged construction. It was found that both direct and indirect loading generates excess pore water pressure in the foundation clays. 2 refs., 2 tabs., 11 figs.

Design of an integral missile shield in integrated head assembly for pressurized water reactor at commercial nuclear plants

International Nuclear Information System (INIS)

Baliga, Ravi; Watts, Tom Neal; Kamath, Harish

2015-01-01

In ICONE22, the authors presented the Integrated Head Assembly (IHA) design concept implemented at Callaway Nuclear Power Plant in Missouri, USA. The IHA concept is implemented to reduce the outage duration and the associated radiation exposure to the workers by reducing critical path time during Plant Refueling Outage. One of the head area components in the IHA is a steel missile shield designed to protect the Control Rod Drive Mechanism (CRDM) assembly from damaging other safety-related components in the vicinity in the Containment. Per Federally implemented General Design Criteria for commercial nuclear plants in the USA, the design of Nuclear Steam Supply System (NSSS) must provide protection from the damages caused by a postulated event of CRDM housing units and their associated parts disengaging from the reactor vessel assembly. This event is considered as a Loss of Coolant Accident (LOCA) and assumes that once the CRDM housing unit and their associated parts disengage from the reactor vessel internals assembly, they travel upward by the water jet with the following sequence of events: Per Reference 1, the drive shaft and control rod cluster are forced out of the reactor core by the differential pressure across the drive shaft with the assumption that the drive shaft and control rod cluster, latched together, are fully inserted when the accident occurs. After the travel, the rod cluster control spider will impact the lower side of the upper support plate inside the reactor vessel fracturing the flexure arms in the joint freeing the drive shaft from the control rod cluster. The control rod cluster is stopped by the upper support plate and will remain below the upper support plate during this accident. However, the drive shaft will continue to accelerate in the upward direction until it is stopped by a safety feature in the IHA. The integral missile shield as a safety feature in the IHA is designed to stop the CRDM drive shaft from moving further up in the

Le realizzazioni dell'economia sovietica. (Soviet economic performance

Directory of Open Access Journals (Sweden)

A. MADDISON

2014-07-01

Full Text Available While in the 1950s Soviet output grew faster than most other industrial countries, the early 1960s has seen a noticeable slowing down in growth. The present paper puts these economic developments into perspective to judge the efficacy of Soviet policy in its attempt to achieve maximum growth and transform an underdeveloped into a developed country. The author first assesses Soviet performance and policy at different stages of development, before assessing the level attained. The purposes for which output is used and the major factors responsible for Soviet performance are then analysed. Finally, likely future developments are considered.JEL: P27, O40

Soviet space nuclear reactor incidents - Perception versus reality

Science.gov (United States)

Bennett, Gary L.

1992-01-01

Since the Soviet Union reportedly began flying nuclear power sources in 1965 it has had four publicly known accidents involving space reactors, two publicly known accidents involving radioisotope power sources and one close call with a space reactor (Cosmos 1900). The reactor accidents, particularly Cosmos 954 and Cosmos 1402, indicated that the Soviets had adopted burnup as their reentry philosophy which is consistent with the U.S. philosophy from the 1960s and 1970s. While quantitative risk analyses have shown that the Soviet accidents have not posed a serious risk to the world's population, concerns still remain about Soviet space nuclear safety practices.

How does network design constrain optimal operation of intermittent water supply?

Science.gov (United States)

Lieb, Anna; Wilkening, Jon; Rycroft, Chris

2015-11-01

Urban water distribution systems do not always supply water continuously or reliably. As pipes fill and empty, pressure transients may contribute to degraded infrastructure and poor water quality. To help understand and manage this undesirable side effect of intermittent water supply--a phenomenon affecting hundreds of millions of people in cities around the world--we study the relative contributions of fixed versus dynamic properties of the network. Using a dynamical model of unsteady transition pipe flow, we study how different elements of network design, such as network geometry, pipe material, and pipe slope, contribute to undesirable pressure transients. Using an optimization framework, we then investigate to what extent network operation decisions such as supply timing and inflow rate may mitigate these effects. We characterize some aspects of network design that make them more or less amenable to operational optimization.

Troubled lands: The legacy of Soviet environmental destruction

International Nuclear Information System (INIS)

Peterson, D.J.

1993-01-01

This book presents a picture of daily life and environmental conditions in the former Soviet Union, based on the personal contacts of the author and on local media coverage. The challenges of living with contaminated food, drinking water, land, and air are described. Also examined are developments in the region's environmental policy and politics and what the long-term effects could be. Information on environmental conditions in other regions of the world are given for comparison

Ethnicity and Power in the Soviet Union

Directory of Open Access Journals (Sweden)

Andrzej Wierzbicki

2017-01-01

Full Text Available Twenty years have passed since the dissolution of the Soviet Union. Up until the point of dissolution, the Soviet authorities and intellectual elite had attempted to build a community in order to unite all Soviet citizens in the spirit of socialist modernisation. Although it is difficult to demonstrate that ‘a Soviet nation’ was successfully created [1], the attempt to build such a nation can serve as a case study through which to examine nation-building processes for constructivists as well as modernists . In addition to socialist modernisation, the Soviet nation aimed to be identified as a state, which would make it similar to the political nations dominant in western countries. Contrary to western tradition, however, it was not a nation state that provided full rights for all its citizens, but rather a socialist state that was ‘ruled by workers and peasantry’. Nevertheless, the authorities aimed to give the Soviet nation the characteristics of a specific nation state. “It was a nation that in historical terms strived, or more accurately part of which strived, to form or proclaim a particular state” [2]. While at the time of proclaiming the USSR there was no such thing as the Soviet nation, it can be assumed that it was intended to become a constructed titular nation. The majority of national communities, even created ones, have an ethnic core. However academics cannot agree on the kind of state the USSR was, to what extent it took into account the ethnicity of its multinational population, how much it reflected the values, culture, and interests of its largest population group (i.e., the Russians or even whether it was a Russian national state despite the strong influence of Russian ideology and politics. Some Russian academics, especially those in nationalistic circles (e.g., Valerij Solovej as well as western scholars such as Terry Martin and Geoffrey Hosking stressed that Russians dominated demographically and politically

SCW Pressure-Channel Nuclear Reactors: Some Design Features and Concepts

International Nuclear Information System (INIS)

Duffey, R.B.; Pioro, I.L.; Gabaraev, B.A.; Kuznetsov, Yu. N.

2006-01-01

Concepts of nuclear reactors cooled with water at supercritical pressures were studied as early as the 1950's and 1960's in the USA and Russia. After a 30-year break, the idea of developing nuclear reactors cooled with supercritical water (SCW) became attractive again as the ultimate development path for water-cooling. The main objectives of using SCW in nuclear reactors are 1) to increase the thermal efficiency of modern nuclear power plants (NPPs) from 33 -- 35% to about 40 -- 45%, and 2) to decrease capital and operational costs and hence decrease electrical energy costs (∼$ 1000 US/kW). SCW NPPs will have much higher operating parameters compared to modern NPPs (pressure about 25 MPa and outlet temperature up to 625 deg. C), and a simplified flow circuit, in which steam generators, steam dryers, steam separators, etc., can be eliminated. Also, higher SCW temperatures allow direct thermo-chemical production of hydrogen at low cost, due to increased reaction rates. Pressure-channel SCW nuclear reactor concepts are being developed in Canada and Russia. Design features related to both channels and fuel bundles are discussed in this paper. Also, Russian experience with operating supercritical steam heaters at NPP is presented. The main conclusion is that development of SCW pressure-channel nuclear reactors is feasible and significant benefits can be expected over other thermal energy systems. (authors)

Reactor Safety Commission Code of Practice for Pressurized Water Reactors

International Nuclear Information System (INIS)

1990-01-01

The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

Evolution of Soviet Theater Nuclear Forces

International Nuclear Information System (INIS)

Atkeson, E.B.

1994-01-01

Soviet theater nuclear forces were a major pillar of Soviet superpower strength, rising sharply under Krushchev in the latter 1950s to their zenith under Brezhnev twenty years later. Most recently they have begun their decline under Gorbachev, and while not yet facing extinction, may be headed for a much reduced role under the new thinking in the USSR. This paper deals with the Soviet TNF in six periods of their life: The Post-war Stalin Period (1945-1953), the Post-Stalin Period (1953-1955), The Transition Period (1955-1959), The Period of Nuclear Revolution (1960-1964), The Period of Modern TNF Planning (1965-1980), and The Period of Non-nuclear Planning (1980-1987)

Fuzzy logic control of steam generator water level in pressurized water reactors

International Nuclear Information System (INIS)

Kuan, C.C.; Lin, C.; Hsu, C.C.

1992-01-01

In this paper a fuzzy logic controller is applied to control the steam generator water level in a pressurized water reactor. The method does not require a detailed mathematical mode of the object to be controlled. The design is based on a set of linguistic rules that were adopted from the human operator's experience. After off-line fuzzy computation, the controller is a lookup table, and thus, real-time control is achieved. Shrink-and-swell phenomena are considered in the linguistic rules, and the simulation results show that their effect is dramatically reduced. The performance of the control system can also be improved by changing the input and output scaling factors, which is convenient for on-line tuning

The evolution of Soviet forces, strategy, and command

International Nuclear Information System (INIS)

Ball, D.; Bethe, H.A.; Blair, B.G.; Bracken, P.; Carter, A.B.; Dickinson, H.; Garwin, R.L.; Holloway, D.; Kendall, H.W.

1988-01-01

This paper reports on the evolution of Soviet forces, strategy and command. Soviet leaders have repeatedly emphasized that it would be tantamount to suicide to start a nuclear war. Mutual deterrence, however, does not make nuclear was impossible. The danger remains that a large-scale nuclear was could start inadvertently in an intense crisis, or by escalation out of a conventional war, or as an unforeseen combination of these. For these reasons crisis management has become a central issue in the United States, but the standard Soviet response to this Western interest has been to say that what is needed is crisis avoidance, not recipes for brinkmanship masquerading under another name. There is much sense in this view. Nevertheless, this demeanor does not mean that the Soviet Union has given no thought to the danger that a crisis might lead to nuclear war, only that Soviet categories for thinking about such matters differ from those employed in the United States

Soviet in content - people’s in form: The building of Farming Cooperative Centres and the Soviet-Yugoslav dispute, 1948-1950

Directory of Open Access Journals (Sweden)

Živančević Jelena

2011-01-01

Full Text Available It was not until 1948, when the Cominform conflict escalated, that the Communist Party of Yugoslavia began a thorough implementation of the Soviet model in Yugoslav agriculture - due to the Soviet criticism, the CPY made immediate legislative changes and started a class struggle in Yugoslav villages. Simultaneously, and just a few months before the Fifth Congress, Josip Broz Tito initiated a competition for building 4,000 Farming Cooperative Centres throughout Yugoslavia - they were built in accordance with the social-realist “national in form - socialist in content” slogan. Once the building started, in his Congress speech, Radovan Zogović, a leader of the Serbian Agitprop department, offered the first official proclamation of Socialist Realism in the post-war period by a political authority. This article analyses the process of planning, designing and building of the Farming Cooperative Centres; discusses their political, ideological and formal implications; and inquires into the specific role of architecture, joined with the theory of Socialist Realism, in building Yugoslav socialism.

The Revitalization of the Soviet Film Industry.

Science.gov (United States)

Bogomolov, Yuri

1991-01-01

Discusses how the grip of the Soviet Union's past--from Stalinist mythology to ideological cliche--is being exposed and undermined whereas a sense of individual efficacy, necessary for the present, has yet to emerge from the portrayals in Soviet films. (PRA)

Water cooled static pressure probe

Science.gov (United States)

Lagen, Nicholas T. (Inventor); Eves, John W. (Inventor); Reece, Garland D. (Inventor); Geissinger, Steve L. (Inventor)

1991-01-01

An improved static pressure probe containing a water cooling mechanism is disclosed. This probe has a hollow interior containing a central coolant tube and multiple individual pressure measurement tubes connected to holes placed on the exterior. Coolant from the central tube symmetrically immerses the interior of the probe, allowing it to sustain high temperature (in the region of 2500 F) supersonic jet flow indefinitely, while still recording accurate pressure data. The coolant exits the probe body by way of a reservoir attached to the aft of the probe. The pressure measurement tubes are joined to a single, larger manifold in the reservoir. This manifold is attached to a pressure transducer that records the average static pressure.

Soviet books and publications on hydrology (continental) and hydrogeology: titles and some notes on obtaining Soviet monographs

Science.gov (United States)

Manheim, Frank T.

1966-01-01

A common method of publication for Soviet scientists, which partly supplants periodicals, is the publication of a collection of articles on a general area of research, frequently by members of a given institution. An extensive sampling of world geologic literature for 1961 (Hawkes, 1966) showed that 33 percent of Soviet titles appeared in periodicals whereas 55 percent of North American and 70 percent of Western European literature appeared in this form. The Soviet predilection for symposia and collections of papers makes searching for information on a given subject more difficult for Westerners because the monographs in question are often not included in exchange agreements (except informal personal ones) with Western libraries and institutions, because they may be primed in small editions, and because such publications frequently escape the notice of Western abstract journals. Unless one is fortunate enough to have many personal contacts in the Soviet Union, there seems to be little alternative to at least a rudimentary knowledge of Russian in order to stay abreast of work published as monographs and in collections.

Improvement of lifetime availability through design, inspection, repair and replacement of coolant channels of Indian Pressurized Heavy Water Reactors

International Nuclear Information System (INIS)

Rupani, B.B.; Sinha, R.K.

1998-01-01

This paper covers an overview of the work carried out for the life management of the coolant channels of Indian Pressurised Heavy Water Reactors. In order to improve maintainability of the coolant channels and reduce down time needed for periodical creep adjustment, improved design of channel hardware were developed. The modular insulation panel, designed as a substitute for the jig saw panels, reduces the time needed for accessing the space around the end-fitting significantly. A compact mechanical snubber has been developed to totally eliminate the need for periodic creep adjustment. In addition, the paper also describes the technologies developed for performing some special inspection, repair and replacement tasks for the coolant channels. These include systems for garter spring repositioning by Mechanical Flexing Technique for fresh reactors and Integrated Garter Spring Repositioning System for operating reactors. A tooling system, developed for in-situ retrieval of sliver scrape samples from pressure tubes, is also described. These samples can be analysed in laboratories to yield valuable information on hydrogen concentration in pressure tube material. The current and planned activities towards development of technologies for improvement of the life time availability of the power plants are addressed. (author)

Soviet Robots in the Solar System Mission Technologies and Discoveries

CERN Document Server

Huntress, JR , Wesley T

2011-01-01

The Soviet robotic space exploration program began in a spirit of bold adventure and technical genius. It ended after the fall of the Soviet Union and the failure of its last mission to Mars in 1996. Soviet Robots in the Solar System chronicles the scientific and engineering accomplishments of this enterprise from its infancy to its demise. Each flight campaign is set into context of national politics and international competition with the United States. Together with its many detailed illustrations and images, Soviet Robots in the Solar System presents the most detailed technical description of Soviet robotic space flights provides a unique insight into programmatic, engineering, and scientific issues covers mission objectives, spacecraft engineering, flight details, scientific payload and results describes in technical depth Soviet lunar and planetary probes

Economic and political hybridity: Patrimonial capitalism in the post-Soviet sphere

OpenAIRE

Robinson, Neil

2013-01-01

Hybridity in non-democratic states can be economic as well as political. Economic hybridity is produced by the same kind of pressures that create political hybridity, but the relationship between economic and political hybridity has not been as much studied by political scientists. This article uses the concept of patrimonial capitalism to look at economic hybridity, its stability and relationship to political hybridity. Using examples from Russia and other former Soviet states it argues that...

Water Flow Testing and Unsteady Pressure Analysis of a Two-Bladed Liquid Oxidizer Pump Inducer

Science.gov (United States)

Schwarz, Jordan B.; Mulder, Andrew; Zoladz, Thomas

2011-01-01

The unsteady fluid dynamic performance of a cavitating two-bladed oxidizer turbopump inducer was characterized through sub-scale water flow testing. While testing a novel inlet duct design that included a cavitation suppression groove, unusual high-frequency pressure oscillations were observed. With potential implications for inducer blade loads, these high-frequency components were analyzed extensively in order to understand their origins and impacts to blade loading. Water flow testing provides a technique to determine pump performance without the costs and hazards associated with handling cryogenic propellants. Water has a similar density and Reynolds number to liquid oxygen. In a 70%-scale water flow test, the inducer-only pump performance was evaluated. Over a range of flow rates, the pump inlet pressure was gradually reduced, causing the flow to cavitate near the pump inducer. A nominal, smooth inducer inlet was tested, followed by an inlet duct with a circumferential groove designed to suppress cavitation. A subsequent 52%-scale water flow test in another facility evaluated the combined inducer-impeller pump performance. With the nominal inlet design, the inducer showed traditional cavitation and surge characteristics. Significant bearing loads were created by large side loads on the inducer during synchronous cavitation. The grooved inlet successfully mitigated these loads by greatly reducing synchronous cavitation, however high-frequency pressure oscillations were observed over a range of frequencies. Analytical signal processing techniques showed these oscillations to be created by a rotating, multi-celled train of pressure pulses, and subsequent CFD analysis suggested that such pulses could be created by the interaction of rotating inducer blades with fluid trapped in a cavitation suppression groove. Despite their relatively low amplitude, these high-frequency pressure oscillations posed a design concern due to their sensitivity to flow conditions and

Mark I 1/5-scale boiling water reactor pressure suppression experiment facility report

International Nuclear Information System (INIS)

Altes, R.G.; Pitts, J.H.; Ingraham, R.F.; Collins, E.K.; McCauley, E.W.

1977-01-01

An accurate Mark I 1 / 5 -scale, boiling water reactor (BWR), pressure suppression facility was designed and constructed at Lawrence Livermore Laboratory (LLL) in 11 months. Twenty-seven air tests using the facility are described. Cost was minimized by utilizing equipment borrowed from other LLL programs. The total value of borrowed equipment exceeded the program's budget of $2,020,000. Substantial flexibility in the facility was used to permit independent variation in the drywell pressure-time history, initial pressure in the drywell and toroidal wetwells, initial toroidal wetwell water level and downcomer length, vent line flow resistance, and vent line flow asymmetry. The two- and three-dimensional sectors of the toroidal wetwell provided significant data

Influence of the loop design of the feedwater- and steam quality in a power plant with pressurized water reactor

International Nuclear Information System (INIS)

Bennert, J.; Becher, L.

1977-01-01

At nuclear power plants with pressurized water reactors, condensate occurs on the high pressure part of the water-steam circuit, caused by the operation with low steam parameters. The behaviour of the electrolytes which entered into the circuit (solubility, distribution in water and/or steam) shows that these electrolytes (salts) are to be found mainly in the condensate. The insinuated electrolytes are reconcentrated during the common arrangements with 'Small Circuit' - consisting of steam generator, high pressure turbine, water separator, feedwater vessel, and have a negative influence on the feedwater - boiler water - and the steam quality. Remedy is possible by modified arrangements, during which these electrolyte-containing condensates will be treated and traced back into the main circuit. Nevertheless that the efficiency decrease is insignificant and additional efforts are necessary, a change over to these arrangements is recommendable, due to the fact that the feedwater quality, the boiler water quality, the steam quality in front of the turbine, and finally also the operational safety, as well as the availability will be improved. (orig.) [de

The Tenth Period of Soviet Third World Policy

Science.gov (United States)

1987-10-01

All its activity is taking place in an atmosphere of responsible criticism and self-criticism and of observance of the principle of looking the truth...tremendous stability to the Soviet-Indian relationship. Moscow’s ties with New Dehli have lasted now well over thirty years. Moscow can be confident...itself a superpower with global interests and commitments. The costs of the Soviet empire may be onerous at the margin when Soviet economic managers

Supercritical water gasification with decoupled pressure and heat transfer modules

KAUST Repository

Dibble, Robert

2017-09-14

The present invention discloses a system and method for supercritical water gasification (SCWG) of biomass materials wherein the system includes a SCWG reactor and a plurality of heat exchangers located within a shared pressurized vessel, which decouples the function of containing high pressure from the high temperature function. The present invention allows the heat transfer function to be conducted independently from the pressure transfer function such that the system equipment can be designed and fabricated in manner that would support commercial scaled-up SCWG operations. By using heat exchangers coupled to the reactor in a series configuration, significant efficiencies are achieved by the present invention SCWG system over prior known SCWG systems.

Adult Development Theory and Political Analysis: An Integral Account of Social and Political Change in Soviet and Post-Soviet Russia

OpenAIRE

Elke Fein

2010-01-01

I propose a reading of social, political and discursive change in Soviet and post-Soviet Russia which is inspired by an integral, above all developmental perspective. In view of explaining Russia’s current political trajectory, I make several arguments. First, I claim that Russian politics are still to a large extent determined by the effects of a threefold crisis of sense-making. Neither the collapse of the Soviet empire, nor the question of how to define democratic government nor the lack o...

Nonlinear dynamics research in the former Soviet Union

International Nuclear Information System (INIS)

McKenney, B.L.; Krafsig, J.; Moon, F.C.; Shlesinger, M.F.

1992-08-01

This assessment of nonlinear dynamics research in the former Soviet Union was performed by seven US scientists and engineers active in the fields examined. The topics covered include: solid-state systems and circuits, information theory and signal analysis, chaos in mechanical systems, turbulence and vortex dynamics, ocean processes, image processing, and lasers and nonlinear optics. The field of nonlinear dynamics and chaos blossomed in academic settings in both the West and the former Soviet Union during the 1980s. The field went from mathematical abstraction to interesting engineering application areas. Several generalizations can be drawn from the review of Soviet work: Soviet work generally began earlier than Western work, and, in areas that do not require extensive computational resources, that work has kept up with, and often leads, the West. This is especially true in the mathematical analysis of nonlinear phenomena. Soviet researchers have shown an ability to combine numerical or analytic ideas with laboratory experimentation in a smoother, less erratic fashion than Western researchers. Furthermore, contrary to Western practice, the same researchers often do both theoretical and experimental work. In areas that require numerical verification of ideas in the field, the Western work is leading that of the former Soviet Union. This is especially true in the areas of signal processing, simulations of turbulence, and communications. No evidence was found of any significant penetration of ideas of nonlinear dynamics into technological applications of a military or commercial area in the former Soviet Union. Opportunities abound, but specific applications are not apparent

Unique rod lens/video system designed to observe flow conditions in emergency core coolant loops of pressurized water reactors

International Nuclear Information System (INIS)

Carter, G.W.

1979-01-01

Techniques and equipment are described which are used for video recordings of the single- and two-phase fluid flow tests conducted with the PKL Spool Piece Measurement System designed by Lawrence Livermore Laboratory and EG and G Inc. The instrumented spool piece provides valuable information on what would happen in pressurized water reactor emergency coolant loops should an accident or rupture result in loss of fluid. The complete closed-circuit television video system, including rod lens, light supply, and associated spool mounting fixtures, is discussed in detail. Photographic examples of test flows taken during actual spool piece system operation are shown

The European Pressurized Water Reactor. A safe and competitive solution for future energy needs

International Nuclear Information System (INIS)

Leverenz, R.; Gerhard, L.; Goebel, A.

2004-01-01

The European Pressurized Water Reactor - the EPR - is a PWR in the 1600 MW class. Its design is based on experience feedback from several thousand reactors x years of light water reactor operation worldwide, primarily those incorporating the most recent technologies: the French N4 and the German KONVOI reactors. It is an evolutionary design that ensures continuity in the mastery of PWR technology, minimizing the risk for the customer. (author)

Methods and means for reducing pressure in systems for fire fighting and water spraying in mines

Energy Technology Data Exchange (ETDEWEB)

Kozlyuk, A I; Grin' , G V; Yushchenko, Yu N

1986-01-01

Valves are evaluated used in water systems for fire fighting and dust suppression in underground black coal mines in the USSR. Specifications of the KR-2, the KR-3 and the R-86 pressure-reducing valves used in deep mines are analyzed. The valves are characterized by low reliability, low capacity and low pressure reducing range. Therefore groups (parallel arrangement) of pressure-reducing valves are used. Using valve groups increases equipment cost. The pressure-reducing systems should consist of no more than 2 valves. The VNIIGD Institute developed the RKGD pressure-reducing valve with the following specifications: inlet pressure 6.87 MPa, outlet pressure from 0.98 to 2.45 MPa, water discharge 100 m/sup 3//h). The RKGD valves are characterized by high reliability but extremely high weight. Therefore, the VNIIGD Institute developed a modified version of pressure-reducing valve, called the PRK (with maximum inlet pressure of 5 MPa, outlet pressure ranging from 0.5 to 1.5 MPa, water discharge 80 m/sup 3//h and weighing 5 kg). Design of the PRK pressure-reducing valve is shown.

The key design features of the Indian advanced heavy water reactor

International Nuclear Information System (INIS)

Sinha, R.K.; Kakodkar, A.; Anand, A.K.; Venkat Raj, V.; Balakrishnan, K.

1999-01-01

The 235 MWe Indian Advanced Heavy Water Reactor (AHWR) is a vertical, pressure tube type, boiling light water cooled reactor. The three key specific features of design of the AHWR, having a large impact on its viability, safety and economics, relate to its reactor physics, coolant channel, and passive safety features. The reactor physics design is tuned for maximising use of thorium based fuel, and achieving a slightly negative void coefficient of reactivity. The fulfilment of these requirements has been possible through use of PuO 2 -ThO 2 MOX, and ThO 2 -U 233 O 2 MOX in different pins of the same fuel cluster, and use of a heterogeneous moderator consisting of pyrolytic carbon and heavy water in 80%-20% volume ratio. The coolant channels of AHWR are designed for easy replaceability of pressure tubes, during normal maintenance shutdowns. The removal of pressure tube along with bottom end-fitting, using rolled joint detachment technology, can be done in AHWR coolant channels without disturbing the top end-fitting, tail pipe and feeder connections, and all other appendages of the coolant channel. The AHWR incorporates several passive safety features. These include core heat removal through natural circulation, direct injection of Emergency Core Coolant System (ECCS) water in fuel, passive systems for containment cooling and isolation, and availability of a large inventory of borated water in overhead Gravity Driven Water Pool (GDWP) to facilitate sustenance of core decay heat removal, ECCS injection, and containment cooling for three days without invoking any active systems or operator action. Incorporation of these features has been done together with considerable design simplifications, and elimination of several reactor grade equipment. A rigorous evaluation of feasibility of AHWR design concept has been completed. The economy enhancing aspects of its key design features are expected to compensate for relative complexity of the thorium fuel cycle activities

Durable Suit Bladder with Improved Water Permeability for Pressure and Environment Suits

Science.gov (United States)

Bue, Grant C.; Kuznetz, Larry; Orndoff, Evelyne; Tang, Henry; Aitchison, Lindsay; Ross, Amy

2009-01-01

Water vapor permeability is shown to be useful in rejecting heat and managing moisture accumulation in launch-and-entry pressure suits. Currently this is accomplished through a porous Gortex layer in the Advanced Crew and Escape Suit (ACES) and in the baseline design of the Constellation Suit System Element (CSSE) Suit 1. Non-porous dense monolithic membranes (DMM) that are available offer potential improvements for water vapor permeability with reduced gas leak. Accordingly, three different pressure bladder materials were investigated for water vapor permeability and oxygen leak: ElasthaneTM 80A (thermoplastic polyether urethane) provided from stock polymer material and two custom thermoplastic polyether urethanes. Water vapor, carbon dioxide and oxygen permeability of the DMM's was measured in a 0.13 mm thick stand-alone layer, a 0.08 mm and 0.05 mm thick layer each bonded to two different nylon and polyester woven reinforcing materials. Additional water vapor permeability and mechanical compression measurements were made with the reinforced 0.05 mm thick layers, further bonded with a polyester wicking and overlaid with moistened polyester fleece thermal underwear .This simulated the pressure from a supine crew person. The 0.05 mm thick nylon reinforced sample with polyester wicking layer was further mechanically tested for wear and abrasion. Concepts for incorporating these materials in launch/entry and Extravehicular Activity pressure suits are presented.

Pressure vessel design

International Nuclear Information System (INIS)

Annaratone, D.

2007-01-01

This book guides through general and fundamental problems of pressure vessel design. It moreover considers problems which seem to be of lower importance but which turn out to be crucial in the design phase. The basic approach is rigorously scientific with a complete theoretical development of the topics treated, but the analysis is always pushed so far as to offer concrete and precise calculation criteria that can be immediately applied to actual designs. This is accomplished through appropriate algorithms that lead to final equations or to characteristic parameters defined through mathematical equations. The first chapter describes how to achieve verification criteria, the second analyzes a few general problems, such as stresses of the membrane in revolution solids and edge effects. The third chapter deals with cylinders under pressure from the inside, while the fourth focuses on cylinders under pressure from the outside. The fifth chapter covers spheres, and the sixth is about all types of heads. Chapter seven discusses different components of particular shape as well as pipes, with special attention to flanges. The eighth chapter discusses the influence of holes, while the ninth is devoted to the influence of supports. Finally, chapter ten illustrates the fundamental criteria regarding fatigue analysis. Besides the unique approach to the entire work, original contributions can be found in most chapters, thanks to the author's numerous publications on the topic and to studies performed ad hoc for this book. (orig.)

Water Pressure Distribution on a Flying Boat Hull

Science.gov (United States)

Thompson, F L

1931-01-01

This is the third in a series of investigations of the water pressures on seaplane floats and hulls, and completes the present program. It consisted of determining the water pressures and accelerations on a Curtiss H-16 flying boat during landing and taxiing maneuvers in smooth and rough water.

Where Did the Water Go?: Boyle's Law and Pressurized Diaphragm Water Tanks

Science.gov (United States)

Brimhall, James; Naga, Sundar

2007-01-01

Many homes use pressurized diaphragm tanks for storage of water pumped from an underground well. These tanks are very carefully constructed to have separate internal chambers for the storage of water and for the air that provides the pressure. One might expect that the amount of water available for use from, for example, a 50-gallon tank would be…

The photovoltaic-powered water desalination plant 'SORO' design, start up, operating experience

Science.gov (United States)

Neuhaeusser, G.; Mohn, J.; Petersen, G.

Design features, operational parameters, and test results of a year of operation of the SORO prototype photovoltaic (PV) reverse osmosis salt water desalinization plant are described. Chemicals are added to the salt water to control the pH, prevent formation of compounds which could plug the flow system, and kill bacteria and slime which might grow in the solution. The water is pressurized and forced into contact with membranes which separate the fresh water from the brackish or sea water. The flow rate in the project was 180 l/h, with the main electrical energy load being the high pressure pump and the well pump. Batteries are charged before current is switched to power the desalinization system. The plant yielded 1.50 cu of fresh water/day and is concluded to be a viable design for scale-up to larger production figures, besides being economically competitive with solar desalinization installations where the salt content is 2000 ppm.

Soviet precision timekeeping research and technology

Energy Technology Data Exchange (ETDEWEB)

Vessot, R.F.C.; Allan, D.W.; Crampton, S.J.B.; Cutler, L.S.; Kern, R.H.; McCoubrey, A.O.; White, J.D.

1991-08-01

This report is the result of a study of Soviet progress in precision timekeeping research and timekeeping capability during the last two decades. The study was conducted by a panel of seven US scientists who have expertise in timekeeping, frequency control, time dissemination, and the direct applications of these disciplines to scientific investigation. The following topics are addressed in this report: generation of time by atomic clocks at the present level of their technology, new and emerging technologies related to atomic clocks, time and frequency transfer technology, statistical processes involving metrological applications of time and frequency, applications of precise time and frequency to scientific investigations, supporting timekeeping technology, and a comparison of Soviet research efforts with those of the United States and the West. The number of Soviet professionals working in this field is roughly 10 times that in the United States. The Soviet Union has facilities for large-scale production of frequency standards and has concentrated its efforts on developing and producing rubidium gas cell devices (relatively compact, low-cost frequency standards of modest accuracy and stability) and atomic hydrogen masers (relatively large, high-cost standards of modest accuracy and high stability). 203 refs., 45 figs., 9 tabs.

Soviet precision timekeeping research and technology

International Nuclear Information System (INIS)

Vessot, R.F.C.; Allan, D.W.; Crampton, S.J.B.; Cutler, L.S.; Kern, R.H.; McCoubrey, A.O.; White, J.D.

1991-08-01

This report is the result of a study of Soviet progress in precision timekeeping research and timekeeping capability during the last two decades. The study was conducted by a panel of seven US scientists who have expertise in timekeeping, frequency control, time dissemination, and the direct applications of these disciplines to scientific investigation. The following topics are addressed in this report: generation of time by atomic clocks at the present level of their technology, new and emerging technologies related to atomic clocks, time and frequency transfer technology, statistical processes involving metrological applications of time and frequency, applications of precise time and frequency to scientific investigations, supporting timekeeping technology, and a comparison of Soviet research efforts with those of the United States and the West. The number of Soviet professionals working in this field is roughly 10 times that in the United States. The Soviet Union has facilities for large-scale production of frequency standards and has concentrated its efforts on developing and producing rubidium gas cell devices (relatively compact, low-cost frequency standards of modest accuracy and stability) and atomic hydrogen masers (relatively large, high-cost standards of modest accuracy and high stability). 203 refs., 45 figs., 9 tabs

Glasnost and Secrecy in the Soviet Military

Science.gov (United States)

1990-12-21

the most vicious and xenophobic brand of Russian chauvinism, complete with witch-hunts and spymania. Secrecy was also important for enhancing the...the Soviet Armed Forces, a significant factor tor a military establishment historically used to ’ie position of the underdog because of the Soviet

Remote-controlled television for locating leaking tubes in pressurized-water reactor steam generators

International Nuclear Information System (INIS)

Cormault, P.; Denis, J.

1978-01-01

The Scarabee system is designed for observation of the tubes in water boxes of pressurized-water reactor nuclear-power-station steam generators. It consists essentially of a camera and a projector used as a marker, both of which swivel freely. The whole unit is housed in a water-tight container which can easily be decontaminated. Remote control of camera and marker movement is carried out from a console. (author)

The Text of the Agreement of 17 November 1977 between the Agency and India for the Application of Safeguards in Connection with the Supply of Heavy Water from the Soviet Union

International Nuclear Information System (INIS)

1978-07-01

The text of the Agreement of 17 November 1977 between the Agency and India for the application of safeguards in connection with the supply of heavy water from the Union of Soviet Socialist Republics is reproduced in this document for the information of all Members

The Text of the Agreement of 17 November 1977 between the Agency and India for the Application of Safeguards in Connection with the Supply of Heavy Water from the Soviet Union

Energy Technology Data Exchange (ETDEWEB)

NONE

1978-07-15

The text of the Agreement of 17 November 1977 between the Agency and India for the application of safeguards in connection with the supply of heavy water from the Union of Soviet Socialist Republics is reproduced in this document for the information of all Members.

Drilling Performance of Rock Drill by High-Pressure Water Jet under Different Configuration Modes

Directory of Open Access Journals (Sweden)

Songyong Liu

2017-01-01

Full Text Available In the rock drilling progress, the resistant force results in tools failure and the low drilling efficiency; thus, it is necessary to reduce the tools failure and enhance the drilling efficiency. In this paper, different configuration modes of drilling performance assisted with water jet are explored based on the mechanism and experiment analysis of rock drilling assisted with water jet. Moreover, the rotary sealing device with high pressure is designed to achieve the axial and rotation movement simultaneously as well as good sealing effect under high-pressure water jet. The results indicate that the NDB and NFB have better effects on drilling performance compared with that of NSB. Moreover, the high-pressure water jet is helpful not only to reduce the drill rod deflection, but also to reduce the probability of drill rod bending and improve the drill rod service life.

Ex-Soviet Union: oil exporter or importer

International Nuclear Information System (INIS)

Khartukov, E.M.

1993-01-01

Perestroika of the Soviet economy and the political disintegration of the USSR have raised questions about the international ramifications of the ongoing economic and political developments in the world's largest oil-producing country. First of all, it relates to their impact on the quantity and quality of oil exports from the former Soviet Union (FSU). On the other hand, the opening of the national oil industry to foreign investors focuses their ever growing attention on the complicated internal, inter-republic oil issues which emerged after the sudden fragmentation of the Soviet oil empire into a dozen of sovereign but still interdependent parts. 1 fig., 7 tabs

Former Soviet Union Hydrological Snow Surveys, 1966-1996

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — The Former Soviet Union Hydrological Snow Surveys are based on observations made by personnel at 1,345 sites throughout the Former Soviet Union between 1966 and...

Control system design and validation platform development for small pressurized water reactors (SPWR) by coupling an engineering simulator and MATLAB/Simulink

International Nuclear Information System (INIS)

Sun, Peiwei; Zhao, Huanhuan; Liao, Longtao; Zhang, Jianmin; Su, Guanghui

2017-01-01

Highlights: • An SPWR control system design and validation platform is developed. • The platform is developed by coupling MATLAB/Simulink and an engineering simulator. • SPWR is modeled using Relap5 and preliminary control system is designed. • The platform is verified through numerical simulation over two typical load patterns. - Abstract: Significant progress has been made in the development of the small pressurized water reactors (SPWR). Unique characteristics of the SPWR deliver challenges to its control system design. In order to facilitate the control system design process and enhance its efficiency, it is important and necessary to establish a control system design and validation platform. Using shared memory technology, an engineering simulator coupled with MATLAB/Simulink is employed to achieve this objective. Shared memory is an efficient method to exchange data within programs. Dynamic data exchange and simulation time synchronization methods are particularly treated. To verify the platform, an SPWR with its control system is modeled using the platform and the simulator. Thermal-hydraulic modeling of the SPWR is carried out using Relap5, and its nodalization is introduced. The objectives of the control strategy are to maintain the average coolant temperature linearly varying with the reactor power and steam pressure constant. A preliminary SPWR control system is designed with proportional-integral-derivative (PID) controllers, and is implemented in MATLAB/Simulink associated with the engineering simulator. Subsequently, in order to evaluate the performance of the established simulation platform, transients of abrupt load changes and wide range load changes are simulated and simulation results are verified against those obtained from the engineering simulator alone. It is demonstrated that simulation results of both platforms are consistent with each other, which proves that the coupling of engineering simulator and MATLAB/Simulink is successful

3-D Soviet Style: A Presentation on Lessons Learned from the Soviet Experience in Afghanistan

Science.gov (United States)

2007-10-01

auteurs se penchent sur les aspects stratégiques, opérationnels et tactiques de l’action soviétique. L’étude se fonde sur de l’information actualisée...publiée en russe et en anglais. Les données statistiques sur le conflit ont également été prises en compte. Les auteurs , MM. Anton Minkov et...communication and to the efforts the Soviets made in building Afghan security forces. It includes information on the theory and practice of Soviet

Carbon in the Former Soviet Union: The Current Balance

Science.gov (United States)

Woodwell, G. M.; Stone, T. A.; Houghton, R. A.

1997-01-01

This work has been carried out in a period of great changes in Russia that have brought extreme hardships to the scientific community. We have been fortunate in establishing excellent relationships with the Russian scientific community and believe we have helped to retain coherence in circumstances where the continuation of research was in doubt. We have learned much and have been effective in advancing, even establishing, scholars and programs in Russia that might not otherwise have survived the transition. The vigor of the International Boreal Forest Research Association (IBFRA) is one sign of the value and success of these activities. Largely due to the current political and economic transitions in the former Soviet Union, the forests of much of the FSU are under reduced logging pressure. In addition, there is a decline in air pollution as heavy industry has waned, at least for now. Russian forestry statistics and our personal experience indicate a decline, perhaps as high as 60%, in forest harvesting over the last few years. But, new international market pressures on the forests exist in European Russia and in the Far East. The central government, still the "owner" of Russian forests, is having difficulty maintaining control over forest use and management particularly in the Far East and among the southern territories that have large, nonRussian ethnic populations. Extraordinarily large areas of mixed forest and grasslands, sparse or open forests, and mixed forests and tundra must be considered when calculating forest area It is insufficient to think of Russia as simply forest and nonforest Forest productivity, measured as growth of timber, appears to be in decline in all areas of Russia except in European Russia. Most information and publications on the recent history of these forests is heavily dependent on statistical data from the Soviet era. The interpretation of these data is very much open to debate. Anatoly Shwidenko, a long term collaborator and former

Is Soviet Defense Policy Becoming Civilianized?

Science.gov (United States)

1990-08-01

Larionov, a consultant to the institute, both at RAND and in Moscow; and Drs. Alexei Arbatov and Aleksandr Savelyev and several of their colleagues during...Soviet defense industry resources to civilian use is presented in Arthur J. Alexander , Perestroika and Change in Soviet Weapons Acquisition, The RAND...1986, especially pp. 101-102. 17 18 the more prominent younger specialists like Alexei Arbatov, Andrei Kokoshin, and Aleksandr Savelyev have long been

Pressurized water reactor flow arrangement

International Nuclear Information System (INIS)

Gibbons, J.F.; Knapp, R.W.

1980-01-01

A flow path is provided for cooling the control rods of a pressurized water reactor. According to this scheme, a small amount of cooling water enters the control rod guide tubes from the top and passes downwards through the tubes before rejoining the main coolant flow and passing through the reactor core. (LL)

Solubility and physical properties of sugars in pressurized water

International Nuclear Information System (INIS)

Saldaña, Marleny D.A.; Alvarez, Víctor H.; Haldar, Anupam

2012-01-01

Highlights: ► Sugar solubility in pressurized water and density at high pressures were measured. ► Glucose solubility was higher than that of lactose as predicted by their σ-profiles. ► Sugar aqueous solubility decreased with an increase in pressure from 15 to 120 bar. ► Aqueous glucose molecular packing shows high sensitivity to pressure. ► The COSMO-SAC model qualitatively predicted the sugar solubility data. - Abstract: In this study, the solubility, density, and refractive index of glucose and lactose in water as a function of temperature were measured. For solubility of sugars in pressurized water, experimental data were obtained at pressures of (15 to 120) bar and temperatures of (373 to 433) K using a dynamic flow high pressure system. Density data for aqueous sugar solutions were obtained at pressures of (1 to 300) bar and temperatures of (298 to 343) K. The refractive index of aqueous sugar solutions was obtained at 293 K and atmospheric pressure. Activity coefficient models, Van Laar and the Conductor-like Screening Model-Segment Activity Coefficient (COSMO-SAC), were used to fit and predict the experimental solubility data, respectively. The results obtained showed that the solubility of both sugars in pressurized water increase with an increase in temperature. However, with the increase of pressure from 15 bar to 120 bar, the solubility of both sugars in pressurized water decreased. The Van Laar model fit the experimental aqueous solubility data with deviations lower than 13 and 53% for glucose and lactose, respectively. The COSMO-SAC model predicted qualitatively the aqueous solubility of these sugars.

High-pressure-induced water penetration into 3-isopropylmalate dehydrogenase

International Nuclear Information System (INIS)

Nagae, Takayuki; Kawamura, Takashi; Chavas, Leonard M. G.; Niwa, Ken; Hasegawa, Masashi; Kato, Chiaki; Watanabe, Nobuhisa

2012-01-01

Structures of 3-isopropylmalate dehydrogenase were determined at pressures ranging from 0.1 to 650 MPa. Comparison of these structures gives a detailed picture of the swelling of a cavity at the dimer interface and the generation of a new cleft on the molecular surface, which are accompanied by water penetration. Hydrostatic pressure induces structural changes in proteins, including denaturation, the mechanism of which has been attributed to water penetration into the protein interior. In this study, structures of 3-isopropylmalate dehydrogenase (IPMDH) from Shewanella oneidensis MR-1 were determined at about 2 Å resolution under pressures ranging from 0.1 to 650 MPa using a diamond anvil cell (DAC). Although most of the protein cavities are monotonically compressed as the pressure increases, the volume of one particular cavity at the dimer interface increases at pressures over 340 MPa. In parallel with this volume increase, water penetration into the cavity could be observed at pressures over 410 MPa. In addition, the generation of a new cleft on the molecular surface accompanied by water penetration could also be observed at pressures over 580 MPa. These water-penetration phenomena are considered to be initial steps in the pressure-denaturation process of IPMDH

Determine spray droplets on water sensitive paper (WSP) for low pressure deflector nozzle using image J

Science.gov (United States)

Sies, M. F.; Madzlan, N. F.; Asmuin, N.; Sadikin, A.; Zakaria, H.

2017-09-01

In this study, determine of spray droplets size (SMD) using water sensitive paper (WSP) at low fluid pressure with deflector nozzle or tangential flow nozzle model Delavan AL75 and New Design Nozzle with two different type of swirl (ND2.5 A1.0 & ND2.5 B1.0). These three deflected flat sprays have used at different liquid mixing ratio. These liquid mixture ratios are pure water, 10% of lime juice + 90% of water (L10W90) and 30% of lime juice + 70% of water (L30W70). WSP is used to collect the spray droplets from nozzles. The operational liquid pressure of each nozzle is 3 bar, while air operational pressures are 3 bar and 6 bar. Then, the WSP were scanned using scanner then it was analyzed using ImageJ software. ImageJ can be used for determining the diameter of droplets size on the WSP. As the results from an experiment, the AL75 nozzle recorded the lowest Sauter mean diameter which is 193.69μm at 6 bar of pressurized air while ND2.5 A1.0 recorded the highest Sauter mean diameter which is 353.61µm at 3 bar of pressurized air. Summary from the experiment shows that the higher of droplet size is because of the lower air pressure (3 Bar). Then, increasing of liquid viscosity also increase the SMD. The orifice diameter for New Design nozzle (ND-2.5) is smaller than AL75, which are 2.5mm and 2.8mm respectively. The different nozzle design also gives effect the SMD. WSP is an alternative method to determine SMD for spray droplets with the low cost if compared to Phase Doppler Anemometry (PDA).

US-Soviet cooperation in countering nuclear terrorism: the role of risk reduction centers

International Nuclear Information System (INIS)

Nunn, S.; Warner, J.W.

1987-01-01

Preventing nuclear terrorism should be high on the agenda of US-Soviet relations. Indeed, the specter of nuclear terrorism, more than any other factor originally prompted and has subsequently sustained the author's deep interest in US-Soviet agreements on establishment of US-Soviet Nuclear Risk Reduction Centers and other important risk-reduction measures. Such centers can play an invaluable role in facilitating discussions aimed at forestalling possible contingencies and in providing a mechanism for dampening escalatory dangers that might otherwise result from any future nuclear terrorism incident. In addition to these crucial substantive functions, the centers could serve to reassure anxious publics that the governments they have entrusted with command authority over tens of thousands of nuclear devices are giving the highest priority to reducing the risk that any of them will ever be used, whether by design or by accident. Nuclear risk Reduction Centers are an idea whose time has come

Adaptive Reference Control for Pressure Management in Water Networks

DEFF Research Database (Denmark)

Kallesøe, Carsten; Jensen, Tom Nørgaard; Wisniewski, Rafal

2015-01-01

Water scarcity is an increasing problem worldwide and at the same time a huge amount of water is lost through leakages in the distribution network. It is well known that improved pressure control can lower the leakage problems. In this work water networks with a single pressure actuator and several....... Subsequently, these relations are exploited in an adaptive reference control scheme for the actuator pressure that ensures constant pressure at the critical points. Numerical experiments underpin the results. © Copyright IEEE - All rights reserved....

Assessment of water pipes durability under pressure surge

Science.gov (United States)

Pham Ha, Hai; Minh, Lanh Pham Thi; Tang Van, Lam; Bulgakov, Boris; Bazhenova, Soafia

2017-10-01

Surge phenomenon occurs on the pipeline by the closing valve or pump suddenly lost power. Due to the complexity of the water hammer simulation, previous researches have only considered water hammer on the single pipe or calculation of some positions on water pipe network, it have not been analysis for all of pipe on the water distribution systems. Simulation of water hammer due to closing valve on water distribution system and the influence level of pressure surge is evaluated at the defects on pipe. Water hammer on water supply pipe network are simulated by Water HAMMER software academic version and the capacity of defects are calculated by SINTAP. SINTAP developed from Brite-Euram projects in Brussels-Belgium with the aim to develop a process for assessing the integrity of the structure for the European industry. Based on the principle of mechanical fault, indicating the size of defects in materials affect the load capacity of the product in the course of work, the process has proposed setting up the diagram to fatigue assessment defect (FAD). The methods are applied for water pipe networks of Lien Chieu district, Da Nang city, Viet Nam, the results show the affected area of wave pressure by closing the valve and thereby assess the greatest pressure surge effect to corroded pipe. The SINTAP standard and finite element mesh analysis at the defect during the occurrence of pressure surge which will accurately assess the bearing capacity of the old pipes. This is one of the bases to predict the leakage locations on the water distribution systems. Amount of water hammer when identified on the water supply networks are decreasing due to local losses at the nodes as well as the friction with pipe wall, so this paper adequately simulate water hammer phenomena applying for actual water distribution systems. The research verified that pipe wall with defect is damaged under the pressure surge value.

Scientific and technical training in the Soviet Union

Science.gov (United States)

Spearman, M. L.

1983-01-01

Specific features and observations on the Soviet educational system and areas of apparent effectiveness are presented, noting that the literacy rate is over 98 percent in 1982. Educational goals are reoriented every five years to match with other projections of five-year plans. The Soviet constitution established strong educational goals, including schools, correspondence courses, lectures in native tongues, free tuition, and vocational training. The educational pattern from pre-school through graduate school lasts over 28 yr and contains two 2-yr periods of work, confined to specialties after graduate school. Mathematics is emphasized, as are physics, Marxism, and a foreign language. Approximately 300,000 engineers were graduated in the Soviet Union in 1982, compared with the 20-yr U.S. average of 50,000/yr. About 2/3 of Soviet engineers participate in defense work, a number which is four times the total number of U.S. engineers. It is asserted that the continual indoctrination, organization, and practical work experience will guarantee that the Soviet state will remain a dominant force in the world as long as centralized state control can be carried out.

Swelling pressure and water absorption property of compacted granular bentonite during water absorption

International Nuclear Information System (INIS)

Oyamada, T.; Komine, H.; Murakami, S.; Sekiguchi, T.; Sekine, I.

2012-01-01

Document available in extended abstract form only. Bentonite is currently planned to be used as buffer materials in engineered barrier of radioactive waste disposal. Granular bentonites are expected as the materials used in constructions as buffer materials by in-situ compaction methods. After applying these buffer materials, it is expected that the condition of the buffer area changes in long-term by the seepage of groundwater into buffer area. Therefore, it is important to understand water movement and swelling behavior of the buffer materials for evaluating the performance of engineered barrier. In this study, we investigated water absorption property and swelling pressure of compacted granular bentonite. Specifically, the process of swelling pressure and amount of water absorption of granular bentonite-GX (Kunigel-GX, produced at the Tsukinuno mine in Japan) were observed by laboratory tests. To discuss the influence of maximum grain size of bentonite particle on swelling pressure and water absorption property, two types of samples were used. One is granular sample which is Bentonite-GX controlled under 2 mm the maximum grain size, the other is milled sample which is Bentonite-GX with the maximum grain size under 0.18 mm by milling with the agate mortar. In addition, the mechanism on the swelling pressure of compacted granular bentonite was considered and discussed. In the cases of granular sample, swelling pressure increases rapidly, then gradually continues to increase up to maximum value. In the cases of milled sample, swelling pressure also increases rapidly at first. However, then its value decreases before progressing of gradual increase continues. Especially, this trend was clearly observed at a relatively low dry density. At the peaks of these curves, the swelling pressure of granular samples is lower than that of milled samples. In addition, the increasing of swelling pressure by the time the peak observed during the process of swelling pressure from

Water Pressure Distribution on a Twin-Float Seaplane

Science.gov (United States)

Thompson, F L

1930-01-01

This is the second of a series of investigations to determine water pressure distribution on various types of seaplane floats and hulls, and was conducted on a twin-float seaplane. It consisted of measuring water pressures and accelerations on a TS-1 seaplane during numerous landing and taxiing maneuvers at various speeds and angles. The results show that water pressures as great as 10 lbs. per sq. in.may occur at the step in various maneuvers and that pressures of approximately the same magnitude occur at the stern and near the bow in hard pancake landings with the stern way down. At the other parts of the float the pressures are less and are usually zero or slightly negative for some distance abaft the step. A maximum negative pressure of 0.87 lb. Per square inch was measured immediately abaft the step. The maximum positive pressures have a duration of approximately one-twentieth to one-hundredth second at any given location and are distributed over a very limited area at any particular instant.

Pressurized-water coolant nuclear reactor steam generator

International Nuclear Information System (INIS)

Mayer, H.; Schroder, H.J.

1975-01-01

A description is given of a pressurized-water coolant nuclear reactor steam generator having a vertical housing for the steam generating water and containing an upstanding heat exchanger to which the pressurized-water coolant passes and which is radially surrounded by a guide jacket supporting a water separator on its top. By thermosiphon action the steam generating water flows upward through and around the heat exchanger within the guide chamber to the latter's top from which it flows radially outwardly and downwardly through a down draft space formed between the outside of the jacket and the housing. The water separator discharges separated water downwardly. The housing has a feedwater inlet opening adjacent to the lower portion of the heat exchanger, providing preheating of the introduced feedwater. This preheated feedwater is conveyed by a duct upwardly to a location where it mixes with the water discharged from the water separator

Soviet Counterinsurgency Operations in Afghanistan (1979-1988)

Science.gov (United States)

2010-04-29

Soviet commitment in Afghanistan. was to be an "economy of force" mission, with the focus of Red Army combat power to remain in the European theatre ...critically for its operational and tactical resupply capability. ’’The Soviets in Afghanis4Ul,li1ce the Americansin Vietnam, discovered thai helicopters were

Fissures in rock under water pressure, implications on stability : 3 unusual cases

Energy Technology Data Exchange (ETDEWEB)

Helwig, P.C. [Helwig Hydrotechnique Ltd., St. John' s, NL (Canada)

2006-07-01

The presence of water in rock joints has important implications on the stability of rock foundations. Appropriate analyses are needed to assess the stability of dam foundations, abutments and rock walls. This paper presented 3 case studies in which the freezing of seepage flows in rock joints and transient pressure in rock walls were investigated: (1) an assessment of the effects of freezing water in rock joints at the Paradise River arch dam in Newfoundland; (2) stability of rock walls in the unlined power tunnel of the Cat Arm hydroelectric development in Newfoundland due to transient pressures; and (3) assessing the influence of fluctuating water pressures in a stilling basin excavated in rock. After an investigation of the Paradise River canyon walls, a drainage system comprised of peripheral drain holes was drilled into the foundation and walls at regular intervals to intercept seepage flows and to relieve uplift water pressures. However, no special treatment was found for the potential freezing of water in the joints of the dam walls and foundation. The Cat Arm tunnel was used to study the depth at which significant transient pressures can be used to assess rock stability. Rock properties, typical fracture apertures and spacing were assumed and joint deformability was taken into account. An axisymmetric solution was obtained by considering the continuity and flow through an annular element of the rock wall. A finite difference method was used to solve the resulting nonlinear differential equation. In the final case study, blast-damaged rock was undermining the toe of a spillway. A cut-off wall was constructed as a series of drilled, cast-in-place concrete caisson piles. Criteria for the design included extending the cut-off wall to a depth beyond the effects of fluctuating surface pressures. Depth was assessed by considering the transient behaviour of water penetrating a sub-vertical joint subject exposed to fluctuating pressures. Results of the calculations

FREUDIAN COMPLEXES OF SOVIET AND POST-SOVIET PHILOLOGY IN STUDYING THE GOSPEL TEXT IN RUSSIAN LITERATURE

OpenAIRE

Ivan Andreevich Esaulov

2012-01-01

The article looks at a number of marginal concepts of Freudian theory and at his articles on Dostoevsky that revealed the 'cultural unconscious' of the founder of psychoanalysis. We point at the similarities between Freud's cultural unconscious – with its negativity against of the “Christian God”, historical Russia and Russian people – and the Soviet type of culture, especially in its early period (1920s – early 1930s). The ardor of Freudo-Marxism typical for the highest levels of Soviet powe...

Analytical studies on optimization of containment design pressure

International Nuclear Information System (INIS)

Haware, S.K.; Ghosh, A.K.; Kushwaha, H.S.

2005-01-01

The containment of the proposed Advanced Heavy Water Reactor (AHWR) is divided into two main volumes viz. V1 and V2 interconnected by vent system via suppression pool. The arrangement is such that the volume V2 surrounds the volume V1 (see Fig.1). Blow Out Panels (BOPs), installed on volume V1 are designed to rupture at a differential pressure of 50 kPa. The containment was analysed using the in-house developed code CONTRAN, for three different scenario considered viz. (i) Loss of Coolant Accident (LOCA) involving double ended break in the downcomer pipe, (ii) LOCA involving double ended break in the reactor inlet header and (iii) Main Steam Line Break (MSLB) Accident. It was revealed that the accident involving the double-ended break of reactor inlet header results in the maximum value of the containment peak pressure. Results of the analyses indicated that the size of the BOP has bearing on the containment peak pressure. Therefore, five cases were analysed, varying the size of BOP from 0 to 10 m 2 , in order to quantify the influence of the size of BOP on the containment peak pressure. The blowdown mass and energy discharge data calculated using the code RELAP5/MOD3.2 was used in the analysis. It was observed that the vents are cleared in around 0.41 seconds into the accident. The containment peak pressures obtained in various cases are presented in Fig.2. The containment peak pressure varies with the size of BOP and passes through minima for a BOP size of around 5 m 2 . There are two flow processes, competing with each other viz. the steam-air mixture passage through the vent system via suppression pool and direct passage of steam air mixture through BOP bypassing the suppression pool. Though the energy suppression efficiency of the suppression pool decreases with increasing size of BOP, the pressure suppression efficiency was found to be maximum at around 5 m 2 size of BOP. The containment peak pressure passing through minima indicates that there is a scope for

Heat insulation device for reactor pressure vessel in water

International Nuclear Information System (INIS)

Nakamura, Heiichiro; Tanaka, Yoshimi.

1993-01-01

Outer walls of a reactor pressure vessel are covered with water-tight walls made of metals. A heat insulation metal material is disposed between them. The water tight walls are joined by welding and flanges. A supply pipeline for filling gases and a discharge pipeline are in communication with the inside of the water tight walls. Further, a water detector is disposed in the midway of the gas discharge pipeline. With such a constitution, the following advantages can be attained. (1) Heat transfer from the reactor pressure vessel to water of a reactor container can be suppressed by filled gases and heat insulation metal material. (2) Since the pressure at the inside of the water tight walls can be equalized with the pressure of the inside of the reactor container, the thickness of the water-tight walls can be reduced. (3) Since intrusion of water to the inside of the walls due to rupture of the water tight walls is detected by the water detector, reactor scram can be conducted rapidly. (4) The sealing property of the flange joint portion is sufficient and detaching operation thereof is easy. (I.S.)

High pressure water jet mining machine

Science.gov (United States)

Barker, Clark R.

1981-05-05

A high pressure water jet mining machine for the longwall mining of coal is described. The machine is generally in the shape of a plowshare and is advanced in the direction in which the coal is cut. The machine has mounted thereon a plurality of nozzle modules each containing a high pressure water jet nozzle disposed to oscillate in a particular plane. The nozzle modules are oriented to cut in vertical and horizontal planes on the leading edge of the machine and the coal so cut is cleaved off by the wedge-shaped body.

FREUDIAN COMPLEXES OF SOVIET AND POST-SOVIET PHILOLOGY IN STUDYING THE GOSPEL TEXT IN RUSSIAN LITERATURE

Directory of Open Access Journals (Sweden)

Ivan Andreevich Esaulov

2012-11-01

Full Text Available The article looks at a number of marginal concepts of Freudian theory and at his articles on Dostoevsky that revealed the 'cultural unconscious' of the founder of psychoanalysis. We point at the similarities between Freud's cultural unconscious – with its negativity against of the “Christian God”, historical Russia and Russian people – and the Soviet type of culture, especially in its early period (1920s – early 1930s. The ardor of Freudo-Marxism typical for the highest levels of Soviet power and humanitarian studies lay in their striving towards a complete restructuring of Russian culture, state and man itself. Russian literature is interpreted on the basis of anti-Christian tenets and a set of criteria absolutely alien to Russian literature. We show that this mental attitude has not been overcome by post-Soviet literary criticism. Our article is a call on scholars of Russian literature to get rid of their Freudian complexes in the treatment of Russian culture.

Water Delivery--It's All about Pressure

Science.gov (United States)

Roman, Harry T.

2005-01-01

There is a great deal of wisdom in the old saying "water seeks its level." In fact, the concept has bearing on a very practical side of human life as well, since the public water delivery system is based on it. In this article, the author discusses the concept behind water pressure and describes how the water systems work based on this concept.…

Ultra-high pressure water jet: Baseline report

International Nuclear Information System (INIS)

1997-01-01

The ultra-high pressure waterjet technology was being evaluated at Florida International University (FIU) as a baseline technology. In conjunction with FIU's evaluation of efficiency and cost, this report covers the evaluation conducted for safety and health issues. It is a commercially available technology and has been used for various projects at locations throughout the country. The ultra-high pressure waterjet technology acts as a cutting tool for the removal of surface substrates. The Husky trademark pump feeds water to a lance that directs the high pressure water at the surface to be removed. The safety and health evaluation during the testing demonstration focused on two main areas of exposure. These were dust and noise. The dust exposure was found to be minimal, which would be expected due to the wet environment inherent in the technology, but noise exposure was at a significant level. Further testing for noise is recommended because of the outdoor environment where the testing demonstration took place. In addition, other areas of concern found were arm-hand vibration, ergonomics, heat stress, tripping hazards, electrical hazards, lockout/tagout, fall hazards, slipping hazards, hazards associated with the high pressure water, and hazards associated with air pressure systems

Fragmenting pastoral mobility: Changing grazing patterns in Post-Soviet Kazakhstan

Science.gov (United States)

Carol Kerven; Ilya Ilych Alimaev; Roy Behnke; Grant Davidson; Nurlan Malmakov; Aidos Smailov; Iain Wright

2006-01-01

Kazak nomads were seasonally mobile in the pre-Soviet period, in response to climate variability and landscape heterogeneity. The scale of these movements was interrupted during the Soviet period, but some degree of mobility remained. Mobility virtually ceased in the post-Soviet 1990s, but is reemerging as flock numbers rebound from the mid 1990s population crash.

Soviet Theater Nuclear Forces’ Issues.

Science.gov (United States)

1979-12-01

survivability) of those staffs. 18 Receit Soviet accounts of the "revolution in military affairs" stress the growing operational role of the General Staff...e.g., 29 economic) means and (ii) the West is preparing to take military advantage of its growing relative strength. The other factor is China. It seems...simple model of Soviet theater nuclear doctrine, might as well go hunting unicorns . He will not find it because, in any meaningful sense, it does not

Thermal Hydraulic Integral Effect Tests for Pressurized Water Reactors

International Nuclear Information System (INIS)

Baek, Won Pil; Song, C. H.; Kim, Y. S.

2007-02-01

The objectives of the project are to construct a thermal-hydraulic integral effect test facility and to perform the tests for design, operation, and safety regulation of pressurized water reactors. In the first phase of this project (1997.8∼2002.3), the basic technology for thermal-hydraulic integral effect tests was established and the basic design of the test facility was accomplished. In the second phase (2002.4∼2005.2), an optimized design of the ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) was established and the construction of the facility was almost completed. In the third phase (2005.3∼2007.2), the construction and commission tests of the ATLAS are to be completed and some first-phase tests are to be conducted

Nationalism and social welfare in the post-Soviet context.

Science.gov (United States)

Chandler, Andrea

2011-01-01

This paper offers hypotheses on the role that state social welfare measures can play in reflecting nationalism and in aggravating interethnic tensions. Social welfare is often overlooked in theoretical literature on nationalism, because of the widespread assumption that the welfare state promotes social cohesion. However, social welfare systems may face contradictions between the goal of promoting universal access to all citizens on the one hand, and social pressures to recognize particular groups in distinct ways on the other. Examples from the post-Soviet context (particularly Russia) are offered to illustrate the ways in which social welfare issues may be perceived as having ethnic connotations.

Dual pressurized light water reactor producing 2000 M We

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-10-15

The dual unit optimizer 2000 M We (Duo2000) is proposed as a new design concept for large nuclear power plant. Duo is being designed to meet economic and safety challenges facing the 21 century green and sustainable energy industry. Duo2000 has two nuclear steam supply systems (NSSS) of the unit nuclear optimizer (Uno) pressurized water reactor (PWR) in a single containment so as to double the capacity of the plant. Uno is anchored to the optimized power reactor 1000 M We (OPR1000) of the Korea Hydro and Nuclear Power Co., Ltd. The concept of Duo can be extended to any number of PWRs or pressurized heavy water reactors (PHWR s), or even boiling water reactor (BWRs). Once proven in water reactors, the technology may even be expanded to gas cooled, liquid metal cooled, and molten salt cooled reactors. In particular, since it is required that the small and medium sized reactors (SMRs) be built as units, the concept of Duo2000 will apply to SMRs as well. With its in-vessel retention as severe accident management strategy, Duo can not only put the single most querulous PWR safety issue to end, but also pave ways to most promising large power capacity dispensing with huge redesigning cost for generation III + nuclear systems. The strengths of Duo2000 include reducing the cost of construction by decreasing the number of containment buildings from two to one, minimizing the cost of NSSS and control systems by sharing between the dual units, and lessening the maintenance cost by uniting NSSS. The technology can further be extended to coupling modular reactors as dual, triple, or quadruple units to increase their economics, thus accelerating the commercialization as well as the customization of SMRs. (Author)

The flooding incident at the Aagesta pressurized heavy water nuclear power plant

International Nuclear Information System (INIS)

Dahlgren, C.

1996-03-01

This work is an independent investigation of the consequences of the flooding incident at the Aagesta HPWR, Stockholm in May 1969. The basis for the report is an incident in which, due to short circuits in the wiring because of flooding water, the ECCS is momentarily subjected to a pressure much higher than designed for. The hypothetical scenario analyzed here is the case in which the ECCS breaks due to the high pressure. As a consequence of the break, the pressure and the water level in the reactor vessel decrease. The report is divided into three parts; First the Aagesta HPWR is described as well as the chronology of the incident, an analysis of the effects of a hypothetical break in the ECCS is then developed. The second part is a scoping analysis of the incident, modeling the pressure decrease and mass flow rate out of the break. The heat-up of the core, and the core degradation was modeled as well. The third part is formed by a RELAP5/MOD3.1 modeling of the Aagesta HPWR. 18 refs

Kimchi, seaweed, and seasoned carrot in the Soviet culinary culture: the spread of Korean food in the Soviet Union and Korean diaspora

OpenAIRE

Changzoo Song

2016-01-01

The half-million Soviet Koreans (or Koryŏ saram) in the former Soviet Union are the descendants of the ethnic Koreans who migrated to the Russian Far East in the late 19th and early 20th centuries from the northern parts of the Korean peninsula. Their settlements were established in the wide areas of the Russian Far East, including the urban areas around Vladivostok. They were, however, forced-migrated to Central Asia in late 1937 under Stalin's rule. From Central Asia, these Soviet Koreans w...

The installation welding of pressure water reactor coolant piping

International Nuclear Information System (INIS)

Deng Feng

2010-01-01

Large pressure water reactor nuclear power plants are constructing in our country. There are three symmetry standard loops in reactor coolant system. Each loop possesses a steam generator and a primary poop, in which one of the loops is equipped with a pressurizer. These components are connected with reactor pressure vessel by installation welding of the coolant piping. The integrity of reactor coolant pressure boundary is the second barrier to protect the radioactive substance from release to outside, so the safe operation of nuclear power plant is closely related to the quality of coolant piping installation welding. The heavy tube with super low carbon content austenitic stainless steel is selected for coolant piping. This kind of material has good welding behavior, but the poor thermal conductivity, the big liner expansion coefficient and the big welding deformation will cause bigger welding stress. To reduce the welding deformation, to control the dimension precision, to reduce the residual stress and to ensure the welding quality the installation sequence should be properly designed and the welding technology should be properly controlled. (authors)

Preventive measures of water hammer in the design stage of mine drainage system

International Nuclear Information System (INIS)

Wu Dongyan

2012-01-01

The mechanisms and types of water hammer accident in mine drainage system are introduced. Through calculating water hammer pressure head of pump-failure water hammer, the extent of the harm caused by water hammer can be displayed visually, therefore,the preventive measures to be taken in the design stage are put forward in order to reduce water hammer accident. (author)

Kant’s Studies in Ukrainian Philosophy of Soviet Period

Directory of Open Access Journals (Sweden)

Vadym Tytarenko

2018-04-01

Full Text Available This writing is devoted to the brief review of Immanuel Kant’s philosophy studies and receptions of his philosophical concepts within the Ukrainian philosophy of Soviet period. Such attempt is actually pertinent because nowadays we definitely need to reconsider the soviet philosophical heritage for better understanding the real value of any philosophical conclusions and worldview-concerning statements which were made in the times of soviet ideology hegemony. Additionally, mentioned reconsidering is presently urgent because Ukrainian intellectual culture is now looking for its identity and is trying to identify the stillremaining ideological totalitarian elements which spoil the originality and objectiveness of its products. The present review attempts to identify which totalitarian intentions and prejudices were used to interpret and evaluate the Immanuel Kant’s heritage in the texts written by several selected Ukrainian philosophers of the Soviet period. Nevertheless, it’s obvious that absolutely impossible to avoid talking about Georg Wilhelm Friedrich Hegel’s philosophical position interpretation by the same authors. Kant’s and Hegel’s soviet-Ukrainian interpretations were often connected, because there was a general trend of soviet Marxist history of philosophy to interpret Kant as the “worse” version of Hegel. To fulfill the general image of Kant’s philosophy interpretation in Ukrainian philosophy and its future perspectives, this paper also delivers some common information about the whole historical path of Kant’s interpretations and receptions

Response of the water status of soybean to changes in soil water potentials controlled by the water pressure in microporous tubes

Science.gov (United States)

Steinberg, S. L.; Henninger, D. L.

1997-01-01

Water transport through a microporous tube-soil-plant system was investigated by measuring the response of soil and plant water status to step change reductions in the water pressure within the tubes. Soybeans were germinated and grown in a porous ceramic 'soil' at a porous tube water pressure of -0.5 kpa for 28 d. During this time, the soil matric potential was nearly in equilibrium with tube water pressure. Water pressure in the porous tubes was then reduced to either -1.0, -1.5 or -2.0 kPa. Sap flow rates, leaf conductance and soil, root and leaf water potentials were measured before and after this change. A reduction in porous tube water pressure from -0.5 to -1.0 or -1.5 kPa did not result in any significant change in soil or plant water status. A reduction in porous tube water pressure to -2.0 kPa resulted in significant reductions in sap flow, leaf conductance, and soil, root and leaf water potentials. Hydraulic conductance, calculated as the transpiration rate/delta psi between two points in the water transport pathway, was used to analyse water transport through the tube-soil-plant continuum. At porous tube water pressures of -0.5 to-1.5 kPa soil moisture was readily available and hydraulic conductance of the plant limited water transport. At -2.0 kPa, hydraulic conductance of the bulk soil was the dominant factor in water movement.

Comparison and analysis on transient characteristics of integral pressurized water reactors

International Nuclear Information System (INIS)

Zhang, Guoxu; Xie, Heng

2017-01-01

Highlights: • Two IPWR Relap5 models with different PSS design were developed. • Postulated SBO and SBLOCA were analyzed. • PRHRS in primary PSS design showed stable performance under different scenarios. • Secondary PRHRS design faced flow instability. - Abstract: In the present work, the similarities and differences of representative IPWRs (integral pressurized water reactor) are studied, and two typical reactor design schemes are summarized. To get a comprehensive understanding of their transient characteristics, SBO (station blackout) and SBLOCA (small break LOCA) are simulated and analyzed respectively by using Relap5/Mod3.2. The calculation results show that, both designs are effective in keeping reactor safe. However, the transient features of the two designs show significant differences. In the primary side passive safety system (PSS) connection design, PRHRS (passive residual heat removal system) shows a roughly congruent performance in removing residual heat under various accidents. While in secondary side PSS connection design, the capability of PRHRS is closely related to primary coolant circulation condition. In SBLOCA analysis, different design approach shows different primary coolant water inventory change trend. And primary PSS connection design could potentially keep reactor core well covered for a longer time.

Systems design of direct-cycle supercritical-water-cooled fast reactors

International Nuclear Information System (INIS)

Oka, Yoshiaki; Koshizuka, Seiichi; Jevremovic, Tatjana; Okano, Yashushi

1995-01-01

The system design of a direct-cycle supercritical-water-cooled fast reactor is presented. The supercritical water does not exhibit a change of phase. the recirculation system, steam separator, and dryer of a boiling water reactor (BWR) are unnecessary. Roughly speaking, the reactor pressure vessel and control rods are similar to those of a pressurized water reactor, the containment and emergency core cooling system are similar to a BWR, and the balance of plant is similar to a supercritical-pressure fossil-fired power plant (FPP). the electric power of the fast converter is 1,508 MW(electric). The number of coolant loops is only two because of the high coolant enthalpy. Containment volume is much reduced. The thermal efficiency is improved 24% over a BWR. The coolant void reactivity is negative by placing thin zirconium-hydride layers between seeds and blankets. The power costs would be much reduced compared with those of a light water reactor (LWR) and a liquid-metal fast breeder reactor. The concept is based on the huge amount of experience with the water coolant technology of LWRs and FPPs. The oxidation of stainless steel cladding is avoided by adopting a much lower coolant temperature than that of the FPP

Numerical simulation of large systems: application to a pressurized water reactor

International Nuclear Information System (INIS)

Tallec, Michele.

1981-10-01

This note describes the design of a pressurized water reactor power plant simulator using a minicomputer. It contains the description of the models used to simulate the dynamic behavior of the various components of the nuclear power station (i.e. the reactor core, two steam generators, the pressurizer and the control systems associated with them); the algorithms used to integrate the resulting system of algebraic differential equations; the solution of problems associated with the use of a mini-computer; the control deck outlay designed and the variables shown on it to the user; and finally the description of tests made to validate the models used and the results obtained for various transients using plant signal is presented. These results are compared to corresponding plant signals and outputs of other, already existing models [fr

Preliminary Study on the High Efficiency Supercritical Pressure Water-Cooled Reactor for Electricity Generation

Energy Technology Data Exchange (ETDEWEB)

Bae, Yoon Yeong; Park, Jong Kyun; Cho, Bong Hyun and others

2006-01-15

This research has been performed to introduce a concept of supercritical pressure water cooled reactor(SCWR) in Korea The area of research includes core conceptual design, evaluation of candidate fuel, fluid systems conceptual design with mechanical consideration, preparation of safety analysis code, and construction of supercritical pressure heat transfer test facility, SPHINX, and preliminary test. As a result of the research, a set of tools for the reactor core design has been developed and the conceptual core design with solid moderator was proposed. The direct thermodynamic cycle has been studied to find a optimum design. The safety analysis code has also been adapted to supercritical pressure condition. A supercritical pressure CO2 heat transfer test facility has been constructed and preliminary test proved the facility works as expected. The result of this project will be good basis for the participation in the international collaboration under GIF GEN-IV program and next 5-year mid and long term nuclear research program of MOST. The heat transfer test loop, SPHINX, completed as a result of this project may be used for the power cycle study as well as further heat transfer study for the various geometries.

Operational monitoring of temperature and state of stress of primary collectors, their stud bolts and cover and temperatures of steam generator's pressure vessel at the nuclear power unit WWER 440

International Nuclear Information System (INIS)

Matal, O.; Simo, T.; Holy, F.; Vejvoda, S.

1992-01-01

Both primary collectors of the WWER 440 steam generator (STGE) are vertically positioned inside the STGE pressure vessel and connected in their lower part to the primary piping and closed at their upper part by primary covers. The primary cover is pushed against the primary collector flange by 20 stud bolts. Two nickel packing rings are fitted between the primary cover and collector. A leakage in the collector-cover junction could cause flow of the radioactive water into the clean secondary water. If the junction is made in accordance with the Soviet standard design the computed stresses exceed the allowable value in the stud bolts by a factor of 1.5. Therefore an improved design of the primary collector - primary cover flange joint was designed and tested on one STGE at a WWER 440 nuclear power unit in Czechoslovakia. The paper describes the system of joint properties measurement, gives some substantial characteristics of the new stud bolts and primary cover design and comments on significant measured results of state of stress and temperatures in comparison with the operational regime of the STGE. (orig.)

Socialization of the Child in the Soviet Union.

Science.gov (United States)

Sandanavicius, Mary

1979-01-01

The socialization process of the child in the Soviet Union is examined in terms of socialistic/communistic political philosophy and the general attitudes of the Soviets toward social sciences, child rearing, and educational practice. The family, school, and youth organizations are also discussed as socializing agents. (Author/KC)

Performance test of ex-core high temperature and high pressure water loop test equipment (Contract research)

International Nuclear Information System (INIS)

Nakano, Hiroko; Uehara, Toshiaki; Takeuchi, Tomoaki; Shibata, Hiroshi; Nakamura, Jinichi; Matsui, Yoshinori; Tsuchiya, Kunihiko

2016-03-01

In Japan Atomic Energy Agency, we started research and development so as to monitor the situations in the Nuclear Plant Facilities during a severe accident, such as a radiation-resistant monitoring camera, a radiation-resistant transmission system for conveying the in-core information, and a heat-resistant signal cable. As a part of developments of the heat-resistant signal cable, we prepared ex-core high-temperature and high-pressure water loop test equipment, which can simulate the conditions of BWRs and PWRs, for evaluating reliability and properties of sheath materials of the cable. This equipment consists of autoclave, water conditioning tank, high-pressure metering pump, preheater, heat exchanger and water purification equipment, etc. This report describes the basic design and the performance test results of ex-core high-temperature and high-pressure water loop test equipment. (author)

Design and performance characteristic analysis of servo valve-type water hydraulic poppet valve

International Nuclear Information System (INIS)

Park, Sung Hwan

2009-01-01

For water hydraulic system control, the flow or pressure control using high-speed solenoid valve controlled by PWM control method could be a good solution for prevention of internal leakage. However, since the PWM control of on-off valves cause extensive flow and pressure fluctuation, it is difficult to control the water hydraulic actuators precisely. In this study, the servo valve-type water hydraulic valve using proportional poppet as the main valve is designed and the performance characteristics of the servo valve-type water hydraulic valve are analyzed. Furthermore, it is demonstrated through experiments that a decline in control chamber pressure that follows the change of pilot flow is caused by the occurrence of cavitation around the proportional poppet, and that fundamental characteristics of the developed valve remain unaffected by the occurrence of cavitation

Heat exchanging tube behaviour in steam generators of pressurized water reactors

International Nuclear Information System (INIS)

Pastor, D.; Oertel, K.

1979-01-01

Based on a comprehensive failure statistics, materials corrosion chemistry and thermohydraulics problems of the tubings of steam generators are considered. A historical review of failures in the tubings of steam generators in pressurized water reactors reflects the often successless measures by designers, manufacturers and operating organizations for preventing failures, especially with regard to materials selection and water regime. It is stated that laboratory tests could not give sufficient information about safe and stable operation of nuclear steam generators unless real constructive, hydrodynamic, thermodynamical and chemical conditions of operation had been taken into account. (author)

Designing high pressure containers for research- principles and applications

International Nuclear Information System (INIS)

Anandkumar, V.

1997-01-01

The high pressure scientist looks for a well engineered pressure apparatus for high pressure experiments for 1 kbar (0.1 GPa) and above. Often, a variety of difficulties including the choice of materials, design configuration, optimum utilisation of the strength of materials used in the design, are encountered. This article is intended to help the high pressure scientist to select the design approach for pressure retaining container. The limitations imposed by the strength of available materials and engineering standards in building high pressure containers are discussed. Engineering solutions to overcome these limitations with optimal utilisation of the strength of the materials are also discussed. Novel methods to boost up the pressure retaining capacity like multilayered design and autofrettaging are compared along with their relative advantages and disadvantages. Special methods by which it is possible to attain pressures which are several times the yield strength of the materials of construction are presented. In this aspects such as the basis of the codes and their relevance in the design of high pressure equipment will also be described. Discussions are centered around the methods to tackle situations where experimental constraints dictate requirements of pressures higher than those permitted by design codes. Safety features are also discussed. (author)

Reactor pressure vessel design

International Nuclear Information System (INIS)

Foehl, J.

1998-01-01

As a result of the popularity of the Agencies report 'Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels' of 1975, it was decided that another report on this broad subject would be of use. In this report, background and contemporary views on specially identified areas of the subject are considered as self-contained chapters, written by experts. In chapter 2, the general principles of reactor pressure vessel design are elaborated. Crack and fracture initiation and propagation are treated in some detail

Thermo hydraulic analysis of narrow channel effect in supercritical-pressure light water reactor

International Nuclear Information System (INIS)

Zhou Tao; Chen Juan; Cheng Wanxu

2012-01-01

Highlights: ► Detailed thermal analysis with different narrow gaps between fuel rods is given. ► Special characteristics of narrow channels effect on heat transfer in supercritical pressure are shown. ► Reasonable size selection of gaps between fuel rods is proposed for SCWR. - Abstract: The size of the gap between fuel rods has important effects on flow and heat transfer in a supercritical-pressure light water reactor. Based on thermal analysis at different coolant flow rates, the reasonable value range of gap size between fuel rods is obtained, for which the maximum cladding temperature safety limits and installation technology are comprehensively considered. Firstly, for a given design flow rate of coolant, thermal hydraulic analysis of supercritical pressure light water reactor with different gap sizes is provided by changing the fuel rod pitch only. The results show that, by means of reducing the gap size between fuel rods, the heat transfer coefficients between coolant and fuel rod, as well as the heat transfer coefficient between coolant and water rod, would both increase noticeably. Furthermore, the maximum cladding temperature will significantly decrease when the moderator temperature is decreased but coolant temperature remains essentially constant. Meanwhile, the reduction in the maximum cladding temperature in the inner assemblies is much larger than that in the outer assemblies. In addition, the maximum cladding temperature could be further reduced by means of increasing coolant flow rate for each gap size. Finally, the characteristics of narrow channels effect are proposed, and the maximum allowable gap between fuel rods is obtained by making full use of the enhancing narrow channels effect on heat transfer, and concurrently considering installation. This could provide a theoretical reference for supercritical-pressure light water reactor design optimization, in which the effects of gap size and flow rate on heat transfer are both considered.

Twin header bore welded steam generator for pressurized water reactors

International Nuclear Information System (INIS)

Davies, R.J.; Hirst, B.

1979-01-01

A description is given of a pressurized water reactor (PWR) steam generator concept, several examples of which have been in service for up to fourteen years. Details are given of the highly successful service record of this equipment and the features which have been incorporated to minimize corrosion and deposition pockets. The design employs a vertical U tube bundle carried off two horizontal headers to which the tubes are welded by the Foster Wheeler Power Products (FWPP) bore welding process. The factors to be considered in uprating the design to meet the current operating conditions for a 1000 MW unit are discussed. (author)

Bibliographic Index of Soviet Military Books, 1970-1974.

Science.gov (United States)

1984-01-31

34 Each is preceded by a numerical designation, used in Soviet bibliographies, which corresponds in many ways to the Dewey Decimal System used in the...74-06882 (C0087) Mal’kov,V.I. Character and System of Laws of War and Armed * . Conflict, Principles of Military Art.(Kharakter i Sistema Zakonov...C0561) Stukalov,P.I., Shchetnini,V.F. System of Political Organi- zation of Socialist Society, the Plaice and Role in it of the Armed For- ces.( Sistema

Afghanistan: The First Five Years of Soviet Occupation

Science.gov (United States)

1986-01-01

July 1982, reported that be- fore reaching the Kabul River his group passed three DRA outposts or forts. One of his guerrilla companions assured him...driver, chef , doctor, and six chief advisers, all were Soviets. At the palace where he resided and worked, the guard force was Soviet, except for a

Coolant mixing in pressurized water reactors

Energy Technology Data Exchange (ETDEWEB)

Hoehne, T; Grunwald, G

1998-10-01

The behavior of PWRs during cold water or boron dilution transients is strongly influenced by the distribution of coolant temperature and boron concentration at the core inlet. This distribution is the needed input to 3-dimensional neutron kinetics to calculate the power distribution in the core. It mainly depends on how the plugs of cold or unborated water formed in a single loop are mixed in the downcomer and in the lower plenum. To simulate such mixture phenomena requires the application of 3-dimensional CFD (computational fluid dynamics) codes. The results of the simulation have to be validated against mixture experiments at scaled facilities. Therefore, in the framework of a research project funded by BMBF, the institute creates a 1:5 mixture facility representing first the geometry of a German pressurized water reactor and later the European Pressurized Water Reactor (EPR) geometry. The calculations are based on the CFD Code CFX-4. (orig.)

Pressure equalization systems in pressurized water reactor fuel rods

International Nuclear Information System (INIS)

Steven, J.; Wunderlich, F.

1979-01-01

For the development of a pressure reduction system in PWR fuel rods the capability of charcoal to adsorb Helium, Xenon and Krypton at temperatures of about 300 0 C was investigated. The influence of the adsorption on fuel rod internal pressure and in creep strain on the tube was evaluated in a design study. (orig.) [de

Pressurized water reactor systems

International Nuclear Information System (INIS)

Meyer, P.J.

1975-01-01

Design and mode of operation of the main PWR components are described: reactor core, pressure vessel and internals, cooling systems with pumps and steam generators, ancillary systems, and waste processing. (TK) [de

Perestroika and Its Impact on the Soviet Labor Market.

Science.gov (United States)

Brand, Horst

1991-01-01

Discusses two books, "Restructuring the Soviet Economy: In Search of the Market" and "In Search of Flexibility: The New Soviet Labour Market," that assess the success of perestroika and the transition to a market-based economy. (JOW)

Thermo-hydraulic behavior of saturated steam-water mixture in pressure vessel during injection of cold water

International Nuclear Information System (INIS)

Aya, Izuo; Kobayashi, Michiyuki; Inasaka, Fujio; Nariai, Hideki.

1983-01-01

The thermo-hydraulic behavior of saturated steam water mixture in a pressure vessel during injection of cold water was experimentally investigated with the Facility for Mixing Effect of Emergency Core Cooling Water. The dimensions of the pressure vessel used in the experiments were 284mm ID and 1,971mm height. 11 experiments were conducted without blowdown in order to comprehend the basic process excluding the effect of blowdown at injection of cold water. The initial pressure and water level, the injection flow rate and the size of injection nozzle were chosen as experimental parameters. Temperatures and void fractions at 6 elevations as well as pressure in the pressure vessel were measured, and new data especially on the pressure undershoot just after the initation of water injection and the vertical distribution of temperature and void fraction were gotten. The transients of pressure, average temperature and void fraction were caluculated using single-volume analysis code BLODAC-1V which is based on thermal equilibrium and so-called bubble gradient model. Some input parameters included in the analysis code were evaluated through the comparison of analysis with experimental data. Moreover, the observed pressure undershoot which is evaluated to be induced by a time lag of vapourization in water due to thermal nonequilibrium, was also discussed with the aid of another simple analysis model. (author)

The Soviet applied information sciences in a time of change

Energy Technology Data Exchange (ETDEWEB)

Bengston, J.; Cronin, R.R.; Davidson, R.B.

1991-07-01

The Foreign Applied Sciences Assessment Center (FASAC) conducts reviews of selected areas of foreign basic and applied science by US scientists who are technically expert and active in the fields reviewed. Several of the FASAC assessments of Soviet science have involved various aspects of the information sciences, including enabling technologies and applications, as well as the core information sciences. This report draws upon those FASAC assessment reports, the expert judgment of some of the authors of those reports, and other public sources to characterize the current state of the information sciences in the Soviet Union and the effects of information science capabilities upon other areas of Soviet science and technology. This report also provides estimates of the likely effect of the political and social reforms underway in the Soviet Union on future Soviet progress in the information sciences and, at a more general level, in science and technology. 41 refs., 7 tabs.

High-pressure water electrolysis: Electrochemical mitigation of product gas crossover

International Nuclear Information System (INIS)

Schalenbach, Maximilian; Stolten, Detlef

2015-01-01

Highlights: • New technique to reduce gas crossover during water electrolysis • Increase of the efficiency of pressurized water electrolysis • Prevention of safety hazards due to explosive gas mixtures caused by crossover • Experimental realization for a polymer electrolyte membrane electrolyzer • Discussion of electrochemical crossover mitigation for alkaline water electrolysis - Abstract: Hydrogen produced by water electrolysis can be used as an energy carrier storing electricity generated from renewables. During water electrolysis hydrogen can be evolved under pressure at isothermal conditions, enabling highly efficient compression. However, the permeation of hydrogen through the electrolyte increases with operating pressure and leads to efficiency loss and safety hazards. In this study, we report on an innovative concept, where the hydrogen crossover is electrochemically mitigated by an additional electrode between the anode and the cathode of the electrolysis cell. Experimentally, the technique was applied to a proton exchange membrane water electrolyzer operated at a hydrogen pressure that was fifty times larger than the oxygen pressure. Therewith, the hydrogen crossover was reduced and the current efficiency during partial load operation was increased. The concept is also discussed for water electrolysis that is operated at balanced pressures, where the crossover of hydrogen and oxygen is mitigated using two additional electrodes

Who's bound by the former Soviet Union's arms control treaties?

International Nuclear Information System (INIS)

Rhinelander, J.B.; Bunn, G.

1991-01-01

A crucial issue raised by the disintegration of the Soviet central government is what happens to Soviet arms control obligations. As the Soviet government transforms or collapses in the wake of the failed August coup, which of the resulting entities will be bound by the treaties the Soviet Union entered into? Under international law, the obligations of a state are not affected by even such dramatic changes in government. No one yet knows, however, what the end result of the ongoing devolution of power in the erstwhile Soviet Union will be. As illustrations of what could happen to Soviet arms control obligations - not predictions of the future - the authors pose two alternative scenarios. In the first, they assume that most of the current 12 republics, including all of the big four where substantial nuclear forces and the largest conventional forces are located (Russia, Ukraine, Khazakhstan, and Belarus), ultimately form a loose confederation with sufficient central authority to be called a nation-state and to carry out the essence of Soviet obligations under major arms control treaties. In the second, they assume that the union disintegrates further, with these four key republics seceding entirely and recognizing one another as independent states - a step which is apparently one of the US criteria for granting its own recognition. In this scenario, the Russian republic maintains its basic territory and replaces the central government as the power center for military and foreign affairs. In each of these cases, they will describe the general issues affecting the Soviet Union's international obligations, and consider specifically the two most important arms control agreements now in force - the multilateral nuclear Non-proliferation Treaty (NPT) and the bilateral Antiballistic Missile (ABM) Treaty

Experimental Study and Engineering Practice of Pressured Water Coupling Blasting

Directory of Open Access Journals (Sweden)

J. X. Yang

2017-01-01

Full Text Available Overburden strata movement in large space stope is the major reason that induces the appearance of strong mining pressure. Presplitting blasting for hard coal rocks is crucial for the prevention and control of strong pressure in stope. In this study, pressured water coupling blasting technique was proposed. The process and effect of blasting were analyzed by orthogonal test and field practice. Results showed that the presence of pressure-bearing water and explosive cartridges in the drill are the main influence factors of the blasting effect of cement test block. The high load-transmitting performance of pore water and energy accumulation in explosive cartridges were analyzed. Noxious substances produced during the blasting process were properly controlled because of the moistening, cooling, and diluting effect of pore water. Not only the goal of safe and static rock fragmentation by high-explosive detonation but also a combination of superdynamic blast loading and static loading effect of the pressured water was achieved. Then the practice of blasting control of hard coal rocks in Datong coal mine was analyzed to determine reasonable parameters of pressured water coupling blasting. A good presplitting blasting control effect was achieved for the hard coal rocks.

Pressure dependence of dynamical heterogeneity in water

International Nuclear Information System (INIS)

Teboul, Victor

2008-01-01

Using molecular dynamics simulations we investigate the effect of pressure on the dynamical heterogeneity in water. We show that the effect of a pressure variation in water is qualitatively different from the effect of a temperature variation on the dynamical heterogeneity in the liquid. We observe a strong decrease of the aggregation of molecules of low mobility together with a decrease of the characteristic time associated with this aggregation. However, the aggregation of the most mobile molecules and the characteristic time of this aggregation are only slightly affected. In accordance with this result, the non-Gaussian parameter shows an important decrease with pressure while the characteristic time t* of the non-Gaussian parameter is only slightly affected. These results highlight then the importance of pressure variation investigations in low temperature liquids on approach to the glass transition

Design Development of SMART ECC Water Asymmetric Two-phase choking test facility

Energy Technology Data Exchange (ETDEWEB)

Cho, Young Il; Cho, Seok; Ko, Yung Joo; Shin, Yong Cheol; Kwon, Tae Soon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2011-05-15

SMART pressurized water reactor type is different from the existing integral NSSS commercial pressurized water reactor system which is equipped with the main features. In addition RCS piping is removed and the feature of the SBLOCA is a major design break accident. The TASS / SMR code is analyzed SMART SBLOCA. In order to verify analysis code, SMART analysis for verification of conservatism is promoting using data for experiments with Integral Effect Test and Separate Effect. In this paper, the design feature of the SWAT (SMART ECC Water Asymmetric Two-phase choking test facility) is described. SWAT is linearly reduced to a 1/5 ratio while the geometrical shape is conserved. In major shape of SMART ECC injection performance test, distortions which caused by gravitational effects are minimized. Because both the emergency core cooling water injection nozzle height and the break nozzle height match the RCP Suction Nozzle height in test section of the main forms. The main part of the test section is SG-side upper down-comer. The boundary conditions are saturated steam and water flow condition and drain flow rate to control the collapsed water level in the down-comer

Managing Uncertainity: Soviet Views on Deception, Surprise, and Control

National Research Council Canada - National Science Library

Hull, Andrew

1989-01-01

.... In the first two cases (deception and surprise), the emphasis is on how the Soviets seek to sow uncertainty in the minds of the enemy and how the Soviets then plan to use that uncertainty to gain military advantage...

The phase diagram of water at negative pressures: virtual ices.

Science.gov (United States)

Conde, M M; Vega, C; Tribello, G A; Slater, B

2009-07-21

The phase diagram of water at negative pressures as obtained from computer simulations for two models of water, TIP4P/2005 and TIP5P is presented. Several solid structures with lower densities than ice Ih, so-called virtual ices, were considered as possible candidates to occupy the negative pressure region of the phase diagram of water. In particular the empty hydrate structures sI, sII, and sH and another, recently proposed, low-density ice structure. The relative stabilities of these structures at 0 K was determined using empirical water potentials and density functional theory calculations. By performing free energy calculations and Gibbs-Duhem integration the phase diagram of TIP4P/2005 was determined at negative pressures. The empty hydrates sII and sH appear to be the stable solid phases of water at negative pressures. The phase boundary between ice Ih and sII clathrate occurs at moderate negative pressures, while at large negative pressures sH becomes the most stable phase. This behavior is in reasonable agreement with what is observed in density functional theory calculations.

Accident tolerant high-pressure helium injection system concept for light water reactors

International Nuclear Information System (INIS)

Massey, Caleb; Miller, James; Vasudevamurthy, Gokul

2016-01-01

Highlights: • Potential helium injection strategy is proposed for LWR accident scenarios. • Multiple injection sites are proposed for current LWR designs. • Proof-of-concept experimentation illustrates potential helium injection benefits. • Computational studies show an increase in pressure vessel blowdown time. • Current LOCA codes have the capability to include helium for feasibility calculations. - Abstract: While the design of advanced accident-tolerant fuels and structural materials continues to remain the primary focus of much research and development pertaining to the integrity of nuclear systems, there is a need for a more immediate, simple, and practical improvement in the severe accident response of current emergency core cooling systems. Current blowdown and reflood methodologies under accident conditions still allow peak cladding temperatures to approach design limits and detrimentally affect the integrity of core components. A high-pressure helium injection concept is presented to enhance accident tolerance by increasing operator response time while maintaining lower peak cladding temperatures under design basis and beyond design basis scenarios. Multiple injection sites are proposed that can be adapted to current light water reactor designs to minimize the need for new infrastructure, and concept feasibility has been investigated through a combination of proof-of-concept experimentation and computational modeling. Proof-of-concept experiments show promising cooling potential using a high-pressure helium injection concept, while the developed choked-flow model shows core depressurization changes with added helium injection. Though the high-pressure helium injection concept shows promise, future research into the evaluation of system feasibility and economics are needed.Classification: L. Safety and risk analysis

Universal Higher Education and Positional Advantage: Soviet Legacies and Neoliberal Transformations in Russia

Science.gov (United States)

Smolentseva, Anna

2017-01-01

The great expansion of participation in higher education in Russia in the post-Soviet period was the layered and contradictory result of both conditions established in the Soviet period, and the structuring of reforms after the collapse of the Soviet Union in 1992. The Soviet government was strongly committed to the expansion of education across…

Operator Support System for Pressurized Water Reactor

International Nuclear Information System (INIS)

Wei Renjie; Shen Shifei

1996-01-01

Operator Support System for Pressurized Water Reactor (OSSPWR) has been developed under the sponsorship of IAEA from August 1994. The project is being carried out by the Department of Engineering Physics, Tsinghua University, Beijing, China. The Design concepts of the operator support functions have been established. The prototype systems of OSSPWR has been developed as well. The primary goal of the project is to create an advanced operator support system by applying new technologies such as artificial intelligence (AI) techniques, advanced communication technologies, etc. Recently, the advanced man-machine interface for nuclear power plant operators has been developed. It is connected to the modern computer systems and utilizes new high performance graphic displays. (author). 6 refs, 4 figs

Socialism and Education in Cuba and Soviet Uzbekistan

Science.gov (United States)

Charon-Cardona, Euridice

2013-01-01

During the Cold War over half a million Asians, Africans and Latin Americans studied and graduated in the Soviet Union's universities and technical schools as part of this country's educational aid policies. Cuba was an intermediary player in the Cold War geopolitical contest between the United States and the Soviet Union, fuelled by the…

Pressure: the politechnics of water supply in Mumbai.

Science.gov (United States)

Anand, Nikhil

2011-01-01

In Mumbai, most all residents are delivered their daily supply of water for a few hours every day, on a water supply schedule. Subject to a more precarious supply than the city's upper-class residents, the city's settlers have to consistently demand that their water come on “time” and with “pressure.” Taking pressure seriously as both a social and natural force, in this article I focus on the ways in which settlers mobilize the pressures of politics, pumps, and pipes to get water. I show how these practices not only allow settlers to live in the city, but also produce what I call hydraulic citizenship—a form of belonging to the city made by effective political and technical connections to the city's infrastructure. Yet, not all settlers are able to get water from the city water department. The outcomes of settlers' efforts to access water depend on a complex matrix of socionatural relations that settlers make with city engineers and their hydraulic infrastructure. I show how these arrangements describe and produce the cultural politics of water in Mumbai. By focusing on the ways in which residents in a predominantly Muslim settlement draw water despite the state's neglect, I conclude by pointing to the indeterminacy of water, and the ways in which its seepage and leakage make different kinds of politics and publics possible in the city.

Determination of Secondary Encasement Pipe Design Pressure

Energy Technology Data Exchange (ETDEWEB)

TEDESCHI, A.R.

2000-10-26

This document published results of iterative calculations for maximum tank farm transfer secondary pipe (encasement) pressure upon failure of the primary pipe. The maximum pressure was calculated from a primary pipe guillotine break. Results show encasement pipeline design or testing pressures can be significantly lower than primary pipe pressure criteria.

The outlook for Soviet gas

International Nuclear Information System (INIS)

Ebel, R.E.

1991-01-01

The economic collapse of the Soviet Union has seen the decline of its oil and gas industry through a lack of capital investment, idle wells, shortages of equipment and spare parts, worker apathy, and a leaky pipeline network. Natural gas reserves controlled by the Soviet Union total some 50 trillion m 3 , over 70% of which are in western Siberia. A total of just 19 gas deposits hold 70% of the total reserves and account for over 75% of national output. Natural gas production in 1990 was 815 billion m 3 or 38% of world output; exports reached 109 billion m 3 , divided roughly equally between eastern and western Europe, and all transported by pipeline. The Soviet Union is also a major gas consumer, at around 709 billion m 3 /y, and uses about half this amount for generating electricity. In the early 1980s, a crash program to expand the gas industry raised production from 435 billion m 3 in 1980 to 643 billion m 3 in 1985, but at the cost of hastily built pipelines and facilities, and a premature exhaustion of major gas fields. A prohibition on import of western-made compressors, due to the Afghanistan invasion, forced the installation of unreliable domestic compressors. Slow growth in gas ouput and unreliability of the current gas supply and transmission system has threatened the stability of supply to domestic and export customers, and gas delivery shortfalls of 50-60 billion m 3 were thought possible. The industry's future depends on development of additional fields, and a revived interest in Soviet natural gas is being shown by foreign investors. Since many of these fields are in remote or geologically unfavorable areas, large investments and lead times will be needed

WAG (water-alternating-gas) process design: an update review

Energy Technology Data Exchange (ETDEWEB)

Zahoor, M.K. [University of Engineering and Technology, Lahore (Pakistan). Dept. of Petroleum and Gas Engineering], e-mail: mkzahoor@uet.edu.pk; Derahman, M.N.; Yunan, M.H. [Universiti Teknologi Malaysia, Johor (Malaysia). Dept. of Petroleum Engineering

2011-04-15

The design and implementation of water-alternating-gas (WAG) process in an improved and cost-effective way are still under process. Due to the complexities involved in implementing the process and the lack of information regarding fluid and reservoir properties, the water-alternating-gas process has not yet been as successful as initially expected. This situation can be overcome by better understanding the fluid distribution and flow behavior within the reservoir. The ultimate purpose can be achieved with improved knowledge on wettability and its influence on fluid distribution, capillary pressure, relative permeability, and other design parameters. This paper gives an insight on the WAG process design and the recently developed correlations which are helpful in incorporating the effects of wettability variations on fluid dynamics within the reservoir. (author)

Water hammer characteristics of integral pressurized water reactor primary loop

International Nuclear Information System (INIS)

Zuo, Qiaolin; Qiu, Suizheng; Lu, Wei; Tian, Wenxi; Su, Guanghui; Xiao, Zejun

2013-01-01

Highlights: • Water hammer models developed for IPWR primary loop using MOC. • Good agreement between the developed code and the experiment. • The good agreement between WAHAP and Flowmaster can validate the equations in WAHAP. • The primary loop of IPWR suffers from slight water hammer impact. -- Abstract: The present work discussed the single-phase water hammer phenomenon, which was caused by the four-pump-alternate startup in an integral pressurized water reactor (IPWR). A new code named water hammer program (WAHAP) was developed independently based on the method of characteristic to simulate hydraulic transients in the primary system of IPWR and its components such as reactor core, once-through steam generators (OTSG), the main coolant pumps and so on. Experimental validation for the correctness of the equations and models in WAHAP was carried out and the models fit the experimental data well. Some important variables were monitored including transient volume flow rates, opening angle of valve disc and pressure drop in valves. The water hammer commercial software Flowmaster V7 was also employed to compare with WAHAP and the good agreement can validate the equations in WAHAP. The transient results indicated that the primary loop of IPWR suffers from slight water hammer impact under pump switching conditions

Water hammer characteristics of integral pressurized water reactor primary loop

Energy Technology Data Exchange (ETDEWEB)

Zuo, Qiaolin [School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shanxi 710049 (China); Qiu, Suizheng, E-mail: szqiu@mail.xjtu.edu.cn [School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shanxi 710049 (China); Lu, Wei; Tian, Wenxi; Su, Guanghui [School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shanxi 710049 (China); Xiao, Zejun [Nuclear Power Institute of China, Chengdu, Sichuan 610041 (China)

2013-08-15

Highlights: • Water hammer models developed for IPWR primary loop using MOC. • Good agreement between the developed code and the experiment. • The good agreement between WAHAP and Flowmaster can validate the equations in WAHAP. • The primary loop of IPWR suffers from slight water hammer impact. -- Abstract: The present work discussed the single-phase water hammer phenomenon, which was caused by the four-pump-alternate startup in an integral pressurized water reactor (IPWR). A new code named water hammer program (WAHAP) was developed independently based on the method of characteristic to simulate hydraulic transients in the primary system of IPWR and its components such as reactor core, once-through steam generators (OTSG), the main coolant pumps and so on. Experimental validation for the correctness of the equations and models in WAHAP was carried out and the models fit the experimental data well. Some important variables were monitored including transient volume flow rates, opening angle of valve disc and pressure drop in valves. The water hammer commercial software Flowmaster V7 was also employed to compare with WAHAP and the good agreement can validate the equations in WAHAP. The transient results indicated that the primary loop of IPWR suffers from slight water hammer impact under pump switching conditions.

Soviet International Finance in the Gorbachev Era

Science.gov (United States)

1991-01-01

officials responsible for financial matters; and the financial press . All of these sources are cited as appropriate in this repoet. Considerable additional...creditors back to 1984. 2See, for example, Judy Shelton, The Coming Soviet Crash, The Free Press , New York, 1989, p. xv. 14 end of 1988, net Soviet...eighth over LIBOR. As recently as September 1989, VEB was able to arrange a five-year, $100 million syndicated credit managed by Banca Commerciale Italiana

Growing Soviet market is worth the hassles

International Nuclear Information System (INIS)

Muse, J.F.

1991-01-01

Tremendous opportunity is offered by the potential market in the Soviet republics for a diverse oil and gas equipment company, such as Baker Hughes. Until recently, however, the many risks and problems limited efforts to direct, hard currency sales by three or four individual divisions (out of a total of 23) that chose to pursue markets for their products by working through independent agents. This article discusses some aspects of dealing with the Soviet market

The Grand Strategy of the Soviet Union

Science.gov (United States)

1982-03-25

of diverse echnic the highest origin could rise to AleveLs of power in all branches of the state. Plainly that is not the case in today’s Soviet...and psychological reasons, the new primacy given to external aggrandizement intensifies ethnic tensions inside Soviet society. The failure to fulfill...or perhaps because our own means are simply too small, we come to terms psychologically with its increasing power by persuading ourselves that it

Initial pressure spike and its propagation phenomena in sodium-water reaction tests for MONJU steam generators

International Nuclear Information System (INIS)

Sato, M.; Hiroi, H.; Tanaka, N.; Hori, M.

1977-01-01

With the objective of demonstrating the safe design of steam generators for prototype LMFBR MONJU against the postulated large-leak accident, a number of large-leak sodium-water reaction tests have been conducted using the SWAT-1 and SWAT-3 rigs. Investigation of the potential effects of pressure load on the system is one of the major concerns in these tests. This paper reports the behavior of initial pressure spike in the reaction vessel, its propagation phenomena to the simulated secondary cooling system, and the comparisons with the computer code for one-dimensional pressure wave propagation problems. Both rigs used are the scaled-down models of the helically coiled steam generators of MONJU. The SWAT-1 rig is a simplified model and consists of a reaction vessel (1/8 scale of MONJU evaporator with 0.4 m dia. and 2.5 m height) and a pressure relief system i.e., a pressure relief line and a reaction products tank. On the other hand, the SWAT-3 rig is a 1/2.5 scale of MONJU SG system and consists of an evaporator (reaction vessel with 1.3 m dia. and 6.35 m height), a superheater, an intermediate heat exchanger (IHX), a piping system simulating the secondary cooling circuit and a pressure relief system. The both water injection systems consist of a water injection line with a rupture disk installed in front of injection hole and an electrically heated water tank. Choice of water injection rates in the scaled-down models is made based on the method of iso-velocity modeling. Test results indicated that the characteristics of the initial pressure spike are dominated by those of initial water injection which are controlled by the conditions of water heater and the size of water injection hole, etc

The Adversary System in Low-Level Soviet Economic Decisionmaking.

Science.gov (United States)

1984-08-01

34- ° .. 78 - capital or a few countertrade agreements, will solve their problems for them. This is markedly different from the overall Soviet pattern...currency countertrade practice, the considerations of this Note would permit further refinement of predictions of Soviet economic decisionmaking that

Application of the regulations on pressurized components or light water reactor primary coolant circuits

International Nuclear Information System (INIS)

Barthelemy, F.; Menjon, G.

1977-01-01

This paper describes the philosophy and the provisions of the Order of 26 February 1974 concerning application of the regulations on pressurized components for light water reactor steam supply systems. The aim is to show how these regulations which differ from other regulations on pressurized components and is more detailed on many points, is applied in practice in France in the various stages of the design, construction and operation of PWRs. (NEA) [fr

Design by analysis of composite pressure equipment

International Nuclear Information System (INIS)

Durand, S.; Mallard, H.

2004-01-01

Design by analysis has been particularly pointed out by the european pressure equipment directive. Advanced mechanical analysis like finite element method are used instead of classical design by formulas or graphs. Structural behaviour can be understood by the designer. Design by analysis of metallic pressure equipments is widely used. Material behaviour or limits analysis is based on sophisticated approach (elasto-plastic analysis,..). Design by analysis of composite pressure equipments is not systematically used for industrial products. The difficulty comes from the number of information to handle. The laws of mechanics are the same for composite materials than for steel. The authors want to show that in design by analysis, the composite material approach is only more complete than the metallic approach. Mechanics is more general but not more complicated. A multi-material approach is a natural evolution of design by analysis of composite equipments. The presentation is illustrated by several industrial cases - composite vessel: analogy with metallic calculations; - composite pipes and fittings; - welding and bounding of thermoplastic equipments. (authors)

In Situ Raman Study of Liquid Water at High Pressure.

Science.gov (United States)

Romanenko, Alexandr V; Rashchenko, Sergey V; Goryainov, Sergey V; Likhacheva, Anna Yu; Korsakov, Andrey V

2018-06-01

A pressure shift of Raman band of liquid water (H 2 O) may be an important tool for measuring residual pressures in mineral inclusions, in situ barometry in high-pressure cells, and as an indicator of pressure-induced structural transitions in H 2 O. However, there was no consensus as to how the broad and asymmetric water Raman band should be quantitatively described, which has led to fundamental inconsistencies between reported data. In order to overcome this issue, we measured Raman spectra of H 2 O in situ up to 1.2 GPa using a diamond anvil cell, and use them to test different approaches proposed for the description of the water Raman band. We found that the most physically meaningful description of water Raman band is the decomposition into a linear background and three Gaussian components, associated with differently H-bonded H 2 O molecules. Two of these components demonstrate a pronounced anomaly in pressure shift near 0.4 GPa, supporting ideas of structural transition in H 2 O at this pressure. The most convenient approach for pressure calibration is the use of "a linear background + one Gaussian" decomposition (the pressure can be measured using the formula P (GPa) = -0.0317(3)·Δν G (cm -1 ), where Δν G represents the difference between the position of water Raman band, fitted as a single Gaussian, in measured spectrum and spectrum at ambient pressure).

Economic Development in Afghanistan during the Soviet Period, 1979-1989: Lessons Learned from the Soviet Experience in Afghanistan

Science.gov (United States)

2007-08-01

gouvernement afghan. Les auteurs de l’étude concluent que l’accent sur la sécurité en Afghanistan a été préjudiciable à un développement économique...Afghanistan (PDPA) regime were largely influenced by Soviet economic theory and experience. In addition to adopting economic planning based on the five...rural Afghans. On peasant in Leninist theory see Esther Kingston-Mann, “Proletarian Theory and Peasant Practice: Lenin 1901-1904,” in Soviet Studies

Soviet medical ethics (1917-1991).

Science.gov (United States)

Lichterman, Boleslav L

2005-01-01

Russian medical ethics bears a heavy mark of seven decades of the communist regime. In 1918 the Health Care Commissariat (ministry) was formed. It was headed by Nikolai Semashko (1874-1949) who claimed that "the ethics of the Soviet physician is an ethics of our socialist motherland, an ethics of a builder of communist society; it is equal to communist moral". "Medical ethics" had been avoided until the late 1930s when it was replaced by "medical (or surgical) deontology". This "deontological" period started with "Problems of surgical deontology" written by N. Petrov, a surgeon, and lasted for almost half a century until "medical deontology" was abandoned in favor of "bioethics" in post-communist Russia. There have been five All-Union conferences on medical deontology since 1969. The story of the emergence of "The Oath of a Soviet Physician" is briefly described. The text of this Oath was approved by a special decree of the Soviet Parliament in 1971. Each graduate of medical school in USSR was obliged to take this Oath when receiving his or her medical diploma. It is concluded that such ideas of zemstvo medicine as universal access to health care and condemnation of private practice were put into practice under the communist regime.

Pressure control of a proton beam-irradiated water target through an internal flow channel-induced thermosyphon.

Science.gov (United States)

Hong, Bong Hwan; Jung, In Su

2017-07-01

A water target was designed to enhance cooling efficiency using a thermosyphon, which is a system that uses natural convection to induce heat exchange. Two water targets were fabricated: a square target without any flow channel and a target with a flow channel design to induce a thermosyphon mechanism. These two targets had the same internal volume of 8 ml. First, visualization experiments were performed to observe the internal flow by natural convection. Subsequently, an experiment was conducted to compare the cooling performance of both water targets by measuring the temperature and pressure. A 30-MeV proton beam with a beam current of 20 μA was used to irradiate both targets. Consequently, the target with an internal flow channel had a lower mean temperature and a 50% pressure drop compared to the target without a flow channel during proton beam irradiation. Copyright © 2017 Elsevier Ltd. All rights reserved.

DESIGNING HYDRAULIC AIR CHAMBER IN WATER TRANSMISSION SYSTEMS USING GENETIC ALGORITHM

Directory of Open Access Journals (Sweden)

Abdorahim Jamal

2016-09-01

Full Text Available Transient flow control in Water Transmission Systems (WTS is one of the requirements of designing these systems. Hence, among control equipment, air chambers offer the best solution to control transient flow effects, i.e. both prevents water column separation and absorbs pressure increase. It is essential to carry out an accurate and optimized design of air chambers, not only due to high costs of their manufacturing but also their important protective role. Accordingly, hydraulic design parameters comprise tank volume, diameter of nozzle and coefficients of inflow and outflow of nozzle. In this paper, it is intended to optimize these parameters in order to minimize manufacturing costs. On the other hand, maximum and minimum pressures in main pipeline are considered as constraints which shall fall in allowed range. Therefore, a model has been developed which is a combination of a hydraulic simulation model of WTS and an optimization model based on genetic algorithm. This model is first applied to WTS of Dehgolan-Ghorveh plain as a case study. Results of this research demonstrate that based on suggested model, negative wave creation and pressure increase in pipeline is prevented as well as decrease in manufacturing costs of air chamber.

RELAP5 analyses of overcooling transients in a pressurized water reactor

International Nuclear Information System (INIS)

Bolander, M.A.; Fletcher, C.D.; Ogden, D.M.; Stitt, B.D.; Waterman, M.E.

1983-01-01

In support of the Pressurized Thermal Shock Integration Study sponsored by the United States Nuclear Regulatory Commission, the Idaho National Engineering Laboratory has performed analyses of overcooling transients using the RELAP5/MOD1.5 computer code. These analyses were performed for Oconee Plants 1 and 3, which are pressurized water reactors of Babcock and Wilcox lowered-loop design. Results of the RELAP5 analyses are presented, including a comparison with plant data. The capabilities and limitations of the RELAP5/MOD1.5 computer code in analyzing integral plant transients are examined. These analyses require detailed thermal-hydraulic and control system computer models

Discussion of mechanical design for pressured cavity-air-receiver in solar power tower system

Energy Technology Data Exchange (ETDEWEB)

Fan, Zhilin; Zhang, Yaoming; Liu, Deyou; Wang, Jun; Liu, Wei [Hohai Univ., Nanjing (China). New Materials and Energy Sources Research and Exploitation Inst.

2008-07-01

In 2005, Hohai university and Nanjing Chunhui science and technology Ltd. of China, cooperating with Weizmann Institute of Science and EDIG Ltd. of Israel, built up a 70kWe solar power tower test plant in Nanjing, Jiangsu province, China, which was regarded as the first demonstration project to demonstrate the feasibility of solar power tower system in China. The system consists of heliostats field providing concentrated sunlight, a solar tower with a height of 33 meter, a pressured cavity-air-receiver transforming solar energy to thermal energy, a modified gas turbine adapting to solar power system, natural gas subsystem for solar-hybrid generation, cooling water subsystem for receiver and CPC, controlling subsystem for whole plant, et al. In this system, air acts as actuating medium and the system works in Brayton cycle. Testing results show that solar power tower system is feasible in China. To promote the development of solar powered gas turbine system and the pressured cavity-air-receiver technology in China, it is necessary to study the mechanical design for pressured Cavity-air-receiver. Mechanical design of pressured cavity-air-receiver is underway and some tentative principles for pressured cavity-air-receiver design, involving in power matching, thermal efficiency, material choosing, and equipment security and machining ability, are presented. At the same time, simplified method and process adapted to engineering application for the mechanical design of pressured cavity-air-receiver are discussed too. Furthermore, some design parameters and appearance of a test sample of pressured cavity-air-receiver designed in this way is shown. It is appealed that, in China, the research in this field should be intensified and independent knowledge patents for pivotal technological equipments such as receiver in solar power tower system should be formed. (orig.)

A review on water fault diagnosis of PEMFC associated with the pressure drop

International Nuclear Information System (INIS)

Pei, Pucheng; Li, Yuehua; Xu, Huachi; Wu, Ziyao

2016-01-01

Highlights: • Reviewed the effect factors and estimations of pressure drop associated with water fault diagnosis. • Reviewed pressure drop-based water fault diagnosis using different indicators. • Deviation of pressure drop is used frequently to diagnose water fault. • Reviewed recovery strategies based on pressure drop used in commercial PEMFC. • Merits, demerits and application prospects of pressure drop-based water fault diagnosis are discussed. - Abstract: The pressure difference between the inlet and outlet of the reactant in fuel cells is called the pressure drop, which is related to the water amount inside the fuel cells. In recent years there have been many studies that used the pressure drop to detect the water content and diagnose water fault of proton exchange membrane fuel cells (PEMFCs). To our knowledge, there has not been a systematic review of these studies. In this paper, the effect variables of pressure drop are reviewed firstly. Then estimations of the theoretical pressure drop are reviewed mainly based on the following four aspects: Bernoulli’s equation, two-phase flow multiplier, Darcy’s law and artificial intelligence. Afterward, the water fault diagnosis based on the pressure drop using the following six indicators are reviewed: indicator of direct pressure drop, its deviation, frequency, multiplier, the ratio of pressure drop to flow rate and the flooding degree. In addition, the strategies of water fault recovery are also summarized. Finally the merits, demerits and application prospects of pressure drop-based water fault diagnosis are presented.

Social-historical memory about soviet the pas: empiric research

Directory of Open Access Journals (Sweden)

E. G. Pozdnyakova­Kirbatyeva

2014-06-01

Also considered komomeratyvni properties attitude to the soviet past in the population of different regions of the country and the most general description of the memory of the soviet past, namely the degree of interest of the population of different regions to the past.

Study on the quantitative rod internal pressure design criterion

International Nuclear Information System (INIS)

Kim, Kyu Tae; Kim, Oh Hwan; Han, Hee Tak

1991-01-01

The current rod internal pressure criterion permits fuel rods to operate with internal pressures in excess of system pressure only if internal overpressure does not cause the diametral gap enlargement. In this study, the generic allowable internal gas pressure not violating this criterion is estimated as a function of rod power. The results show that the generic allowable internal gas pressure decreases linearly with the increase of rod power. Application of the generic allowable internal gas pressure for the rod internal pressure design criterion will result in the simplication of the current design procedure for checking the diametral gap enlargement caused by internal overpressure because according to the current design procedure the cladding creepout rate should be compared with the fuel swelling rate at each axial node at each time step whenever internal pressure exceeds the system pressure. (Author)

SIMULATION OF NEGATIVE PRESSURE WAVE PROPAGATION IN WATER PIPE NETWORK

Directory of Open Access Journals (Sweden)

Tang Van Lam

2017-11-01

Full Text Available Subject: factors such as pipe wall roughness, mechanical properties of pipe materials, physical properties of water affect the pressure surge in the water supply pipes. These factors make it difficult to analyze the transient problem of pressure evolution using simple programming language, especially in the studies that consider only the magnitude of the positive pressure surge with the negative pressure phase being neglected. Research objectives: determine the magnitude of the negative pressure in the pipes on the experimental model. The propagation distance of the negative pressure wave will be simulated by the valve closure scenarios with the help of the HAMMER software and it is compared with an experimental model to verify the quality the results. Materials and methods: academic version of the Bentley HAMMER software is used to simulate the pressure surge wave propagation due to closure of the valve in water supply pipe network. The method of characteristics is used to solve the governing equations of transient process of pressure change in the pipeline. This method is implemented in the HAMMER software to calculate the pressure surge value in the pipes. Results: the method has been applied for water pipe networks of experimental model, the results show the affected area of negative pressure wave from valve closure and thereby we assess the largest negative pressure that may appear in water supply pipes. Conclusions: the experiment simulates the water pipe network with a consumption node for various valve closure scenarios to determine possibility of appearance of maximum negative pressure value in the pipes. Determination of these values in real-life network is relatively costly and time-consuming but nevertheless necessary for identification of the risk of pipe failure, and therefore, this paper proposes using the simulation model by the HAMMER software. Initial calibration of the model combined with the software simulation results and

U.S. Technology Transfer to the Soviet Union: A Dilemma

Science.gov (United States)

1981-04-01

University, Mikhael Kuzmin and Russian Drama, 1906-1936; Edith W. Clowes, 10 months at the Moscow State University, Friedrich Nietzsche in Russia, 1890...According to Representative Paul Findley’s article in the Congressional Record, 54 - The Soviet "students" are far older than their American...relay point for orders for copies of articles from publishers, libraries, and information centers. NTIS said that the following design goals were met

Soviet/Russian-American space cooperation

Science.gov (United States)

Karash, Yuri Y.

This dissertation seeks to answer two questions: (1) what are the necessary conditions for the emergence of meaningful space cooperation between Russia and the United States, and (2) might this cooperation continue developing on its own merit, contributing to the further rapprochement between the two countries, even if the conditions that originated the cooperation were to change? The study examines the entire space era up to this point, 1957 to 1997, from the first satellite launch through the joint U.S.-Russian work on the ISS project. It focuses on the analysis of three distinct periods of possible and real cooperation between the United States and the Soviet Union/Russia. The first possibility for a limited Soviet-American cooperation in space emerged in the late 1950s, together with the space age, and continued until the mid-1960s. The major potential joint project of this period was a human expedition to the Moon. The global competition/confrontation between the two countries prevented actual cooperation. The second period was from the late 1960s until 1985 with consideration of experimental docking missions, including the docking of a reusable U.S. shuttle to a Soviet Salyut-type station. The global U.S.-Soviet competition still continued, but the confrontation was replaced by detente for a brief period of time lasting from the end of 1960s until mid-1970s. Detente gave the first example of U.S.-Soviet cooperation in space---the Apollo-Soyuz joint space flight (ASTP) which took place in 1975. However, the lack of interest of political leaderships in continuation of broad-scale cooperation between the two countries, and the end of detente, removed ASTP-like projects out of question at least until 1985. The third period started together with Mikhail Gorbachev's Perestroika in 1985 and continues until now. It involves almost a hundred of joint space projects both at the governmental and at the private sectors levels. The mainstream of the joint activities

Neutron fluence determination for light water reactor pressure vessels

International Nuclear Information System (INIS)

Gold, R.

1994-01-01

A general description of limitations that exist in pressure vessel neutron fluence determinations for commercial light water reactors is presented. Complexity factors that arise in light water reactor pressure vessel neutron fluence calculations are identified and used to analyze calculational limitations. Two broad categories of calculational limitations are introduced, namely benchmark field limitations and deep penetration limitations. Explicit examples of limitations that can arise in each of these two broad categories are presented. These limitations are used to show that the recent draft regulatory guide for the determination of pressure vessel neutron fluence, developed by the Nuclear Regulatory Commission, is based upon procedures and assumptions that are not valid. To eliminate the complexity and limitations of calculational methods, it is recommended that the determination of light water reactor pressure vessel neutron fluence be based upon experiment. Recommendations for improved methods of pressure vessel surveillance neutron dosimetry are advanced

Reflooding phase after loss of coolant of an advanced pressurized water reactor with high conversion ratio

International Nuclear Information System (INIS)

Schumann, S.

1984-01-01

The emergency core cooling behaviour of an advanced pressurized water reactor (APWR) during the reflooding phase of the LOCA with double-ended break is analysed and compared to a common pressurized water reactor (PWR). The code FLUT-BS, its models and correlations are explained in detail and have been verified by numerous PWR-reflood experiments with large parameter range. The influence of core-design on ECC-behaviour as well as the influences of initial and boundary values are examined. The results show the essential differences of ECC-behaviour between PWR and APWR. (orig.) [de

Is high-pressure water the cradle of life?

International Nuclear Information System (INIS)

Bassez, Marie-Paule

2003-01-01

Several theories have been proposed for the synthesis of prebiotic molecules. This letter shows that the structure of supercritical water, or high-pressure water, could trigger prebiotic synthesis and the origin of life deep in the oceans, in hydrothermal vent systems. Dimer geometries of high-pressure water may have a point of symmetry and a zero dipole moment. Consequently, simple apolar molecules found in submarine hydrothermal vent systems will dissolve in the apolar environment provided by the apolar form of the water dimer. Apolar water could be the medium which helps precursor molecules to concentrate and react more efficiently. The formation of prebiotic molecules could thus be linked to the structure of the water inside chimney nanochannels and cavities where hydrothermal piezochemistry and shock wave chemistry could occur. (letter to the editor)

Redefined Soviet military doctrine in perspective

International Nuclear Information System (INIS)

Menning, B.W.

1992-01-01

On May 29, 1987, the Warsaw Pact's Political Consultative Committee issued a communique proclaiming that the military doctrine of the Warsaw Pact member states is strictly defensive and proceeds from the fact that the application of military means to resolve any dispute is inadmissible under current conditions. Following this declaration, a corresponding redefinition of Soviet military doctrine to emphasize defensiveness and war prevention has evoke lively commentary and debate in both the West and the East. Because doctrinal issues are likely to retain significance during arms control and security negotiations. The purpose of this paper is to highlight important trends associated with a continuing dialogue over Soviet military doctrine and to assess what the future portends as doctrinal discussions unfold. Since 1987 the accelerating pace of change has accentuated the importance of doctrinally related concerns. As a result of the INF Treaty and the Stockholm agreement, there has been greater transparency regarding Soviet and Warsaw Pact military developments. On December 7, 1988, General Secretary Mikhail Gorbachev announced unilateral troop reduction over the next two years, which, when completed, would reduce the offensive capabilities of Soviet forces in Eastern Europe. In March 1989 talks on Confidence- and Security-Building Measures (CSBM) opened in Vienna, with suggestions for exchanges of views on military policy. At the very same time, NATO and the Warsaw Pact began formal negotiations on reduction of Conventional Forces in Europe (CFE) with a specific mandate to reduce those asymmetries that most favored prosecution of deep operations

Capillarity Induced Negative Pressure of Water Plugs in Nanochannels

NARCIS (Netherlands)

Tas, Niels Roelof; Mela, P.; Kramer, Tobias; Berenschot, Johan W.; van den Berg, Albert

2003-01-01

We have found evidence that water plugs in hydrophilic nanochannels can be at significant negative pressure due to tensile capillary forces. The negative pressure of water plugs in nanochannels induces bending of the thin channel capping layer, which results in a visible curvature of the liquid

Imaging optical probe for pressurized steam-water environment

International Nuclear Information System (INIS)

Donaldson, M.R.; Pulfrey, R.E.

1979-01-01

An air-cooled imaging optical probe, with an outside diameter of 25.4 mm, has been developed to provide high resolution viewing of flow regimes in a steam-water environment at 343 0 C and 15.2 MPa. The design study considered a 3-m length probe. A 0.3-m length probe prototype was fabricated and tested. The optical probe consists of a 3.5-mm diameter optics train surrounded by two coaxial coolant flow channels and two coaxial insulating dead air spaces. With air flowing through the probe at 5.7 g/s, thermal analysis shows that no part of the optics train will exceed 93 0 C when a 3-m length probe is immersed in a 343 0 C environment. Computer stress analysis plus actual tests show that the probe can operate successfully with conservative safety factors. The imaging optical probe was tested five times in the design environment at the semiscale facility at the INEL. Two-phase flow regimes in the high temperature, high pressure, steam-water blowdown and reflood experiments were recorded on video tape for the first time with the imaging optical probe

Radonclose - the system of Soviet designed regional waste management facilities

International Nuclear Information System (INIS)

Horak, W.C.; Reisman, A.; Purvis, E.E. III.

1997-01-01

The Soviet Union established a system of specialized regional facilities to dispose of radioactive waste generated by sources other than the nuclear fuel cycle. The system had 16 facilities in Russia, 5 in Ukraine, one in each of the other CIS states, and one in each of the Baltic Republics. These facilities are still being used. The major generators of radioactive waste they process these are research and industrial organizations, medical and agricultural institution and other activities not related to nuclear power. Waste handled by these facilities is mainly beta- and gamma-emitting nuclides with half lives of less than 30 years. The long-lived and alpha-emitting isotopic content is insignificant. Most of the radwaste has low and medium radioactivity levels. The facilities also handle spent radiation sources, which are highly radioactive and contain 95-98 percent of the activity of all the radwaste buried at these facilities

Design and operational parameters of transportable supercritical water oxidation waste destruction unit

International Nuclear Information System (INIS)

McFarland, R.D.; Brewer, G.R.; Rofer, C.K.

1991-12-01

Supercritical water oxidation (SCWO) is the destruction of hazardous waste by oxidation in the presence of water at temperatures and pressures above its critical point. A 1 gal/h SCWO waste destruction unit (WDU) has been designed, built, and operated at Los Alamos National Laboratory. This unit is transportable and is intended to demonstrate the SCWO technology on wastes at Department of Energy sites. This report describes the design of the WDU and the preliminary testing phase leading to demonstration

STUDY OF WATER HAMMERS IN THE FILLING OF THE SYSTEM OF PRESSURE COMPENSATION IN THE WATER-COOLED AND WATER-MODERATED POWER REACTORS

Directory of Open Access Journals (Sweden)

A. V. Korolyev

2017-01-01

Full Text Available The research presented in the article conforms to the severe accident that took place at the Three Mail Island nuclear power plant in the USA. The research is focused on improving the reliability of the pressure compensator that is an important equipment of the primary circuit. In order to simulate such a situation, the stand has been developed to simulate the design of the pressurizer of the PWR-440 reactor, in particular an elliptical shape of the upper lid which has a steam outlet pipe at the top of the construction that creates conditions for occurrence of such water hammers. For the experiments, an installation has been created that makes it possible to measure and record the water hammering that occur when the tanks are filled. Measurement of the amplitude of the water hammering was carried out by a specially developed piezoelectric sensor, and the registration – by a light-beam oscilloscope. The technique of carrying out the experiment is described and the results of an experimental study of the water hammers arising when the vessels are completely filled are presented. Quantitative data were obtained on the amplitudes of the hydraulic impacts depending on the rate of filling of the vessel and the diameter of the outlet, the maximum pressure of the hydraulic shock was 7–9 atm. Comparison of calculated and experimental data has been performed. The allowable discrepancy is explained by the calculated value of the system stiffness coefficient, which did not take into account the presence of welded seams in the tank that imparts the system with additional rigidity. The calculated relationships are obtained, that make it possible to estimate the amplitudes of the water hammers through the acceleration of the water level in front of the outlet from a vessel with an elliptical bottom. The possibility of a water hammer in the pressure compensator is demonstrated by experiment and by theoretical calculations. Based on the experimental data, a

Optimization and Prototyping of Medium Pressure Water (MPW) Depaint Process, Tri-Service Committee on Corrosion Proceedings

National Research Council Canada - National Science Library

Stropki, John

1994-01-01

This research program was designed to evaluate the potential of a paint stripping process that utilizes a medium pressure water jet as a viable alternative to the current practice of paint stripping...

Soviet Cultural Diplomacy in Denmark during the Cold War

DEFF Research Database (Denmark)

Frederichsen, Kim

2012-01-01

The article discusses the Soviet apparatus for cultural diplomacy abroad during the Cold War period using the worlds oldest society for friendship with the Soviet Union as a case study. The article looks at question from 3 diffrent angels: 1: Organisation, planning and financing. 2: Activities. 3...

Soviet Union in the context of the Nobel prize

CERN Document Server

Blokh, Abram M

2018-01-01

The result of meticulous research by Professor Abram Blokh, this book presents facts, documents, thoughts and comments on the system of the Nobel Prize awards to Russian and Soviet scientists. It provides a comprehensive overview of the relationship between the ideas expressed by the Nobel Foundation and those expressed by the autocratic and totalitarian regimes in Russia and the ex-Soviet Union during the 20th century who had the same attitude of revulsion toward the intellectual and humanistic values represented by the Nobel Prizes. To do his research, the author had access to the declassified documents in the archives of the Nobel Foundation for many years. Also included in the book are new materials obtained and developed by the author after the publication of the first two editions (in Russian). This additional information is from the archives of the Soviet Ministry of Foreign Affairs, the Russian Academy of Sciences, the Soviet Writers' Union et al. in Moscow and St Petersburg. These documents shed new...

Soviet exoatmospheric neutral particle beam research

International Nuclear Information System (INIS)

Leiss, J.E.; Abrams, R.H.; Ehlers, K.W.; Farrell, J.A.; Gillespie, G.H.; Jameson, R.A.; Keefe, D.; Parker, R.K.

1988-02-01

This technical assessment was performed by a panel of eight U.S. scientists and engineers who are familiar with Soviet research through their own research experience, their knowledge of the published scientific literature and conference proceedings, and personal contacts with Soviet scientists and other foreign colleagues. Most of the technical components of a neutral particle beam generating system including the ion source, the accelerator, the accelerator radio frequency power supply, the beam conditioning and aiming system, and the beam neutralizer system are addressed. It does not address a number of other areas important to an exoatmospheric neutral beam system

A dual pressurized water reactor producing 2000 MWe

International Nuclear Information System (INIS)

Kang, K. M.; Suh, K. Y.

2010-01-01

The Dual Unit Optimizer 2000 MWe (DUO2000) is proposed as a new design concept for large nuclear power plant. DUO is being designed to meet economic and safety challenges facing the 21. century green and sustainable energy industry. DUO2000 has two nuclear steam supply systems (NSSSs) of the Unit Nuclear Optimizer (UNO) pressurized water reactor (PWR) in a single containment so as to double the capacity of the plant. UNO is anchored to the Optimized Power Reactor 1000 MWe (OPR1000). The concept of DUO can be extended to any number of PWRs or pressurized heavy water reactors (PHWRs), or even boiling water reactor (BWRs). Once proven in water reactors, the technology may even be expanded to gas cooled, liquid metal cooled, and molten salt cooled reactors. In particular, since it is required that the Small and Medium sized Reactors (SMRs) be built as units, the concept of DUO2000 will apply to SMRs as well. With its in-vessel retention external reactor vessel cooling (IVR-ERVC) as severe accident management strategy, DUO can not only put the single most querulous PWR safety issue to end, but also pave ways to most promising large power capacity dispensing with huge redesigning cost for Generation III+ nuclear systems. Also, the strengths of DUO2000 include reducing the cost of construction by decreasing the number of containment buildings from two to one, minimizing the cost of NSSS and control systems by sharing between the dual units, and lessening the maintenance cost by uniting the NSSS. Two prototypes are presented for the DUO2000, and their respective advantages and drawbacks are considered. The strengths include, but are not necessarily limited to, reducing the cost of construction by decreasing the number of containment buildings from two to one, minimizing the cost of NSSS and control systems by sharing between the dual units, and lessening the maintenance cost by uniting the NSSS, just to name the few. The Coolant Unit Branching Apparatus (CUBA) is proposed

Integrity of the reactor coolant boundary of the European pressurized water reactor (EPR)

Energy Technology Data Exchange (ETDEWEB)

Goetsch, D.; Bieniussa, K.; Schulz, H.; Jalouneix, J.

1997-04-01

This paper is an abstract of the work performed in the frame of the development of the IPSN/GRS approach in view of the EPR conceptual safety features. EPR is a pressurized water reactor which will be based on the experience gained by utilities and designers in France and in Germany. The reactor coolant boundary of a PWR includes the reactor pressure vessel (RPV), those parts of the steam generators (SGs) which contain primary coolant, the pressurizer (PSR), the reactor coolant pumps (RCPs), the main coolant lines (MCLs) with their branches as well as the other connecting pipes and all branching pipes including the second isolation valves. The present work covering the integrity of the reactor coolant boundary is mainly restricted to the integrity of the main coolant lines (MCLs) and reflects the design requirements for the main components of the reactor coolant boundary. In the following the conceptual aspects, i.e. design, manufacture, construction and operation, will be assessed. A main aspect is the definition of break postulates regarding overall safety implications.

Integrity of the reactor coolant boundary of the European pressurized water reactor (EPR)

International Nuclear Information System (INIS)

Goetsch, D.; Bieniussa, K.; Schulz, H.; Jalouneix, J.

1997-01-01

This paper is an abstract of the work performed in the frame of the development of the IPSN/GRS approach in view of the EPR conceptual safety features. EPR is a pressurized water reactor which will be based on the experience gained by utilities and designers in France and in Germany. The reactor coolant boundary of a PWR includes the reactor pressure vessel (RPV), those parts of the steam generators (SGs) which contain primary coolant, the pressurizer (PSR), the reactor coolant pumps (RCPs), the main coolant lines (MCLs) with their branches as well as the other connecting pipes and all branching pipes including the second isolation valves. The present work covering the integrity of the reactor coolant boundary is mainly restricted to the integrity of the main coolant lines (MCLs) and reflects the design requirements for the main components of the reactor coolant boundary. In the following the conceptual aspects, i.e. design, manufacture, construction and operation, will be assessed. A main aspect is the definition of break postulates regarding overall safety implications

Reactor water spontaneous circulation structure in reactor pressure vessel

International Nuclear Information System (INIS)

Takahashi, Kazumi

1998-01-01

The gap between the inner wall of a reactor pressure vessel of a BWR type reactor and a reactor core shroud forms a down comer in which reactor water flows downwardly. A feedwater jacket to which feedwater at low temperature is supplied is disposed at the outer circumference of the pressure vessel just below a gas/water separator. The reactor water at the outer circumferential portion just below the air/water separator is cooled by the feedwater jacket, and the feedwater after cooling is supplied to the feedwater entrance disposed below the feedwater jacket by way of a feedwater introduction line to supply the feedwater to the lower portion of the down comer. This can cool the reactor water in the down comer to increase the reactor water density in the down comer thereby forming strong downward flows and promote the recycling of the reactor water as a whole. With such procedures, the reactor water can be recycled stably only by the difference of the specific gravity of the reactor water without using an internal pump. In addition, the increase of the height of the pressure vessel can be suppressed. (I.N.)

High Pressure Water Jet System Performance Assessment Project A-2A

International Nuclear Information System (INIS)

FARWICK, C.C.

1999-01-01

Performance assessment for canister cleaning system in the KE Basin. Information obtained from this assessment will be used to design any additional equipment used to clean canisters. After thorough review of the design, maintenance history and operational characteristics of the 105 K East (KE) canister cleaning system, Bartlett recommends that the high pressure water jet system (HPWJS) be modified as outlined in section 5.0, and retained for future use. Further, it is recommended that Spent Nuclear Fuel (SNF) Project consider use of a graded approach for canister cleaning, based on individual canister type and characteristics. This approach would allow a simple method to be used on canisters not needing the more rigorous, high-pressure method. Justification is provided in section 5.0. Although Bartlett has provided some preliminary cost estimates, it is recommended that SNF Project perform a detailed cost-benefit analysis to weigh the alternatives presented

Marxism--Leninism and natural resources: the Soviet outlook

Energy Technology Data Exchange (ETDEWEB)

Papp, D.S.

1977-06-01

Soviet leaders recognize that natural resources are finite, but they do not share the pessimism of many of their Western counterparts. They maintain that resource depletion is not a threat to be taken seriously on a worldwide basis, but rather is a manifestation of the capitalism. To understand both the continued Soviet optimism and the Soviet assessment of why the Western world is experiencing its current ''raw material crisis'', the author examines the role that natural resources play within Marxist-Leninist idealogy. Soviets believe, the author says, that the resource predicament is insoluble; that the condition will escalate until, along with several other factors, the situation will result in a worldwide socialist society. Western thought has advocated fine methods through which the industrialized world could evade the energy and raw materials shortages. These include new methods of mining, developing, and searching for natural resource deposits; setting up a non-socialist industrial nations' organization; appropriation of resource sites; zero growth rates; and genuine cooperation. The Kremlin discounts the West's ability to successfully carry out any of these solutions. (MCW)

Development status and application prospect of supercritical-pressure light water cooled reactor

International Nuclear Information System (INIS)

Li Manchang; Wang Mingli

2006-01-01

The Supercritical-pressure Light Water Cooled Reactor (SCWR) is selected by the Generation IV International Forum (GIF) as one of the six Generation IV nuclear systems that will be developed in the future, and it is an innovative design based on the existing technologies used in LWR and supercritical coal-fired plants. Technically, SCWR may be based on the design, construction and operation experiences in existing PWR and supercritical coal-fired plants, which means that there is no insolvable technology difficulties. Since PWR technology will be adopted in the near term and medium term projects in China, and considering the sustainable development of the technology, it is an inevitable choice to research and develop the nuclear system of supercritical light water cooled reactor. (authors)

JPRS Report, Soviet Union, World Economy & International Relations, No. 5, May 1988

Science.gov (United States)

1988-10-06

percent (2). The socialist states (the PRC, DPRK, Mongolia, Viet - nam , Cambodia and Laos) are the Soviet Union’s prin- cipal foreign trade partners: our...right is no longer attempting to maintain that the Soviet leader- ship’s new course amounts to cosmetic or purely propa- ganda measures. Soviet

Reactor vessel pressure transient protection for pressurized water reactors

International Nuclear Information System (INIS)

Zech, G.

1978-09-01

During the past few years the NRC has been studying the issue of protection of the reactor pressure vessels at Pressurized Water Reactors (PWRs) from transients when the vessels are at a relatively low temperature. This effort was prompted by concerns related to the safety margins available to vessel damage as a result of such events. Nuclear Reactor Regulation Category A Technical Activity No. A-26 was established to set forth the NRC plan for resolution of the generic aspects of this safety issue. The purpose of the report is to document the completion of this generic technical activity

Soviet energy: current problems and future options

Energy Technology Data Exchange (ETDEWEB)

Stein, J B

1981-12-01

The connection between Soviet oil and energy resources, their efficient and timely utilization, and politico-military opportunities in the Persian Gulf region offer an inescapable link for analysis. Worsening trends in economic growth, factor productivity, social unrest, and energy production/distribution offset optimistic trends in Soviet military procurement and deployment. A conjunction of geologic, geographic, and systemic factors all point to a mid-1980s energy imbalance which in turn will pose hard questions for the Moscow leadership. 28 references.

Soviet command and control in a historical context

OpenAIRE

Kern, Jeffrey A.

1981-01-01

Approved for public release; distribution is unlimited An examination is made of the historical antecedents of present day command and control doctrine in the Soviet Union. The continuity of principal characteristics is demonstrated. The ideological determinants shaping the command and control system are first developed. These include centralism, collective decision-making, unity of command, and redundancy. Practical consequences of these are explored. The functioning of Soviet command...

Soviet civil defense plans make nuclear war winnable

International Nuclear Information System (INIS)

Goure, L.

1985-01-01

In this paper, the author expresses his opinion that the U.S. is naive and suicidal in its lack of civil defense preparation for nuclear war. The Soviets' extensive civil defense planning is evidence that they plan to use their nuclear weapons and survive a counterattack by the U.S. The author compares the two systems and explains why the Soviets' system is superior

Geopolitics: The Key to Understanding Soviet Regional Behavior.

Science.gov (United States)

1987-04-01

Soviet foreign policy. nertnngthis role, CO can begin to build a usable theoretical framwork for analyzing Soviet behavior in, utategiczlly inportant...the writings of the great geopolitical theorists, such as Mackinder, Spykman, and Gray, in developing a conceptual basis for understanding the la-tem...Histary,- British geographer Sir Halford J. mdcinder provided the conceptual framewrk for geopolitical theory by dividing the world into three vast regions

Is Soviet society fit for the nuclear age

International Nuclear Information System (INIS)

Kemeny, L.G.

1986-01-01

The author argues that the Kremlin's handling of the Chernobyl crisis is a far greater indictment of Soviet ethos, society and ideology than their technology. The Soviet nuclear plan is seen to be to press on regardless of safety standards. Australia's government and society, through poor education, foreign disinformation and media orchestration, are unable to participate effectively in the responsibilities of a global nuclear society

Design and Construction of Strain Gauge Interface Pressure ...

African Journals Online (AJOL)

Design and Construction of Strain Gauge Interface Pressure Transducer for Measurement of Static and Dynamic Interface Pressure Applied by Pressure Garments and its Relationship to Deep Vein Thrombosis.

Hello, Lenin? Nostalgia On Post-Soviet Television In Russia And Ukraine

Directory of Open Access Journals (Sweden)

Kateryna Khinkulova

2012-11-01

Full Text Available After the collapse of the USSR in 1991, Soviet television looked old-fashioned and seemed redundant, with the emerging post-Soviet televisual cultures turning their gazes to global sources of inspiration. The next decade affected Russia and Ukraine in very different ways. In Russia brief exposure to what was seen as “cheap mass-culture” left TV viewers and producers disillusioned. With the change of attitude towards Western TV, the ideas about Soviet TV changed, too. From a grey and unexciting model Soviet TV had become a shining example of “high quality” and nostalgia-driven content set in for the next few years. In Ukraine, where no domestic TV had existed as such prior to 1991 and where Soviet TV was rapidly fading into the past (and some-one else’s past, too, a decade of experimenting with programming had left the TV producers much more open to global television formats and Western ideas, developing programmes very different than the Russian ones.

Vent clearing during a simulated loss-of-coolant accident in Mark I boiling-water-reactor pressure-suppression system

International Nuclear Information System (INIS)

Pitts, J.H.; McCauley, E.W.

1978-01-01

The response of the pressure-suspension containment system of Mark I boiling-water reactors to a loss-of-coolant accident (LOCA) is being studied. This response is a design basis for light-water nuclear reactors. Part of the study is being carried out on a 1 / 5 -scale experimental facility that models the pressure-suppression containment system of the Peach Bottom 2 nuclear power plant. The test series reported here focused on the initial or air-clearing phase of a hypothetical LOCA. Measured forces, measured pressures, and the hydrodynamic phenomena (observed with high-speed cameras) show a logical interrelationship

Tensile Strength of Water Exposed to Pressure Pulses

DEFF Research Database (Denmark)

Andersen, Anders Peter; Mørch, Knud Aage

2012-01-01

at an extended water-solid interface by imposing a tensile stress pulse which easily causes cavitation. Next, a compressive pulse of duration ~1 ms and a peak intensity of a few bar is imposed prior to the tensile stress pulse. A dramatic increase of the tensile strength is observed immediately after......It is well known that pressurization for an extended period of time increases the tensile strength of water, but little information is available on the effect of pressure pulses of short duration. This is addressed in the present paper where we first measure the tensile strength of water...

Analysis and Experimental Qualification of an Irradiation Capsule Design for Testing Pressurized Water Reactor Fuel Cladding in the High Flux Isotope Reactor

Energy Technology Data Exchange (ETDEWEB)

Smith, Kurt R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Howard, Richard H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Daily, Charles R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Petrie, Christian M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-09-01

The Advanced Fuels Campaign within the Fuel Cycle Research and Development program of the Department of Energy Office of Nuclear Energy is currently investigating a number of advanced nuclear fuel cladding concepts to improve the accident tolerance of light water reactors. Alumina-forming ferritic alloys (e.g., FeCrAl) are some of the leading candidates to replace traditional zirconium alloys due to their superior oxidation resistance, provided no prohibitive irradiation-induced embrittlement occurs. Oak Ridge National Laboratory has developed experimental designs to irradiate thin-walled cladding tubes with representative pressurized water reactor geometry in the High Flux Isotope Reactor (HFIR) under relevant temperatures. These designs allow for post-irradiation examination (PIE) of cladding that closely resembles expected commercially viable geometries and microstructures. The experiments were designed using relatively inexpensive rabbit capsules for the irradiation vehicle. The simplistic designs combined with the extremely high neutron flux in the HFIR allow for rapid testing of a large test matrix, thus reducing the time and cost needed to advanced cladding materials closer to commercialization. The designs are flexible in that they allow for testing FeCrAl alloys, stainless steels, Inconel alloys, and zirconium alloys (as a reference material) both with and without hydrides. This will allow a direct comparison of the irradiation performance of advanced cladding materials with traditional zirconium alloys. PIE will include studies of dimensional change, microstructure variation, mechanical performance, etc. This work describes the capsule design, neutronic and thermal analyses, and flow testing that were performed to support the qualification of this new irradiation vehicle.

DOSTOEVSKY'S RELIGIOSITY AS A METHODOLOGICAL PROBEM OF SOVIET LITERARY CRITICISM

Directory of Open Access Journals (Sweden)

Sergey Sergeevich Shaulov

2012-11-01

Full Text Available Soviet literary criticism, especially in the first decades after the 1917 Revolution, was quite biased in its treatment of Dostoevsky and his works. The reasons for this bias lie both inside and outside the sphere of political ideology. We suggest that there exists a genetic link between some Soviet readings of Dostoevsky and a number of interpretations made in the author's lifetime. Also analysed are the attempts to 'domesticate' Dostoevsky and adapt his works to drastically different cultural conditions and political norms. It is indicative that this adaptation has always passed the stage of mythologizing the writer and his works. This mythologization paradoxically became a convergence point for Soviet (Lunacharsky, anti-Soviet (Berdyayev and purely philosophical (Bakhtin readings of Dostoevsky. Ultimately, the central Dostoevsky myth in post-revolutionary Russia was a version of Romantic mythology often directly expressed in comparing Dostoevsky with Prometheus. We also look at the negative readings of Dostoevsky, which construed the author as a certain mythological antagonist of the proletariat as the collective messiah. Such readings (exemplified in our article by Pereverzev's and Livshits' point at the ultimate limit of ethical assessment of Dostoevsky from the standpoint of rational secular humanism and the Soviet humanitarian thought as its version. Dostoevsky's artistic practice incorporates this tradition within the intranovel dialogue as just one of the voices and demonstrates its ethical insufficiency, which in its turn provokes the mixed reaction of 'appropriation' and 'rejection' from both Soviet thinkers and their contemporary heirs.

Supercritical-pressure, once-through cycle light water cooled reactor concept

International Nuclear Information System (INIS)

Oka, Yoshiaki; Koshizuka, Seiichi

2001-01-01

The purpose of the study is to develop new reactor concepts for the innovation of light water reactors (LWR) and fast reactors. Concept of the once-through coolant cycle, supercritical-pressure light water cooled reactor was developed. Major aspects of reactor design and safety were analysed by the computer codes which were developed by ourselves. It includes core design of thermal and fast reactors, plant system, safety criteria, accident and transient analysis, LOCA, PSA, plant control, start up and stability. High enthalpy rise as supercritical boiler was achieved by evaluating the cladding temperature directly during transients. Fundamental safety principle of the reactor is monitoring coolant flow rate instead of water level of LWR. The reactor system is compact and simple because of high specific enthalpy of supercritical water and the once-through cycle. The major components are similar to those of LWR and supercritical thermal plant. Their temperature are within the experiences in spite of the high outlet coolant temperature. The reactor is compatible with tight fuel lattice fast reactor because of the high head pumps and low coolant flow rate. The power rating of the fast reactor is higher than the that of thermal reactor because of the high power density. (author)

The Soviet Union and population: theory, problems, and population policy.

Science.gov (United States)

Di Maio, A J

1980-04-01

Until the important public dialog on 3rd World population issues began in the Soviet Uuion in 1965, ideological limitations and bureaucratic interests prevented policy makers from recognizing the existence of a world of national "population problem." Since then, freer discussions of the Soviet Union's surprising decline in birthrate and labor shortages have led to serious policy questions. Conflicting policy goals, however, have resulted in only modest pronatalist policies. The Soviet population problem is a result of interregional disparities in population growth rates between the highly urbanized Soviet European populations with low birth rates and the least urbanized Central Asians with dramatically higher birth rates. As a result, these essentially Muslim people will provide the only major increases in labor resources and an increasing percentage of Soviet armed forces recruits. Policy planners are thus faced with difficult options. Current policies stressing technological transfers from the west and greater labor productivity, however, are unlikely to solve further labor shortages and regional imbalances. Ultimately, nonEuropana regions will be in an improved bargaining position for more favorable nationwide economic policies and for a greater role in policy planning.

Analytical study on water hammer pressure in pressurized conduits with a throttled surge chamber for slow closure

Directory of Open Access Journals (Sweden)

Yong-liang Zhang

2010-06-01

Full Text Available This paper presents an analytical investigation of water hammer in a hydraulic pressurized pipe system with a throttled surge chamber located at the junction between a tunnel and a penstock, and a valve positioned at the downstream end of the penstock. Analytical formulas of maximum water hammer pressures at the downstream end of the tunnel and the valve were derived for a system subjected to linear and slow valve closure. The analytical results were then compared with numerical ones obtained using the method of characteristics. There is agreement between them. The formulas can be applied to estimating water hammer pressure at the valve and transmission of water hammer pressure through the surge chamber at the junction for a hydraulic pipe system with a surge chamber.

CANDU with supercritical water coolant: conceptual design features

International Nuclear Information System (INIS)

Spinks, N.

1997-01-01

An advanced CANDU reactor, with supercritical water as coolant, has many attractive design features. The pressure exceeds 22 MPa but coolant temperatures in excess of 370 degrees C can be reached without encountering the two-phase region with its associated fuel-dry-out and flow-instability problems. Increased coolant temperature leads to increased plant thermodynamic efficiency reducing unit energy cost through reduced specific capital cost and reduced fueling cost. Increased coolant temperature leads to reduced void reactivity via reduced coolant in-core density. Light water becomes a coolant option. To preserve neutron economy, an advanced fuel channel is needed and is described below. A supercritical-water-cooled CANDU can evolve as fuel capabilities evolve to withstand increasing coolant temperatures. (author)

Experimental study on vapor explosion induced by pressure pulse in coarse mixing of hot molten metal and water

International Nuclear Information System (INIS)

Inoue, A.; Tobita, Y.; Aritomi, M.; Takahashi, M.; Matsuzaki, M.

2004-01-01

An experimental study was done to investigate characteristics of metal-water interaction, when a mount of hot liquid metal is injected into the water. The test section is a vertical shock tube of 60mm in inner diameter and 1200mm in length. A special injector which is designed to inject hot metal of controlled volume and flow rate is attached at the top of the tube. When the hot metal is injected in the water and comes down at a position of the test vessel, a trigger pressure pulse is generated at the bottom of the test tube. Local transient pressures along the tube are measured by piezo pressure transducers. The following items were investigated in the experiment; 1) The criteria to cause a vapor explosion, 2) Transient behaviors and propagation characteristics of pressure wave in the mixing region. 3) Effects of triggering pulse, injection temperature and mass of hot molten metal on the peak pressure. The probability of the vapor explosion jumped when the interface temperature at the molten metal-water direct contact is higher than the homogeneous nucleation temperature of water and the triggering pulse becomes larger than 0.9MPa. Two types of the pressure propagation modes are observed, one is the detonative mode with a sharp rise and other is usual pressure mode with a mild rise. (author)

Evaluation of water cooled supersonic temperature and pressure probes for application to 2000 F flows

Science.gov (United States)

Lagen, Nicholas T.; Seiner, John M.

1990-01-01

The development of water cooled supersonic probes used to study high temperature jet plumes is addressed. These probes are: total pressure, static pressure, and total temperature. The motivation for these experiments is the determination of high temperature supersonic jet mean flow properties. A 3.54 inch exit diameter water cooled nozzle was used in the tests. It is designed for exit Mach 2 at 2000 F exit total temperature. Tests were conducted using water cooled probes capable of operating in Mach 2 flow, up to 2000 F total temperature. Of the two designs tested, an annular cooling method was chosen as superior. Data at the jet exit planes, and along the jet centerline, were obtained for total temperatures of 900 F, 1500 F, and 2000 F, for each of the probes. The data obtained from the total and static pressure probes are consistent with prior low temperature results. However, the data obtained from the total temperature probe was affected by the water coolant. The total temperature probe was tested up to 2000 F with, and without, the cooling system turned on to better understand the heat transfer process at the thermocouple bead. The rate of heat transfer across the thermocouple bead was greater when the coolant was turned on than when the coolant was turned off. This accounted for the lower temperature measurement by the cooled probe. The velocity and Mach number at the exit plane and centerline locations were determined from the Rayleigh-Pitot tube formula.

HILOS DE TEATRO: LA PUESTA EN ESCENA DEL PALACIO DE LOS SOVIETS DE LE CORBUSIER, 1931 / Strands of theatre: Le Corbusier’s staging of the Palace of the Soviets, 1931

Directory of Open Access Journals (Sweden)

Josefina González Cubero

2012-11-01

Full Text Available RESUMEN El proyecto para el concurso del Palacio de los Soviets en Moscú (1931 de Le Corbusier plantea otra posible y más fragmentaria clave de interpretación que, aunque en principio sea más marginal, merece ser mencionada: la relación con el teatro, con la renovación de la escena europea y con la experimentación soviética, porque Le Corbusier es consciente de que la arquitectura no consiste sólo en la cualidad del edificio, es también una puesta en escena, una dramaturgia. Escenógrafos como Appia, con la luz, o directores de escena como Max Reinhardt, con el espectáculo de masas, y Vsevelod Meyerhold, con el teatro japonés del Kabuki, van penetrando en el sentir de un Le Corbusier que deja la impronta teatral en la puesta en escena de la megaestructura moscovita. SUMMARY Le Corbusier’s design submitted to the public competition for the Palace of the Soviets in Moscow (1931 may have an additional interpretation which, although less researched and in principal more marginal, is noteworthy. And that is the relationship between theatre and the resetting of the stage in Europe and Soviet experimentation. Le Corbusier was aware that architecture goes beyond the building itself and is also a sort of staging or dramaturgy. Set designers such as Appia, through the use of light, or stage directors like Max Reinhardt, through the use of performance for the masses, and Vsevelod Meyerhold, through Japonese Kabuki theatre, gradually permeated the sensibility of Le Corbusier who left staging as a mark in his design for the Moscow megastructure.

Franco-German nuclear cooperation: from the 'common product' to the first European pressurized water reactor

International Nuclear Information System (INIS)

Vignon, D.

1999-01-01

It has now been 10 years since Framatome and Siemens decided to collaborate on the design and sales of an advanced nuclear power plant (NPP) model based on pressurized water reactor (PWR) technology. Originally called the 'common product', this model was renamed the European pressurized water reactor when Electricite de France (EDF) and the German electric utilities joined this cooperative development effort in 1992. Since the beginning, this cooperation has been formalized in the framework of an agreement that led to the founding of a joint and equally owned subsidiary, Nucler Power International (NPI), which is reponsible for leading the development of the new model and later handling its export sales

Water chemistry of Atucha II PHWVR. Design concepts and evolution

International Nuclear Information System (INIS)

Chocron, Mauricio; Rodriguez, Ivanna; Duca, Jorge; Fernandez, Ricardo; Rico, Jorge

2007-01-01

Full text: Atucha II is a pressurized heavy water vessel reactor designed by Siemens-KWU, currently part of AREVA NP, of 745 MWe and similar to Atucha I, which has been in operation over 25 years. The primary heat transport system (PHTS) is composed by vertical channels (277-313 C degrees) that allocate the fuel elements while the moderator circuit is composed by a partially separated circuit (142-173 C degrees). The moderation power is transferred to the feedwater through the moderator heat exchangers (HX). These HXs operate as the last, high pressure water-steam cycle heaters as well. Materials (with exception of fuel channels and fuel sheaths which are made of zirconium alloys) are all austenitic steels while cobalt containing alloys have been all replaced at the design stage. Steam generator and moderator HX tubing are Alloy 800 made. The core is operated without boron except with the first fresh nucleus. The secondary circuit or Balance of plant (BOP) is similar in conception to that of a PWR but the moderator HXs. It is entirely built of ferrous alloys, has a feedwater-deaerator tank and moisture separator. The energy sink is the Rio de la Plata River. The Reactors Chemistry Department, Chemistry Division, National Atomic Energy Commission, in its character of R and D institution has been committed by CNA II-N.A.S.A Project to prepare the water chemistry specifications, water chemistry engineering and manuals, considering the type of reactor, design and construction aspects and operation characteristics, taking into account the current state-of-the art and worldwide standards. This includes conceptual aspects and implementation and operative aspects as well. This documentation will be released after a designer's review as it has been stated in the respective agreement. Respecting the confidentiality agreement between CNEA and NASA and the confidentiality regarding handling original documentation provided by the designer, it is considered illustrative to

Impact of moderator history on physics parameters in pressurized water reactors

International Nuclear Information System (INIS)

Mosteller, R.D.

1988-01-01

The magnitude of differential reactivity effects that result from spectral differences in different portions of a pressurized water (PWR) core is studied, and it is shown that these effects can be correlated very well with the local moderator history. The impact of these differences on physics parameters such as axial offset, isothermal moderator temperature coefficient, and differential control rod worth is shown to be significant for two PWRs of considerably different design

Nõukogude garaažikultuur. Soviet Garage Culture

Directory of Open Access Journals (Sweden)

Tauri Tuvikene

2012-04-01

Full Text Available Apart from its manifestation in the form of political ideology, the arts and the economic system, socialism also manifested itself in space. The socialist space did not only take shape ideologically, but was also influenced by societal limitations and possibilities. Because of this, it is important to shed light on everyday life in the Soviet Union, which did not necessarily consist of big slogans or open opposition, and which neither expressed loud support nor aversion in relation to the Soviet system. In this article I take a look at the garage areas (which were usually built in clusters as spatial elements, and the garage culture associated with them. I describe how the garage was a necessary part of the car culture in Soviet society, a part which at times comprised objects, practices and meanings of its own: in other words, a garage culture. Cars have had a major impact on cityscapes in the West, where the number of cars per capita was many times larger than in the Soviet Union, but car usage has left its mark in socialist cities as well. Getting around in a car inevitably means aneed to park it somewhere; this basic fact applied to both sides of the Iron Curtain. However, garage areas have carried more importance in socialist societies – there is more of them, and they feature a large amount of parking spaces (hundreds if not thousands. The reason for this popularity was societal limitations and possibilities: on the one hand there was an opportunity for extensive land use brought about by the state ownership of land untouched by free-market search for profitability, but on the other hand there were also obstacles, created by a deficit. By enabling the car owner to keep his vehicle going, the garage had a concrete role to play in the Soviet economic system. The garage was a place where you could repair your car, store spare parts and protect it from potential theft. The role of the garage in Soviet car culture as described in this article

Taipower's reload safety evaluation methodology for pressurized water reactors

International Nuclear Information System (INIS)

Huang, Ping-Hue; Yang, Y.S.

1996-01-01

For Westinghouse pressurized water reactors (PWRs) such as Taiwan Power Company's (TPC's) Maanshan Units 1 and 2, each of the safety analysis is performed with conservative reload related parameters such that reanalysis is not expected for all subsequent cycles. For each reload cycle design, it is required to perform a reload safety evaluation (RSE) to confirm the validity of the existing safety analysis for fuel cycle changes. The TPC's reload safety evaluation methodology for PWRs is based on 'Core Design and Safety Analysis Package' developed by the TPC and the Institute of Nuclear Energy Research (INER), and is an important portion of the 'Taipower's Reload Design and Transient Analysis Methodologies for Light Water Reactors'. The Core Management System (CMS) developed by Studsvik of America, the one-dimensional code AXINER developed by TPC, National Tsinghua University and INER, and a modified version of the well-known subchannel core thermal-hydraulic code COBRAIIIC are the major computer codes utilized. Each of the computer models is extensively validated by comparing with measured data and/or vendor's calculational results. Moreover, parallel calculations have been performed for two Maanshan reload cycles to validate the RSE methods. The TPC's in-house RSE tools have been applied to resolve many important plant operational issues and plant improvements, as well as to verify the vendor's fuel and core design data. (author)

High pressure water jet cutting and stripping

Science.gov (United States)

Hoppe, David T.; Babai, Majid K.

1991-01-01

High pressure water cutting techniques have a wide range of applications to the American space effort. Hydroblasting techniques are commonly used during the refurbishment of the reusable solid rocket motors. The process can be controlled to strip a thermal protective ablator without incurring any damage to the painted surface underneath by using a variation of possible parameters. Hydroblasting is a technique which is easily automated. Automation removes personnel from the hostile environment of the high pressure water. Computer controlled robots can perform the same task in a fraction of the time that would be required by manual operation.

Decontamination and recycle of zirconium pressure tubes from Pressurized Heavy Water Reactor

International Nuclear Information System (INIS)

Gantayet, L.M.; Verma, R.; Remya Devi, P.S.; Banerjee, S.; Kotak, V.; Raha, A.; Sandeep, K.C.; Joshi, Shreeram W.; Lali, A.M.

2009-01-01

An ion exchange process has been developed for decontamination of zirconium pressure tubes from Pressurized Heavy Water Reactor and recycling of neutronically improved zirconium. Distribution coefficient, equilibrium isotherm, kinetic and breakthrough data were used to develop the separation process. Effect of gamma radiation on indigenous resins was also studied to assess their suitability in high radiation field. (author)

Neurocontrol of Pressurized Water Reactors in Load-Follow Operations

International Nuclear Information System (INIS)

Lin Chaung; Shen Chihming

2000-01-01

The neurocontrol technique was applied to control a pressurized water reactor (PWR) in load-follow operations. Generalized learning or direct inverse control architecture was adopted in which the neural network was trained off-line to learn the inverse model of the PWR. Two neural network controllers were designed: One provided control rod position, which controlled the axial power distribution, and the other provided the change in boron concentration, which adjusted core total power. An additional feedback controller was designed so that power tracking capability was improved. The time duration between control actions was 15 min; thus, the xenon effect is limited and can be neglected. Therefore, the xenon concentration was not considered as a controller input variable, which simplified controller design. Center target strategy and minimum boron strategy were used to operate the reactor, and the simulation results demonstrated the effectiveness and performance of the proposed controller

Structure and dynamics of water confined in a graphene nanochannel under gigapascal high pressure: dependence of friction on pressure and confinement.

Science.gov (United States)

Yang, Lei; Guo, Yanjie; Diao, Dongfeng

2017-05-31

Recently, water flow confined in nanochannels has become an interesting topic due to its unique properties and potential applications in nanofluidic devices. The trapped water is predicted to experience high pressure in the gigapascal regime. Theoretical and experimental studies have reported various novel structures of the confined water under high pressure. However, the role of this high pressure on the dynamic properties of water has not been elucidated to date. In the present study, the structure evolution and interfacial friction behavior of water constrained in a graphene nanochannel were investigated via molecular dynamics simulations. Transitions of the confined water to different ice phases at room temperature were observed in the presence of lateral pressure at the gigapascal level. The friction coefficient at the water/graphene interface was found to be dependent on the lateral pressure and nanochannel height. Further theoretical analyses indicate that the pressure dependence of friction is related to the pressure-induced change in the structure of water and the confinement dependence results from the variation in the water/graphene interaction energy barrier. These findings provide a basic understanding of the dynamics of the nanoconfined water, which is crucial in both fundamental and applied science.

A Soviet view

International Nuclear Information System (INIS)

Tikhonov, S.Y.

1992-01-01

During the past several years, the international situation has changed greatly. Efforts to maintain strategic stability have replaced the desire for strategic superiority. Equally important, new thinking in the Soviet Union has greatly accelerated the political warming between the superpowers. As a result of thee developments, the Soviet Union and the United States have come to the conclusion that a nuclear war cannot be won and should never be fought. These events have drastically reduced the probability of the deliberate use of nuclear or conventional weapons. However, the risk of a military crisis and its consequences still exist. Indeed, the risk of a nuclear exchange is still possible. What has changed, however, is that in the current international climate, a crisis or war may result unintentionally because of misperceptions, misunderstanding, accident, or technical fault. While the probability of this is admittedly small, it remains far greater than that of deliberate conflict. The purpose of this chapter, therefore, is twofold. First, it identifies potential sources of unintended crises and conflicts and recommends appropriate confidence-building measures. Second, it addresses CBMs and their potential roles in nuclear crisis de-escalation

Detection and characterization of flaws in segments of light water reactor pressure vessels

International Nuclear Information System (INIS)

Cook, K.V.; Cunningham, R.A. Jr.; McClung, R.W.

1988-01-01

Studies have been conducted to determine flaw density in segments cut from light water reactor )LWR) pressure vessels as part of the Oak Ridge National Laboratory's Heavy-Section Steel Technology (H SST) Program. Segments from the Hope Creek Unit 2 vessel and the Pilgrim Unit 2 Vessel were purchased from salvage dealers. Hope Creek was a boiling water reactor (BWR) design and Pilgrim was a pressurized water reactor (PWR) design. Neither were ever placed in service. Objectives were to evaluate these LWR segments for flaws with ultrasonic and liquid penetrant techniques. Both objectives were successfully completed. One significant indication was detected in a Hope Creek seam weld by ultrasonic techniques and characterized by further analyses terminating with destructive correlation. This indication [with a through-wall dimension of ∼6 mm (∼0.24 in.)] was detected in only 3 m (10 ft) of weldment and offers extremely limited data when compared to the extent of welding even in a single pressure vessel. However, the detection and confirmation of the flaw in the arbitrarily selected sections implies the Marshall report estimates (and others) are nonconservative for such small flaws. No significant indications were detected in the Pilgrim material by ultrasonic techniques. Unfortunately, the Pilgrim segments contained relatively little weldment; thus, we limited our ultrasonic examinations to the cladding and subcladding regions. Fluorescent liquid penetrant inspection of the cladding surfaces for both LWR segments detected no significant indications [i.e., for a total of approximately 6.8 m 2 (72 ft 2 ) of cladding surface]. (author)

Experimental investigation of iodine removal and containment depressurization in containment spray system test facility of 700 MWe Indian pressurized heavy water reactors

Energy Technology Data Exchange (ETDEWEB)

Jain, Manish [Department of Mechanical Engineering, I.I.T., Bombay, Powai, Mumbai (India); Kandar, T.K.; Vhora, S.F.; Mohan, Nalini [Directorate of Technology Development, Nuclear Power Corporation of India Limited, Mumbai (India); Iyer, K.N. [Department of Mechanical Engineering, I.I.T., Bombay, Powai, Mumbai (India); Prabhu, S.V., E-mail: svprabhu@iitb.ac.in [Department of Mechanical Engineering, I.I.T., Bombay, Powai, Mumbai (India)

2017-05-15

Highlights: • Depressurization rate in a scaled down vessel filled with air and steam is studied. • Iodine removal rate in a scaled down vessel filled with steam/air is investigated. • Effect of SMD and vessel pressure on depressurization rate is studied. • Depressurization rate decreases with the increase in the droplet size (590 μm – 1 mm) • Decrease in pressure and iodine concentration with time follow exponential trend. - Abstract: As an additional safety measure in the new 700 MWe Indian pressurized heavy water reactors, the first of a kind system called containment Spray System is introduced. The system is designed to cater/mitigate the conditions after design basis accidents i.e., loss of coolant accident and main steam line break. As a contribution to the safety analysis of condition following loss-of-coolant accidents, experiments are carried out to establish the performance of the system. The loss of coolant is simulated by injecting saturated steam and iodine vapors into the containment vessel in which air is enclosed at atmospheric and room temperature, and then the steam-air mixture is cooled by sprays of water. The effect of water spray on the containment vessel pressure and the iodine scrubbing in a scaled down facility is investigated for the containment spray system of Indian pressurized heavy water reactors. The experiments are carried out in the scaled down vessel of the diameter of 2.0 m and height of 3.5 m respectively. Experiments are conducted with water at room temperature as the spray medium. Two different initial vessel pressure i.e. 0.7 bar and 1.0 bar are chosen for the studies as they are nearing the loss of coolant accident & main steam line break pressures in Indian pressurized heavy water reactors. These pressures are chosen based on the containment resultant pressures after a design basis accident. The transient temperature and pressure distribution of the steam in the vessel are measured during the depressurization

Innovations in prestressed concrete pressure vessel design

International Nuclear Information System (INIS)

Chow, P.Y.; Ngo, D.; Lin, T.Y.

1979-01-01

The study explored a new approach to the design of a high-pressure PCPV that accepts tension and tension cracks in the outer region of the PCPV. It examined the possibility of incorporating artificially-introduced preformed separations that pre-determined crack locations in the design as a method of controlling high tensile stresses generated by internal temperature and pressure. The results showed that the PCPV so designed was, in the extreme case of the DSV, approximately 70% cheaper than the 18 steel vessels of equivalent capacity it replaces. (orig.)

Pressure surge free fire water systems increase safety on offshore oil- and gas drilling platforms

International Nuclear Information System (INIS)

Carlsen, Randi

2001-01-01

The article describes a new fire water system for use on the oil- and gas drilling platforms that is characterized by improved start-up time and reduced energy consumption. Deluge valves are commonly used in fast large-flow fire water systems all over the world. During the test of a new fire water system on a platform a few years ago, a pipe near the living quarter suddenly ruptured due to an unexpected pressure surge thought to be impossible. It was caused by a weakness of the deluge valve. A better valve was needed and the 'UniqValve' was designed and manufactured. The UniqValve operates in cooperation with the fire pumps during start-up as it 'reads' the pressure variations of the water flow and corrects the water flow to the fire areas in less than a tenth of a second. The valve is now integrated in a modular system. The fire water unit is mounted in a container, which reduces cost and simplifies the placement of the fire water installation

An Optimal Design Model for New Water Distribution Networks in ...

African Journals Online (AJOL)

The mathematical formulation is a Linear Programming Problem (LPP) which involves the design of a new network of water distribution considering the cost in the form of unit price of pipes, the hydraulic gradient and the loss of pressure. The objective function minimizes the cost of the network which is computed as the sum ...

Evolution of environmental protection strategies in the Soviet Union

International Nuclear Information System (INIS)

Lesperance, A.M.

1992-05-01

In performing this work, interviews were conducted with members of the Supreme Soviet Committee for Rational Use of Natural Resources, Moscow, City Council, and St. Petersburg City Council. These officials provided their views on the current status of environmental protection in the former Soviet Union. Literature published in English, although limited, supplemented these discussions. In addition, a literature search was conducted of recent articles about this topic. Although the research for this paper was conducted before and during the August 1991 coup attempt in the Soviet Union, and after the formation of the Commonwealth of Independent States (CIS), many of the observations expressed in this report may be relevant to the new states. This report provides to historical perspective on the barriers encountered while attempting to develop environmental policy in the former Soviet Union and establishes a context for problems facing the new states in developing their environmental policies. Organization changes that have occurred in environmental protection since the August coup are included to the extent they are known

Chernobyl - a Canadian technical perspective

International Nuclear Information System (INIS)

Howieson, J.Q.; Snell, V.G.

1987-01-01

In this report we present the design review done to date in Canada by AECL. From the Canadian point of view it covers: 1) relevant information on the Chernobyl design and the accident, both as presented by the Soviets at the Post-Accident Review Meeting (PARM) held in Vienna from August 25-29, 1986, and as deduced from publicly available Soviet documentation; and 2) details of AECL's technical review of the CANDU PHWR (Pressurized Heavy Water Reactor) against the background of the Chernobyl accident, and implications of the Chernobyl accident. Reviews of operational aspects are underway by the Canadian electrical utilities and a review by the Canadian regulatory agency (the Atomic Energy Control Board) is near completion

Cavitation nuclei in water exposed to transient pressures

DEFF Research Database (Denmark)

Andersen, Anders Peter; Mørch, Knud Aage

2015-01-01

A model of skin-stabilized interfacial cavitation nuclei and their response to tensile and compressive stressing is presented. The model is evaluated in relation to experimental tensile strength results for water at rest at the bottom of an open water-filled container at atmospheric pressure...... and room temperature. These results are obtained by recording the initial growth of cavities generated by a short tensile pulse applied to the bottom of the container. It is found that the cavitation nuclei shift their tensile strength depending on their pressure history. Static pressurization...... for an extended period of time prior to testing is known to increase the tensile strength of water, but little information is available on how it is affected by compression pulses of short duration. This is addressed by imposing compression pulses of approximately 1 ms duration and a peak intensity of a few bar...

The Soviet collapse: Contradictions and neo-modernisation

Directory of Open Access Journals (Sweden)

Richard Sakwa

2013-01-01

Full Text Available Over two decades have passed since the dissolution of the communist system and the disintegration of the Soviet Union in 1991 yet there is still no consensus over the causes and consequences of these epochal (and distinct events. As for the causes, it is easy to assume that the fall was ‘over-determined’, with an endless array of factors. It behoves the scholar to try to establish a hierarchy of causality, which is itself a methodological exercise in heuristics. However, the arbitrary prioritisation of one factor over another is equally a hermeneutic trap that needs to be avoided. Following an examination of the various ‘why’ factors, we focus on ‘what’ exactly happened at the end of the Soviet period. We examine the issue through the prism of reformulated theories of modernisation. The Soviet system was a sui generis approach to modernisation, but the great paradox was that the system did not apply this ideology to itself. By attempting to stand outside the processes which it unleashed, both society and system entered a cycle of stagnation. The idea of neo-modernisation, above all the idea that societies are challenged to come to terms with the ‘civilisation of modernity’, each in their own way, provides a key to developments. In the end the Soviet approach to this challenge failed, and the reasons for this need to be examined, but the challenge overall remains for post-communist Russia.

Water cycles in closed ecological systems: effects of atmospheric pressure.

Science.gov (United States)

Rygalov, Vadim Y; Fowler, Philip A; Metz, Joannah M; Wheeler, Raymond M; Bucklin, Ray A

2002-01-01

In bioregenerative life support systems that use plants to generate food and oxygen, the largest mass flux between the plants and their surrounding environment will be water. This water cycle is a consequence of the continuous change of state (evaporation-condensation) from liquid to gas through the process of transpiration and the need to transfer heat (cool) and dehumidify the plant growth chamber. Evapotranspiration rates for full plant canopies can range from ~1 to 10 L m-2 d-1 (~1 to 10 mm m-2 d-1), with the rates depending primarily on the vapor pressure deficit (VPD) between the leaves and the air inside the plant growth chamber. VPD in turn is dependent on the air temperature, leaf temperature, and current value of relative humidity (RH). Concepts for developing closed plant growth systems, such as greenhouses for Mars, have been discussed for many years and the feasibility of such systems will depend on the overall system costs and reliability. One approach for reducing system costs would be to reduce the operating pressure within the greenhouse to reduce structural mass and gas leakage. But managing plant growth environments at low pressures (e.g., controlling humidity and heat exchange) may be difficult, and the effects of low-pressure environments on plant growth and system water cycling need further study. We present experimental evidence to show that water saturation pressures in air under isothermal conditions are only slightly affected by total pressure, but the overall water flux from evaporating surfaces can increase as pressure decreases. Mathematical models describing these observations are presented, along with discussion of the importance for considering "water cycles" in closed bioregenerative life support systems.

Water cycles in closed ecological systems: effects of atmospheric pressure

Science.gov (United States)

Rygalov, Vadim Y.; Fowler, Philip A.; Metz, Joannah M.; Wheeler, Raymond M.; Bucklin, Ray A.; Sager, J. C. (Principal Investigator)

2002-01-01

In bioregenerative life support systems that use plants to generate food and oxygen, the largest mass flux between the plants and their surrounding environment will be water. This water cycle is a consequence of the continuous change of state (evaporation-condensation) from liquid to gas through the process of transpiration and the need to transfer heat (cool) and dehumidify the plant growth chamber. Evapotranspiration rates for full plant canopies can range from 1 to 10 L m-2 d-1 (1 to 10 mm m-2 d-1), with the rates depending primarily on the vapor pressure deficit (VPD) between the leaves and the air inside the plant growth chamber. VPD in turn is dependent on the air temperature, leaf temperature, and current value of relative humidity (RH). Concepts for developing closed plant growth systems, such as greenhouses for Mars, have been discussed for many years and the feasibility of such systems will depend on the overall system costs and reliability. One approach for reducing system costs would be to reduce the operating pressure within the greenhouse to reduce structural mass and gas leakage. But managing plant growth environments at low pressures (e.g., controlling humidity and heat exchange) may be difficult, and the effects of low-pressure environments on plant growth and system water cycling need further study. We present experimental evidence to show that water saturation pressures in air under isothermal conditions are only slightly affected by total pressure, but the overall water flux from evaporating surfaces can increase as pressure decreases. Mathematical models describing these observations are presented, along with discussion of the importance for considering "water cycles" in closed bioregenerative life support systems.

Proposed Chevron Tengiz venture stalls amid Soviet political squabble

International Nuclear Information System (INIS)

Anon.

1991-01-01

This paper reports on the status of foreign investment in Soviet oil and gas joint ventures which has reached a critical juncture. Just as the U.S. is considering granting most favored nation trade status to the U.S.S.R., the joint venture petroleum deal seen as the litmus test for such deals-Chevron Corp.'s proposed addition of supergiant Tengiz oil field to its Caspian Sea joint venture-has stalled amid controversy. Unconfirmed reports from Soviet officials and other foreign joint venture participants in the U.S.S.R. have Chevron pulling out of the long negotiated, multibillion dollar project after the Soviets rejected the company's terms. Chevron, however, insists the project is still alive

Soviets may halt production drop with outside funds, technologies

International Nuclear Information System (INIS)

Riva, J.P. Jr.

1991-01-01

In a long history of Soviet oil production, a normal development progression has occurred in which several prolific oil provinces have been discovered in sequence, become dominant producers, and then declined. The present drop in Soviet oil output is partly the result of the natural decline of many of its large older fields, but also it is due to reduced capital investments in the domestic oil industry and to the reliance on outdated and inefficient exploration and development technology. This paper reports that financial and technical problems can be remedied by joint ventures with foreign oil companies. Despite these limitations, the Soviet Union has led the world in oil production ever since 1974, often by a considerable margin

'A people forgotten by history': Soviet Studies of the Kurds

NARCIS (Netherlands)

Leezenberg, M.

2015-01-01

The Russian/Soviet experience raises complex general questions concerning orientalism, conceptual hegemony, and the politics of (post-)colonial knowledge. Russia was not an empire in Said's sense, and drew much of its orientalist categories from non-imperialist German sources; the Soviet Union was

Station black out concurrent with PORV failure using a Generic Pressurized Water Reactor simulator

International Nuclear Information System (INIS)

Zubair, Muhammad; Ababneh, Ahmad; Ishag, Ahmed

2017-01-01

Highlights: •SBO accident simulation by using a GPWR simulator. •Normal SBO, and SBO with additional failure of Pilot Operated Relief Valve. •The research results will provide help in future for better understanding of accidents in APR 1400 reactors. -- Abstract: Station Black Out (SBO) is an accident situation that refers to the total loss of offsite power, along with the unavailability of onsite power, which results from the failure of all Diesel Generators (DG). Probabilistic Safety Assessment (PSA) spans a number of methods that include modeling of event-trees and simulation of accidents scenarios, aimed to quantify risk and ensure safety in nuclear power plants. PSA also deals with prediction of future accidents and calculation of failure probabilities that has been done in this study. A SBO accident was simulated using a Generic Pressurized Water Reactor (GPWR) simulator from KEYMASTER™. The accident scenario consists of two stages; the first stage belongs to normal SBO, in second stage SBO accident with additional failure of Pilot Operated Relief Valve (PORV) opens and it stuck open has been considered for the pressurizer. A comparison of the two stages was made by plotting variables on the same graph. The research has been carried out to analyze the hot and cold leg temperatures, Steam Generator (SG) pressure, SG Narrow Range (NR) level, SG water-level-percentage (PCT), Pressurizer pressure, Fuel Temperature, and containment pressure. Simulation results suggest that failure in closing PORV has negligible impact on hot and cold leg temperatures, results in an overall less pressure in SGs, but higher pressure in the pressurizer. Additionally, containment pressure did not exceed the maximum approved pressure of 8.7 kg/cm 2 , but was approaching the Advanced Pressurized Water Reactor’s (APR-1400) design pressure of 4.218 kg/cm 2 . Finally, nuclear fuel temperature exceeded Probabilistic Risk Assessment (PRA) limit of 726.7 °C for both scenarios. The

Analysis of the 1957-1958 Soviet nuclear accident

International Nuclear Information System (INIS)

Trabalka, J.R.; Eyman, L.D.; Auerbach, S.I.

1980-01-01

The presence of an extensive environmental contamination zone in Chelibinsk Province of the Soviet Union, associated with an accident in the winter of 1957 to 1958 involving the atmospheric release of fission wastes, appears to have been confirmed, primarily by an analysis of the Soviet radioecology literature. The contamination zone is estimated to contain 10(5) to 10(6) curies of strontium-90. A plausible explanation for the incident is the use of now-obsolete techniques for waste storage and cesium-137 isotope separation. Radioactive contamination appears to have resulted in resettlement of the human population from a significant area (100 to 1000 square kilometers). It therefore seems imperative to obtain a complete explanation of the cause (or causes) and consequences of the accident; Soviet experience gained in the application of corrective measures would be invaluable to the world nuclear community

JPRS Report, Soviet Union, Military History Journal, No. 11, November 1987

National Research Council Canada - National Science Library

1988-01-01

.... The articles are By the Course Indicated by Lenin, Outstanding Victory of Soviet Army, Strategic Soviet Troop Regroupings in Preparation of 1942-1943 Winter Campaign, Combat of 87th Rifle Division...

Is the shaman indeed risen in post-Soviet Siberia?

Directory of Open Access Journals (Sweden)

Olle Sundström

2012-01-01

Full Text Available In his exhaustive study of ‘shamanism’ among the Altaic peoples in Southern Siberia, the renowned Soviet ethnographer Leonid P. Potapov contends that ‘under the present conditions there are no remnants or survivals of Shamanism as such left in Altai’. What remains are legends and reminiscences, but these can no longer be told by people with personal experiences of Altaic ‘shamans’ and their rituals. According to Potapov, modern socialist culture has changed the minds of the Altaic peoples to the degree that they are now a materialistically thinking people, and ‘shamanism’ has completely disappeared. In addition, he contends that there are no prospects of its return after the deathblow dealt by Soviet anti-religious repression in the 1930s ‘shamanic’ rituals were forbidden and ritual paraphernalia such as drums and costumes were expropriated by the authorities. Considering that Potapov in his study follows Altaic ‘shamanism’ through 1500 years, depicting it as a ‘religion’ and ‘theology’ which stayed more or less intact over the centuries, his statement seems more like a pious hope based on the Soviet vision of a society liberated from superstition, religion, and spiritual exploitation. Potapov himself delineates Altaic ‘shamanism’s’ development from a ‘state religion’to a ‘folk religion’. From this perspective it might seem remarkable that ‘shamanism’ should not have survived 70 years of atheist repression, missionary work and the Soviet transformation of society. Already by the time Potapov’s book was published, during the very last months of the existence of the Soviet Union, there had, in fact, appeared a number of persons claiming to be ‘shamans’, with an ancestry dating from the time of ‘shamans’ of the first half of the twentieth century. These individuals were also part of organisations and movements promoting the revival of ‘shamanism’ in the autonomous Altai Republic. In

Measurement of pressure distributions and velocity fields of water jet intake flow

International Nuclear Information System (INIS)

Jeong, Eun Ho; Yoon, Sang Youl; Kwon, Seong Hoon; Chun, Ho Hwan; Kim, Mun Chan; Kim, Kyung Chun

2002-01-01

Waterjet propulsion system can avoid cavitation problem which is being arised conventional propeller propulsion system. The main issue of designing waterjet system is the boundary layer separation at ramp and lib of water inlet. The flow characteristics are highly depended on Jet to Velocity Ratio(JVR) as well as the intake geometry. The present study is conducted in a wind tunnel to provide accurate pressure destribution at the inlet wall and velocity field of the inlet and exit planes. Particle image velocimetry technique is used to obtain detail velocity fields. Pressure distributions and velocity field are discussed with accelerating and deaccelerating flow zones and the effect of JVR

Design of condenser for 500 MWe pressurised heavy water reactors (PHWRs) - a case study

International Nuclear Information System (INIS)

Agarwal, N.K.; Subbarao, A.; Chaudhary, K.

1996-01-01

Condenser forms the major heat sink in the power plants. In recent years, power plant availability and performance have become great concern to the industry. The detailed design of the condenser and its associated cooling water (CW) system require careful optimisation of parameters which include material selection, cooling water flow rate, condenser surface areas, turbine exhaust pressures etc. This is required to produce a design offering maximum efficiency and reliability and minimum maintenance. The various parameters involved in condenser design are discussed. 5 refs., 1 fig

PROBLEMS OF INTEGRATION AT THE FORMER SOVIET UNION

Directory of Open Access Journals (Sweden)

Еlena А. Hudorenko

2015-01-01

Full Text Available The article provides analysis of historical retrospective of integrationprocesses in former Soviet Union, ways and opportunities for furtherdevelopment thereof.The authors make a study of the problems of development and functioningof Eurasian cooperation, the effectiveness of interaction with certain states,analyze the reasons of failures, emphasize the achievements results ofcooperation, point out the opportunities for integration processes betweendifferent CIS and provide practical recommendations for effectiveness thereof in former Soviet Union.

Soviet Policy Toward Western Europe Objectives, Instruments, Results.

Science.gov (United States)

1986-02-01

Hellenic Socialist Move- ment ( PASOK ) and the development of ties between its left wing and the Greek Communist party (KKE). Before PASOK won an...absolute majority in the June 1985 elections, the Soviets may have hoped for the formation of a PASOK -KKE coalition or, more likely, an arrange- ment...whereby a minority PASOK government would remain in power with tacit Communist support. Although these expectations were not fulfilled, the Soviets expect

Pressurized water reactor inspection procedures

International Nuclear Information System (INIS)

Heinrich, D.; Mueller, G.; Otte, H.J.; Roth, W.

1998-01-01

Inspections of the reactor pressure vessels of pressurized water reactors (PWR) so far used to be carried out with different central mast manipulators. For technical reasons, parallel inspections of two manipulators alongside work on the refueling cavity, so as to reduce the time spent on the critical path in a revision outage, are not possible. Efforts made to minimize the inspection time required with one manipulator have been successful, but their effects are limited. Major reductions in inspection time can be achieved only if inspections are run with two manipulators in parallel. The decentralized manipulator built by GEC Alsthom Energie and so far emmployed in boiling water reactors in the USA, Spain, Switzerland and Japan allows two systems to be used in parallel, thus reducing the time required for standard inspection of a pressure vessel from some six days to three days. These savings of approximately three days are made possible without any compromises in terms of positioning by rail-bound systems. During inspection, the reactor refueling cavity is available for other revision work without any restrictions. The manipulator can be used equally well for inspecting standard PWR, PWR with a thermal shield, for inspecting the land between in-core instrumentation nozzles, BWR with and without jet pumps (complementary inspection), and for inspecting core support shrouds. (orig.) [de

Nuclear power in eastern and central Europe. Background paper

International Nuclear Information System (INIS)

Myers, L.C.

1993-11-01

The breakup of the former Soviet Union and other political changes in eastern and central Europe have opened up the area to closer scrutiny than was previously possible. Because of the accident at Chernobyl, nuclear power is one of the subjects that western nations have had a great deal of interest in exploring. The former Soviet Union designed and/or helped build more than 60 civilian reactors in the region. Most of these reactors follow one of two distinctly different designs: the VVER, or pressurized water reactor series; and the RBMK, which is a graphite-moderated, multi-channel reactor (the so-called Chernobyl type). In addition, there are two fast-breeder reactors and four graphite-moderated boiling water reactors for combined heat and power in operation in Russia. These last two designs are not widely distributed and so are not discussed in detail in this report. As noted above, the safety of Soviet-designed reactors has been of great concern around the world since the catastrophic events at Chernobyl in 1986. This paper will briefly describe the technology involved. It will also examine the main safety concerns, both technical and organizational, associated with each reactor type. In addition, the paper will review the nuclear power programs in the new countries emerging from the former Soviet Union and its satellites and discuss the international efforts underway to address the most pressing problems. (author). 1 tab

Nuclear power in eastern and central Europe. Background paper

Energy Technology Data Exchange (ETDEWEB)

Myers, L C [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

1993-11-01

The breakup of the former Soviet Union and other political changes in eastern and central Europe have opened up the area to closer scrutiny than was previously possible. Because of the accident at Chernobyl, nuclear power is one of the subjects that western nations have had a great deal of interest in exploring. The former Soviet Union designed and/or helped build more than 60 civilian reactors in the region. Most of these reactors follow one of two distinctly different designs: the VVER, or pressurized water reactor series; and the RBMK, which is a graphite-moderated, multi-channel reactor (the so-called Chernobyl type). In addition, there are two fast-breeder reactors and four graphite-moderated boiling water reactors for combined heat and power in operation in Russia. These last two designs are not widely distributed and so are not discussed in detail in this report. As noted above, the safety of Soviet-designed reactors has been of great concern around the world since the catastrophic events at Chernobyl in 1986. This paper will briefly describe the technology involved. It will also examine the main safety concerns, both technical and organizational, associated with each reactor type. In addition, the paper will review the nuclear power programs in the new countries emerging from the former Soviet Union and its satellites and discuss the international efforts underway to address the most pressing problems. (author). 1 tab.

Vospitanie and Regime Change: Teacher-Education Textbooks in Soviet and Post-Soviet Ukraine

Science.gov (United States)

Bogachenko, Tatiana; Perry, Laura

2015-01-01

This article examines the pedagogical dimension of vospitanie, or character formation, in communist and post-communist education. It explores how vospitanie is conceptualized in two teacher-education textbooks--one from each period--in Ukraine, a post-Soviet country. Comparative analysis shows how conceptualizations of vospitanie have evolved over…

Status of advanced small pressurized water reactors

International Nuclear Information System (INIS)

Chen Peipei; Zhou Yun

2012-01-01

In order to expand the nuclear power in energy and desalination, increase competitiveness in global nuclear power market, many developed countries with strong nuclear energy technology have realized the importance of Small Modular Reactor (SMR) and initiated heavy R and D programs in SMR. The Advanced Small Pressurized Water Reactor (ASPWR) is characterized by great advantages in safety and economy and can be used in remote power grid and replace mid/small size fossil plant economically. This paper reviews the history and current status of SMR and ASPWR, and also discusses the design concept, safety features and other advantages of ASPWR. The purpose of this paper is to provide an overall review of ASPWR technology in western countries, and to promote the R and D in ASPWR in China. (authors)

Soviet Union, Military Affairs.

Science.gov (United States)

1987-06-05

supremacy in the world. Like the foreign policies of the USSR and the USA , their military doctrines reveal the objectives they pursue: the Soviet... Gastronom or a Detskiy Mir. In- stallation of the equipment was delayed a long time as a result. The district finance service therefore did not consider

President Ford and both the Soviet and American ASTP crews

Science.gov (United States)

1974-01-01

President Gerald R. Ford removes the Soviet Soyuz spacecraft model from a model set depicting the 1975 Apollo Soyuz Test Project (ASTP), an Earth orbital docking and rendezvous mission with crewmen from the U.S. and USSR. From left to right, Vladamir A. Shatalov, Chief, Cosmonaut training; Valeriy N. Kubasov, ASTP Soviet engineer; Aleksey A. Leonov, ASTP Soviet crew commander; Thomas P. Stafford, commander of the American crew; Donald K. Slayton, American docking module pilot; Vance D. Brand, command module pilot for the American crew. Dr. George M Low, Deputy Administrator for NASA is partially obscured behind President Ford.

Variation of Pore Water Pressure in Tailing Sand under Dynamic Loading

Directory of Open Access Journals (Sweden)

Jia-xu Jin

2018-01-01

Full Text Available Intense vibration affects the pore water pressure in a tailing dam, with the tendency to induce dam liquefaction. In this study, experiments were performed wherein model tailing dams were completely liquefied by sustained horizontal dynamic loading to determine the effects of the vibration frequency, vibration amplitude, and tailing density on the pore water pressure. The results revealed four stages in the increase of the tailing pore water pressure under dynamic loading, namely, a slow increase, a rapid increase, inducement of structural failure, and inducement of complete liquefaction. A lower frequency and smaller amplitude of the vibration were found to increase the time required to achieve a given pore water pressure in dense tailings. Under the effect of these three factors—vibration frequency and amplitude and tailing density—the tailing liquefaction time varied nonlinearly with the height from the base of the tailing dam, with an initial decrease followed by an increase. The pore pressure that induced structural failure also gradually decreased with increasing height. The increase in the tailing pore pressure could be described by an S-shaped model. A complementary multivariate nonlinear equation was also derived for predicting the tailing pore water pressure under dynamic loading.

Stability analysis of supercritical-pressure light water-cooled reactor in constant pressure operation

International Nuclear Information System (INIS)

Suhwan, JI; Shirahama, H.; Koshizuka, S.; Oka, Y.

2001-01-01

The purpose of this study is to evaluate the thermal-hydraulic and the thermal-nuclear coupled stabilities of a supercritical pressure light water-cooled reactor. A stability analysis code at supercritical pressure is developed. Using this code, stabilities of full and partial-power reactor operating at supercritical pressure are investigated by the frequency-domain analysis. Two types of SCRs are analyzed; a supercritical light water reactor (SCLWR) and a supercritical water-cooled fast reactor (SCFR). The same stability criteria as Boiling Water Reactor are applied. The thermal-hydraulic stability of SCLWR and SCFR satisfies the criteria with a reasonable orifice loss coefficient. The decay ratio of the thermal-nuclear coupled stability in SCFR is almost zero because of a small coolant density coefficient of the fast reactor. The evaluated decay ratio of the thermal-nuclear coupled stability is 3,41 ∼ 10 -V at 100% power in SCFR and 0,028 at 100% power in SCLWR. The sensitivity is investigated. It is found that the thermal-hydraulic stability is sensitive to the mass flow rate strongly and the thermal-nuclear coupled stability to the coolant density coefficient. The bottom power peak distribution makes the thermal-nuclear stability worse and the thermal-nuclear stability better. (author)

Nonlinear vibration of a hemispherical dome under external water pressure

International Nuclear Information System (INIS)

Ross, C T F; McLennan, A; Little, A P F

2011-01-01

The aim of this study was to analyse the behaviour of a hemi-spherical dome when vibrated under external water pressure, using the commercial computer package ANSYS 11.0. In order to achieve this aim, the dome was modelled and vibrated in air and then in water, before finally being vibrated under external water pressure. The results collected during each of the analyses were compared to the previous studies, and this demonstrated that ANSYS was a suitable program and produced accurate results for this type of analysis, together with excellent graphical displays. The analysis under external water pressure, clearly demonstrated that as external water pressure was increased, the resonant frequencies decreased and a type of dynamic buckling became likely; because the static buckling eigenmode was similar to the vibration eigenmode. ANSYS compared favourably with the in-house software, but had the advantage that it produced graphical displays. This also led to the identification of previously undetected meridional modes of vibration; which were not detected with the in-house software.

Nonlinear vibration of a hemispherical dome under external water pressure

Science.gov (United States)

Ross, C. T. F.; McLennan, A.; Little, A. P. F.

2011-07-01

The aim of this study was to analyse the behaviour of a hemi-spherical dome when vibrated under external water pressure, using the commercial computer package ANSYS 11.0. In order to achieve this aim, the dome was modelled and vibrated in air and then in water, before finally being vibrated under external water pressure. The results collected during each of the analyses were compared to the previous studies, and this demonstrated that ANSYS was a suitable program and produced accurate results for this type of analysis, together with excellent graphical displays. The analysis under external water pressure, clearly demonstrated that as external water pressure was increased, the resonant frequencies decreased and a type of dynamic buckling became likely; because the static buckling eigenmode was similar to the vibration eigenmode. ANSYS compared favourably with the in-house software, but had the advantage that it produced graphical displays. This also led to the identification of previously undetected meridional modes of vibration; which were not detected with the in-house software.

Application of a neural network to control a pressurized water reactor

International Nuclear Information System (INIS)

Lin, C.; Ku, C.C.; Lee, C.S.

1993-01-01

A neural network has been trained to control a pressurized water reactor. The inputs of the training pattern are the plant signals, and the outputs are the control rod actions. The training patterns are some kind of lookup table of control action. The table is designed by the heuristic method, which is based on the designer's knowledge of the controlled system and the operation experience. This method has two advantages: The controller's performance does not depend on the mathematical model of the plant, and the controller could be a nonlinear one. The advantages of using neural networks to implement the controller are to save computing time and overcome partial hardware failure

Hollow Fiber Space Water Membrane Evaporator Flight Prototype Design and Testing

Science.gov (United States)

Bue, Grant C.; Makinen, Janice; Vogel, Mtthew; Honas, Matt; Dillon, Paul; Colunga, Aaron; Truong, Lily; Porwitz, Darwin; Tsioulos, Gus

2011-01-01

The spacesuit water membrane evaporator (SWME) is being developed to perform thermal control for advanced spacesuits and to take advantage of recent advances in micropore membrane technology. This results in a robust heat-rejection device that is potentially less sensitive to contamination than is the sublimator. The current design was based on a previous design that grouped the fiber layers into stacks, which were separated by small spaces and packaged into a cylindrical shape. This was developed into a full-scale prototype consisting of 14,300 tube bundled into 30 stacks, each of which is formed into a chevron shape and separated by spacers and organized into three sectors of 10 nested stacks. The new design replaced metal components with plastic ones, eliminated the spacers, and has a custom built flight like backpressure valve mounted on the side of the SWME housing to reduce backpressure when fully open. A number of tests were performed in order to improve the strength of the polyurethane header that holds the fibers in place while the system is pressurized. Vacuum chamber testing showed similar heat rejection as a function of inlet water temperature and water vapor backpressure was similar to the previous design. Other tests pushed the limits of tolerance to freezing and showed suitability to reject heat in a Mars pressure environment with and without a sweep gas. Tolerance to contamination by constituents expected to be found in potable water produced by distillation processes was tested in a conventional way by allowing constituents to accumulate in the coolant as evaporation occurs. For this purpose, the SWME cartridge has endured an equivalent of 30 EVAs exposure and demonstrated acceptable performance decline.

Nuclear power in the Soviet Bloc

International Nuclear Information System (INIS)

Davey, W.G.

1982-03-01

The growth of Soviet Bloc nuclear power generation to the end of the century is evaluated on the basis of policy statements of objectives, past and current nuclear power plant construction, and trends in the potential for future construction. Central to this study is a detailed examination of individual reactor construction and site development that provides specific performance data not given elsewhere. A major commitment to nuclear power is abundantly clear and an expansion of ten times in nuclear electric generation is estimated between 1980 and 2000. This rate of growth is likely to have significant impact upon the total energy economy of the Soviet Bloc including lessening demands for use of coal, oil, and gas for electricity generation

Nuclear power in the Soviet Bloc

Energy Technology Data Exchange (ETDEWEB)

Davey, W.G.

1982-03-01

The growth of Soviet Bloc nuclear power generation to the end of the century is evaluated on the basis of policy statements of objectives, past and current nuclear power plant construction, and trends in the potential for future construction. Central to this study is a detailed examination of individual reactor construction and site development that provides specific performance data not given elsewhere. A major commitment to nuclear power is abundantly clear and an expansion of ten times in nuclear electric generation is estimated between 1980 and 2000. This rate of growth is likely to have significant impact upon the total energy economy of the Soviet Bloc including lessening demands for use of coal, oil, and gas for electricity generation.

The image of women in Soviet Manifesto

Directory of Open Access Journals (Sweden)

Mirko Orabona

2016-03-01

Full Text Available This article summarizes the condition of women within the Bolshevik regime, focusing on the use of posters. Visual propaganda was a means to easily reach wide strata of the population. The official Party ideology, expressed through visual propaganda, contributed to the definition of new social identities, as well as to the creation of new ways of thinking and acting in Soviet society. It had its own internal dynamics and operated as an independent force in a continually evolving society in which the field of discourse was radically changing. Posters aticipated developments in Soviet society and provided a model for people to follow; they were not limited to reflecting past or current events. The posters under consideretion pertain to the representation of women in their various occupations (e.g, workers, peasants or simply happily engaged in everyday life. The images prescribed, for example, which clothes to wear or how hair should be styled, and were without doubt powerful and pervasive; yet they were destined to meet an inevitable decline following Stalin's death, when the Soviet Union reprised its international relations.

Soviet theories of economic demography: a survey.

Science.gov (United States)

Gregory, P

1983-06-01

At this time Soviet demographic scientists maintain the position that population problems may in fact exist temporarily under socialism but that the planning principle will allow society to resolve population problems, through the use of the administrative, moral, and economic levers (subsidies, government policies, propaganda, education) emphasized by Urlanis (1974) and others. For planners to deal effectively with population management, the determinants of fertility and labor force participation must be established. The foundations of Soviet theories of human capital and fertility were laid by several writers. For the sake of simplicity, these are referred to as the Urlanis-Strumilin model, named after 2 pioneer researchers in Soviet demography and manpower economics. The formulations are based upon the writings of Strumlin (1964) and Urlanis (1974), supplemented by writings of numerous other Soviet researchers. Although their models avoid neoclassical terms such as marginal utility and income and price elasticities, they clearly employ these concepts. The Urlanis-Strumilin model, reduced to its basic elements, is a direct household utility maximizing model. The husband and wife, the household decision makers, must select optimal levels of child "quantity," child "quality," leisure, their own human capital (further education and training), and other goods. The Soviet theory recognizes that an increase in household income will increase relatively the demands for income elastic goods. The model postulates that the demand for child quality is inversely related to the price of children. The price of children is the opportunity cost of children, the major element of which is the income foregone by the mother in the course of childbearing and childrearing. The child quantity demand schedule has elastic and inelastic portions. The marginal utility of the 1st child is great. The marginal utilities of higher order children decline substantially. Families with at least 1