WorldWideScience

Sample records for ship nuclear machinery

  1. The development of natural circulation operation support program for ship nuclear power machinery

    International Nuclear Information System (INIS)

    Hao, Jianli; Chen, Wenzhen; Chen, Zhiyun

    2012-01-01

    Highlights: ► The natural circulation under various ocean and ship motion conditions is studied. ► A natural circulation operation support computer program (NCOSP) is developed with Simulink. ► The NCOSP program has the merit of easy input preparation, fast and accurate simulation. ► The NCOSP is suitable for the fast parameter simulation of ship nuclear power machinery. -- Abstract: The existing simulation program of ship nuclear power machinery (SNPM) cannot adequately deal with the natural circulation (NC) operation and the effects of various ocean conditions and ship motion. Aiming at the problem, the natural circulation operation support computer program for SNPM is developed, in which the momentum conservation equation of the primary loop, some heat transfer and flow resistance models and equations are modified for the various ocean conditions and ship motion. The additional pressure loss model and effective height model for the control volume in the gyration movement, simple harmonic rolling and pitching movements are also discussed in the paper. Furthermore, the transient response to load change under NC conditions is analyzed by the developed program. The results are compared with those predicted by the modified RELAP5/mod3.2 code. It is shown that the natural circulation operation support program (NCOSP) is simple in the input preparation, runs fast and has a satisfactory precision, and is therefore very suitable for the operating field support of SNPM under the conditions of NC.

  2. Theoretical research for natural circulation operational characteristic of ship nuclear machinery under ocean conditions

    Energy Technology Data Exchange (ETDEWEB)

    Yan Binghuo [Department of Nuclear Science and Engineering, Naval University of Engineering, Wuhan 430033 (China)], E-mail: yanbh1986@163.com; Yu Lei [Department of Nuclear Science and Engineering, Naval University of Engineering, Wuhan 430033 (China)], E-mail: yulei301@163.com

    2009-06-15

    Based on the two-phase drift flux model and the multi-pressure nodes matrix solving method, natural circulation thermal hydraulic analysis models for the Nuclear Machinery (NM) under ocean conditions are developed. The neutron physical activities and the responses of the reactivity control systems are described by the two-group, 3-dimensional space and time dependent neutron kinetics model. Reactivity feedback is calculated by coupling the neutron physics and thermal hydraulic codes, and is tested by comparison with experiments. Using the models developed, the natural circulation operating characteristics of NM in rolling and pitching motions and the transitions between forced circulation (FC) to natural circulation (NC) are analyzed. The results show that the influence of the rolling motion increases as the rolling amplitude is increased, and as the rolling period becomes shorter. The results also show that for this NM, with the same rolling period and rolling angle, the influence of pitching motion on natural circulation is greater than that of rolling motion. Furthermore, the oscillation period for pitching motion is the same as the pitching period, while the oscillation period for rolling is one half of the rolling period. In the ocean environment, excessive flow oscillation of the natural circulation may cause the control rods to respond so frequently that the NM would not be able to realize the transition from the FC to NC steadily. However, the influence of ocean environment on the transition from NC to FC is limited.

  3. 29 CFR 1915.164 - Ship's propulsion machinery.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 7 2010-07-01 2010-07-01 false Ship's propulsion machinery. 1915.164 Section 1915.164 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR (CONTINUED) OCCUPATIONAL SAFETY AND HEALTH STANDARDS FOR SHIPYARD EMPLOYMENT Ship's Machinery and Piping Systems § 1915.164 Ship's...

  4. Nuclear ship engineering simulator

    International Nuclear Information System (INIS)

    Itoh, Yasuyoshi; Kusunoki, Tsuyoshi; Hashidate, Koji

    1991-01-01

    The nuclear ship engineering simulator, which analyzes overall system response of nuclear ship numerically, is now being developed by JAERI as an advanced design tool with the latest computer technology in software and hardware. The development of the nuclear ship engineering simulator aims at grasping characteristics of a reactor plant under the situation generated by the combination of ocean, a ship hull and a reactor. The data from various tests with the nuclear ship 'MUTSU' will be used for this simulator to modulate and verify its functions of reproducing realistic response of nuclear ship, and then the simulator will be utilized for the research and development of advanced marine reactors. (author)

  5. Reactors. Nuclear propulsion ships

    International Nuclear Information System (INIS)

    Fribourg, Ch.

    2001-01-01

    This article has for object the development of nuclear-powered ships and the conception of the nuclear-powered ship. The technology of the naval propulsion P.W.R. type reactor is described in the article B.N.3 141 'Nuclear Boilers ships'. (N.C.)

  6. Nuclear merchant ship propulsion

    International Nuclear Information System (INIS)

    Schroeder, E.; Jager, W.; Schafstall, H.G.

    1977-01-01

    The operation of about 300 nuclear naval vessels has proven the feasibility of nuclear ship propulsion. Until now six non military ships have been built or are under construction. In the Soviet Union two nuclear icebreakers are in operation, and a third one is under construction. In the western world three prototype merchant ships have been built. Of these ships only the NS OTTO HAHN is in operation and provides valuable experience for future large scale use of nuclear merchant ship propulsion. In many countries studies and plans are made for future nuclear merchant ships. Types of vessels investigated are large containerships, tankers and specialized ships like icebreakers or ice-breaking ships. The future of nuclear merchant ship propulsion depends on three interrelated items: (1) nuclear ship technology; (2) economy of nuclear ship propulsion; (3) legal questions. Nuclear merchant ship technology is based until now on standard ship technology and light water reactor technology. Except for special questions due to the non-stationary type of the plant entirely new problems do not arise. This has been proven by the recent conceptual licensing procedure for a large nuclear containership in Germany. The economics of nuclear propulsion will be under discussion until they are proven by the operation of privately owned lead ships. Unsolved legal questions e.g. in connection with port entry permissions are at present another problem for nuclear shipping. Efforts are made to solve these questions on an international basis. The future development of nuclear energy electricity production in large land based plants will stimulate the employment of smaller units. Any future development of long distance sea transport will have to take this opportunity of a reliable and economic energy supply into account

  7. Safety of nuclear ships

    International Nuclear Information System (INIS)

    1978-01-01

    Interest in the utilization of nuclear steam supply systems for merchant ships and icebreakers has recently increased considerably due to the sharp rise in oil prices and the continuing trend towards larger and faster merchant ships. Canada, for example, is considering construction of an icebreaker in the near future. On the other hand, an accident which could result in serious damage to or the sinking of a nuclear ship is potentially far more dangerous to the general public than a similar accident with a conventional ship. Therefore, it was very important to evaluate in an international forum the safety of nuclear ships in the light of our contemporary safety philosophy, taking into account the results of cumulative operating experience with nuclear ships in operation. The philosophy and safety requirement for land-based nuclear installations were outlined because of many common features for both land-based nuclear installations and nuclear ships. Nevertheless, essential specific safety requirements for nuclear ships must always be considered, and the work on safety problems for nuclear ships sponsored by the NEA was regarded as an important step towards developing an international code of practice by IMCO on the safety of nuclear merchant ships. One session was devoted to the quantitative assessment of nuclear ship safety. The probability technique of an accident risk assessment for nuclear power plants is well known and widely used. Its modification, to make it applicable to nuclear propelled merchant ships, was discussed in some papers. Mathematical models for describing various postulated accidents with nuclear ships were developed and reported by several speakers. Several papers discussed a loss-of-coolant accident (LOCA) with nuclear steam supply systems of nuclear ships and engineering design features to prevent a radioactive effluence after LOCA. Other types of postulated accidents with reactors and systems in static and dynamic conditions were also

  8. Handbook of nuclear ships

    International Nuclear Information System (INIS)

    1981-03-01

    First, the government organs and other organizations related to nuclear ships and their tasks are described. The fundamental plan for the development of nuclear ships had been determined in July, 1963, and was revised three times thereafter. However in December, 1980, new determination to carry out the research works also was made. The course of the construction of the nuclear ship ''Mutsu'' from 1955 to 1980, the main particulars of the nuclear ship ''Mutsu'' and the drawing of the general arrangement are shown. The designated port for berthing the Mutsu was completed in 1972 in Ominato, Aomori Prefecture, but after the happening of radiation leak during the trial operation of the Mutsu in 1974, it was agreed to remove the port. The main works to be carried out at the port and the port facilities are explained. The progress of the examination of safety of the Mutsu and the result, the test of raising the power output carried out in 1974, and the course of selecting the port for making the repair works of the Mutsu are described. The law concerning Japan Nuclear Ship Research and Development Agency had been instituted in 1963, and was revised four times thereafter. The change of the budget for the tests and researches related to nuclear ships in Japan is shown. The state of development of nuclear ships in foreign countries, the international organs related to atomic energy, shipping, shipbuilding and energy, and chronological table are introduced. (Kako, I.)

  9. Nuclear ships and their safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1961-04-15

    Several aspects of nuclear ship propulsion, with special reference to nuclear safety, were discussed at an international symposium at Taormina, Italy, from 14-18 November 1960. Discussions on specific topics are conducted, grouped under the following headings: Economics and National Activities in Nuclear Ship Propulsion; International Problems and General Aspects of Safety for Nuclear Ships; Nuclear Ship Projects from the Angle of Safety; Ship Reactor Problems; Sea Motion and Hull Problems; Maintenance and Refuelling Problems; and Safety Aspects of Nuclear Ship Operation.

  10. Decommission of nuclear ship 'MUTSU'

    International Nuclear Information System (INIS)

    Tateyama, Takeshi

    1996-01-01

    The nuclear-powered ship 'MUTSU' was decommissioned by removing the reactor room in June 1995, which was hoisted and transported by a floating crane to a shore storage room at Sekinehama, Aomori Prefecture. This work was carried out in three stages: extraction of the spent fuel assemblies and neutron sources, dismantling of the machinery in the reactor auxiliary room, and separation and transportation of the reactor together with the secondary shielding structure and surrounding hull. IHI mainly conducted the third stage work. The separation work of the reactor room structure using a semisubmersible barge is outlined. Stress analysis and design of the reactor room for lifting work is also described. (author)

  11. Civilian nuclear ships

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1993-03-01

    This report contains a review of the information available on nuclear powered ships, built for civilian purposes. In the introduction a short discussion is given of the reasons for the limited use of nuclear ships for these purposes. In the second section a brief review is presented of data for the three experimental/merchant ships build by the United States, Germany and Japan, i.e. NS Savannah, NS Otto Hahn and NS Mutsu. In the third section the Soviet/Russian icebreaker NS Lenin is considered. Its design, operational experience and the introduction of a new nuclear propulsion plant is reviewed. In the fourth section the newer Soviet/Russian icebreakers with nuclear propulsion are considered. Finally design of the Soviet/Russian icebreaker transport/container ship NS Sevmorput is reviewed in the fifth section. The future Russian plans for nuclear vessels for the arctic waters are briefly discussed. (au)

  12. Nuclear ship accidents

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1993-05-01

    In this report available information on 28 nuclear ship accident and incidents is considered. Of these 5 deals with U.S. ships and 23 with USSR ships. The ships are in almost all cases nuclear submarines. Only events that involve the nuclear propulsion plants, radiation exposures, fires/explosions and sea water leaks into the submarines are considered. Comments are made on each of the events, and at the end of the report an attempt is made to point out the weaknesses of the submarine designs which have resulted in the accidents. It is emphasized that much of the available information is of a rather dubious nature. consequently some of the assessments made may not be correct. (au)

  13. Recent situations around nuclear ships

    International Nuclear Information System (INIS)

    Mizuno, Hiroshi

    1978-01-01

    The philosophy when the safety standard for nuclear ships is drawn up and the international rules specifically for nuclear ships are summarized. As for the safety standard for nuclear ships, the safety requirements for ordinary ships, for the ships transporting nuclear reactors, for ordinary nuclear reactors, and for the reactors moving around the seas must be included. As for the international rules for nuclear ships, there are chapter 8 ''Nuclear ships'' in the International Convention on the Safety of Life at Sea, 1960 and 1974, and Safety Consideration in the Use of Ports and Approaches by Nuclear Merchant Ships. Also there are national rules and standards in Japan and foreign countries. One of the means to explore the practicality of nuclear ships is the investigation of the economy. At this time, the social merits and demerits of nuclear ships must be compared with conventional ships by taking total expenses into account without omission. When oil is depleted, the age of nuclear ships will not necessarily begin, and the will be still some competitors. The investigations concerning the economy of nuclear ships have been carried out in various countries. The present state of the development of nuclear ships in Japan and foreign countries is explained. Many conferences and symposia have been held concerning nuclear ships, and those held recently are enumerated. The realization of nuclear ship age cannot be anticipated from existing papers and shipbuilding projects. (Kako, I.)

  14. Accidents in nuclear ships

    Energy Technology Data Exchange (ETDEWEB)

    Oelgaard, P L [Risoe National Lab., Roskilde (Denmark); [Technical Univ. of Denmark, Lyngby (Denmark)

    1996-12-01

    This report starts with a discussion of the types of nuclear vessels accidents, in particular accidents which involve the nuclear propulsion systems. Next available information on 61 reported nuclear ship events in considered. Of these 6 deals with U.S. ships, 54 with USSR ships and 1 with a French ship. The ships are in almost all cases nuclear submarines. Only events that involve the sinking of vessels, the nuclear propulsion plants, radiation exposures, fires/explosions, sea-water leaks into the submarines and sinking of vessels are considered. For each event a summary of available information is presented, and comments are added. In some cases the available information is not credible, and these events are neglected. This reduces the number of events to 5 U.S. events, 35 USSR/Russian events and 1 French event. A comparison is made between the reported Soviet accidents and information available on dumped and damaged Soviet naval reactors. It seems possible to obtain good correlation between the two types of events. An analysis is made of the accident and estimates are made of the accident probabilities which are found to be of the order of 10{sup -3} per ship reactor years. It if finally pointed out that the consequences of nuclear ship accidents are fairly local and does in no way not approach the magnitude of the Chernobyl accident. It is emphasized that some of the information on which this report is based, may not be correct. Consequently some of the results of the assessments made may not be correct. (au).

  15. Accidents in nuclear ships

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1996-12-01

    This report starts with a discussion of the types of nuclear vessels accidents, in particular accidents which involve the nuclear propulsion systems. Next available information on 61 reported nuclear ship events in considered. Of these 6 deals with U.S. ships, 54 with USSR ships and 1 with a French ship. The ships are in almost all cases nuclear submarines. Only events that involve the sinking of vessels, the nuclear propulsion plants, radiation exposures, fires/explosions, sea-water leaks into the submarines and sinking of vessels are considered. For each event a summary of available information is presented, and comments are added. In some cases the available information is not credible, and these events are neglected. This reduces the number of events to 5 U.S. events, 35 USSR/Russian events and 1 French event. A comparison is made between the reported Soviet accidents and information available on dumped and damaged Soviet naval reactors. It seems possible to obtain good correlation between the two types of events. An analysis is made of the accident and estimates are made of the accident probabilities which are found to be of the order of 10 -3 per ship reactor years. It if finally pointed out that the consequences of nuclear ship accidents are fairly local and does in no way not approach the magnitude of the Chernobyl accident. It is emphasized that some of the information on which this report is based, may not be correct. Consequently some of the results of the assessments made may not be correct. (au)

  16. Code of safety for nuclear merchant ships

    International Nuclear Information System (INIS)

    1982-01-01

    The Code is in chapters, entitled: general (including general safety principles and principles of risk acceptance); design criteria and conditions; ship design, construction and equipment; nuclear steam supply system; machinery and electrical installations; radiation safety (including radiological protection design; protection of persons; dosimetry; radioactive waste management); operation (including emergency operation procedures); surveys. Appendices cover: sinking velocity calculations; seaway loads depending on service periods; safety assessment; limiting dose-equivalent rates for different areas and spaces; quality assurance programme; application of single failure criterion. Initial application of the Code is restricted to conventional types of ships propelled by nuclear propulsion plants with pressurized light water type reactors. (U.K.)

  17. Towards a nuclear merchant ship

    International Nuclear Information System (INIS)

    Nicholson, R.L.R.; Llewelyn, G.I.W.; Farmer, A.A.

    1976-01-01

    The operation of nuclear merchant ships is likely to be attended by a number of constraints and requirements. Not all of these can be fully resolved until such ships come into use and the necessary experience and confidence have been acquired. But the timing of commercial introduction, if it comes about, will depend on the relative economics of nuclear versus fossil fuel propulsion, and the differences in turn depend in part on the operating costs particular to nuclear ships. A review of operation aspects is essential not only to commercial appraisal; each country whose trade may be carried in nuclear ships - whether it will build such ships or not - will have occasion to give some attention to the problems. It is an international problem and is, as noted later, being considered internationally. This paper; i) reviews some of the operational aspects as seen in the U.K.; ii) summarizes views received by the Nuclear Merchant Ship Unit (NMSU) from U.K. shipping, shipbuilding and nuclear industries on the prospects of a U.K. nuclear merchant ship. (author)

  18. Welding technologies for nuclear machinery and equipment

    International Nuclear Information System (INIS)

    Kobayashi, Masahiro; Yokono, Tomomi.

    1991-01-01

    The main welding methods applied to nuclear machinery and equipment are shielded metal arc welding, submerged arc welding, MAG welding and TIG welding. But in the last 10 years, in order to improve the reliability required for the welding of nuclear machinery and equipment, the welding technologies aiming at the reduction of heat input, the decrease of the number of welding pass and the automatic control of welding factors have been applied for the main purpose of bettering the quality and excluding human errors. The merits and the technology of narrow gap, pulsed MAG welding and melt-through welding are explained. As the automation of TIG welding, image processing type narrow gap, hot wire TIG welding and remote control type automatic TIG welding are described. For the longitudinal welding of active metal sheet products, plasma key-hole welding is applied. Since the concentration of its arc is good, high speed welding with low heat input can be done. For the stainless steel cladding by welding, electroslag welding has become to be employed in place of conventional submerged arc welding. Arc is not generated in the electroslag welding, and the penetration into base metal is small. (K.I.)

  19. Potential risks of nuclear ships

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1994-07-01

    This report represents an attempt to evaluate the potential risks of nuclear ships. Firstly reasons are given why nuclear ship accidents will not lead to accidents of the magnitude of the Chernobyl accident. This is due to much lower content of radioactive material and to different reactor designs. Next a review is given of the types of accidents which have actually occurred. Of these the reactor accidents which may lead to serious consequences for the crew and the environment are considered further. These are reactivity accidents and loss of coolant accidents. In addition the long term risks of sunken nuclear ships and sea disposed reactor compartments etc. are also discussed. Based on available accident data an attempt is made to estimate the probability of serious nuclear ship accidents. (au)

  20. Design and modelling of innovative machinery systems for large ships

    DEFF Research Database (Denmark)

    Larsen, Ulrik

    Eighty percent of the growing global merchandise trade is transported by sea. The shipping industry is required to reduce the pollution and increase the energy efficiency of ships in the near future. There is a relatively large potential for approaching these requirements by implementing waste heat...... consisting of a two-zone combustion and NOx emission model, a double Wiebe heat release model, the Redlich-Kwong equation of state and the Woschni heat loss correlation. A novel methodology is presented and used to determine the optimum organic Rankine cycle process layout, working fluid and process......, are evaluated with regards to the fuel consumption and NOx emissions trade-off. The results of the calibration and validation of the engine model suggest that the main performance parameters can be predicted with adequate accuracies for the overall purpose. The results of the ORC and the Kalina cycle...

  1. Are nuclear ships environmentally safer than conventionally powered ships

    International Nuclear Information System (INIS)

    Bone, C.A.; Molgaard, C.A.; Helmkamp, J.C.; Golbeck, A.L.

    1988-01-01

    An epidemiologic analysis was conducted to determine if risk of hospitalization varied by age, ship type, or occupation between nuclear and conventional powered ship crews in the U.S. Navy. Study cohorts consisted of all male enlisted personnel who served exclusively aboard conventional or nuclear powered aircraft carriers and cruisers during the years 1975-1979; cases were those men hospitalized during this period (N = 48,242). Conventional ship personnel showed significantly elevated rates of injury and disease when compared to nuclear ship personnel. The largest relative risks by age occurred for conventional ship crewmen less than 30 years old. Seaman, logistics (supply), and healthcare personnel serving aboard conventional ships comprised the occupational groups exhibiting the highest hospitalization rate differentials. The results strongly suggest that nuclear ships provide a healthier, safer working and living environment than conventional ships

  2. New Zealand code for nuclear powered shipping

    International Nuclear Information System (INIS)

    1976-06-01

    This report recommends guidelines for the safety precautions and procedures to be implemented when New Zealand ports and approaches are used by nuclear powered merchant ships and nuclear powered naval ships

  3. SKODA Nuclear Machinery - tradition and expertise in nuclear power industry

    International Nuclear Information System (INIS)

    Svitak, F.

    1997-01-01

    The SKODA Nuclear Machinery company is a major manufacturer of nuclear reactor assemblies and supplier of WWER type primary coolant circuits. In the past, the company was nearly a monopolistic manufacturer of WWER reactor assemblies supplied to the Central and East European countries (except the USSR) grouped in the former Council of Mutual Economic Assistance. Over the 1980-1993 period, 21 units of the WWER-440 type and 3 units of the WWER-1000 type were manufactured. The company keeps abreast of technological progress and has been switching to new manufacturing areas, such as compact storage racks for spent fuel pools, hermetic cable bushings, spent fuel storage and transport casks, and cooperation in the manufacture of neutron flux measuring channels. Technological services provided to nuclear power plants constitute another important field of the company's business. The company's combined expertise in Soviet and Western designed PWRs is a considerable asset. (P.A.)

  4. Development of nuclear powered ship in Japan

    International Nuclear Information System (INIS)

    Sato, Hiroshi

    1976-01-01

    The development of nuclear merchant ship in Japan was started in 1955 by the establishment of Nuclear Ship Study Group, and since then, the investigation, test and research on nuclear ships have been continued. As a result, a nuclear ocean observation and supply ship was designed for trial. Researches were carried out also in JAERI and Institute for Technical Research of Ships. Meanwhile, the nuclear icebreaker Lenin was completed in Soviet Union in 1959, the nuclear ship Savannah set out for maiden voyage in U.S. in 1962, and the construction of the nuclear ore carrier Otto Hahn was prepared in FRG. Japan Nuclear Ship Development Corp. was established in 1963, and started the design and construction of the first nuclear ship in Japan, Mutsu. The basic policy in the construction is the improvement of nuclear ship technology, the securing of safety, and the use of domestic technologies as far as possible. The progress of the design, construction and test of the Mutsu is described. Owing to the problem of radiation leak, the development of nuclear ships stagnated for a while, but the nuclear plant of the Mutsu demonstrated the expected performance in the functional test, land criticality test and zero output test, and it is expected that the bud of the independent development brought up so far can bear valuable fruit. The independent development of marine nuclear reactors should be continued by selecting the way most suitable to Japan. (Kako, I.)

  5. Japan nuclear ship sea trial

    International Nuclear Information System (INIS)

    Yamazaki, Hiroshi; Kitamura, Toshikatus; Mizushima, Toshihiko

    1992-01-01

    The sea trial of the first Japan nuclear Ship 'MUTSU' was conducted from the end of October to December in 1990. The purpose of the sea trial was to verify the nuclear propulsive performances and maneuverabilities. The present report describes the results of the sea trial. These results are classified into four items: 1. Speed test and engineering performance tests 2. Maneuvering performance tests 3. Vibration tests 4. Other tests. Acceptable performances were demonstrated, as expected in the original design. The experience of the use of the Global Positioning System (GPS), which were newly adopted for the sea trial, is also reported. (author)

  6. The National Shipbuilding Research Program, 1997 Ship Production Symposium, Paper No. 21: A Parametric Approach to Machinery Unitization in Shipbuilding

    National Research Council Canada - National Science Library

    Jaquith, Peter E; Burns, Richard M; Duneclift, Lee A; Gaskari, Massood; Green, Thomas; Silveira, John L; Walsh, Anthony

    1997-01-01

    During the past ten years, both U.S. and foreign shipyards have developed advanced unitization concepts that include multi-level assemblies representing large vertical segments of ship machinery spaces...

  7. Nuclear powered freight ships - safe and reliable

    International Nuclear Information System (INIS)

    Schafstall, H.C.

    1978-12-01

    The five nuclear-powered ships built in the world so far have entered over 100 ports in 14 countries about 1000 times in 15 years, during which there were no accidents endangering the safety of a ship. However, for the expansion of freight shipping with nuclear power, comprehensive international regulations for safety requirements, responsibility etc., are necessary. Although the NEA/IAEO symposium excluded economic questions on the safety of nuclear powered ships, the trends regarding further development in individual countries became clear

  8. Some concepts of future nuclear ship

    International Nuclear Information System (INIS)

    Fujino, Masataka

    2000-01-01

    Characteristic features of nuclear power generation are as follows: (1) Thermal energy can be continuously extracted for a long time without fuel feed, (2) Nuclear energy is suitable for generating huge power, (3) Oxygen is unnecessary for combustion of fuel, and (4) Unlike fossil fuel, nuclear power generation does not exhaust NOx, SOx, and CO 2 : it can be considered environmentally friendly. In view of these features, the Japan Atomic Energy Research Institute commissioned the Shipbuilding Research Association of Japan (JSRA) to survey what kinds of nuclear ship would be put to practical use in the near future. For this purpose, a research committee was organized in 1992 by the JSRA, and concluded its investigation in 1996. The main aim of this research was to clarify the requirements of ship performance as nuclear ships, and then to extract the technical issues of the marine reactor installed in nuclear ships to be solved. As a result of the survey, it was suggested that displacement-type large high-speed container ship would be one of the promising future nuclear merchant ships, and 6500 m deep-sea and 600 m undersea scientific research submersibles would be other promising nuclear special purpose ships. At the same time, various requirements of marine reactors, which are expected to be installed in these ships, were clarified mainly from the technical viewpoints. (author)

  9. Development of a nuclear ship safety philosophy

    International Nuclear Information System (INIS)

    Thompson, T.E.

    1978-01-01

    A unique safety philosophy must be recognized and accepted as an integral part of the design and operation of a nuclear ship. For the nuclear powered ship, the ultimate safety of the reactor and therefore the crew and the environment lies with the safety of the ship itself. The basis for ship safety is its ability to navigate and survive the conditions or the environment in which it may find itself. The subject of traditional ship safety is examined along with its implication for reactor protection and safety. Concepts of reactor safety are also examined. These two philosophies are combined in a manner so as to provide a sound philosophy for the safety of nuclear ships, their crews, and the environment

  10. Report of Nuclear Powered Ship Meeting

    International Nuclear Information System (INIS)

    1984-01-01

    The development of nuclear-powered ships in Japan broke down due to the radiation leak on the nuclear ship ''Mutsu'' in 1974, and the objective has not yet been attained. The Japan Nuclear Ship Research and Development Agency was reorganized to advance the development of nuclear-powered ships and to develop marine nuclear reactors. Recently, various opinions have been expressed regarding the development of nuclear-powered ships and Mutsu, accordingly, it is necessary to clarify the way it should be. The Atomic Energy Commission organized this meeting to discuss the problem. The practical use of nuclear-powered ships is expected at the beginning of the 21st century, but it is only the guess. But it is important to accumulate the technology, knowledge and experience to prepare for the use of nuclear-powered ships. The continuation of the development of Mutsu is important for the future, and the construction of the new home port is unavoidable. The aim of the research and development, and the concrete way of advancing the research and development of Mutsu are discussed. It is scheduled that the Agency is integrated with other atomic energy organizations by March, 1985. The consideration to be given for implementing the integration is described. (Kako, I.)

  11. Auxiliary facilities on nuclear ship 'MUTSU'

    International Nuclear Information System (INIS)

    Tsujimura, Shotaro; Takigami, Yoshio.

    1989-01-01

    The nuclear ship 'MUTSU' has been moored at SEKINEHAMA, MUTU City in AOMORI Prefecture and several tests and works are being carried out on the ship. The construction of the auxiliary facilities for these works on the ship was completed in safety in August 1988. After that the facilities have fulfilled their function. The outlines of design, fabrication and construction of the facilities are described in this paper. (author)

  12. Nuclear fuel shipping inspection device

    International Nuclear Information System (INIS)

    Takahashi, Toshio; Hada, Koji.

    1988-01-01

    Purpose: To provide an nuclear fuel shipping inspection device having a high detection sensitivity and capable of obtaining highly reliable inspection results. Constitution: The present invention concerns a device for distinguishing a fuel assembly having failed fuel rods in LMFBR type reactors. Coolants in a fuel assembly to be inspected are collected by a sampling pipeway and transferred to a filter device. In the filter device, granular radioactive corrosion products (CP) in the coolants are captured, to reduce the background. The coolants, after being passed through the filter device, are transferred to an FP catching device and gamma-rays of iodine and cesium nuclides are measured in FP radiation measuring device. Subsequently, the coolants transferred to a degasing device to separate rare gas FP in the coolants from the liquid phase. In a case if rare gas fission products are detected by the radiation detector, it means that there is a failed fuel rod in the fuel assembly to be inspected. Since the CP and the soluble FP are separated and extracted for the radioactivity measurement, the reliability can be improved. (Kamimura, M.)

  13. Structural design of nuclear reactor machinery and equipment

    International Nuclear Information System (INIS)

    Hara, Hideki

    1992-01-01

    Since the machinery, equipment and piping which compose nuclear power station facilities are diverse, when those are designed, consideration is given sufficiently to the objective of use and the importance of the object machinery and equipment so that those can maintain the soundness over the design life. In this report, on the contents and the design standard in the design techniques for nuclear reactor machinery and equipment, the way of thinking is shown, taking an example of reactor pressure vessel which is stipulated as the vessel kind 1 in the 'Technical standard of structures and others regarding nuclear facilities for electric power generation', Notice No. 501 of the Ministry of International Trade and Industry. The reactor pressure vessel of 1350 MWe improved type BWR (ABWR) is used under the condition of 87.9 kg/cm 2 and 302 degC, and the inside diameter is about 7.2 m, the inside height is about 21 m, and the wall thickness is about 170 mm. The design standard for reactor pressure vessels and its way of thinking, breakdown prevention design and the design techniques for reactor pressure vessels are described. (K.I.)

  14. Development of the nuclear ship MUTSU spent fuel shipping cask

    International Nuclear Information System (INIS)

    Ishizuka, M.; Umeda, M.; Nawata, Y.; Sato, H.; Honami, M.; Nomura, T.; Ohashi, M.; Higashino, A.

    1989-01-01

    After the planned trial voyage (4700 MWD/MTU) of the nuclear ship MUTSU in 1990, her spent fuel assemblies, initially made of two types of enriched UO 2 (3.2wt% and 4.4wt%), will be transferred to the reprocessing plant soon after cooling down in the ship reactor for more than one year. For transportation, the MUTSU spent fuel shipping casks will be used. Prior to transportation to the reprocessing plant, the cooled spent fuel assemblies will be removed from the reactor to the shipping casks and housed at the spent fuel storage facility on site. In designing the MUTSU spent fuel shipping cask, considerations were given to make the leak-tightness and integrity of the cask confirmable during storage. The development of the cask and the storage function demonstration test were performed by Japan Atomic Energy Research Institute (JAERI) and Mitsubishi Heavy Industries, Ltd. (MHI). One prototype cask for the storage demonstration test and licensed thirty-five casks were manufactured between 1987 and 1988

  15. Spatiotemporal Regulation of Nuclear Transport Machinery and Microtubule Organization

    Science.gov (United States)

    Okada, Naoyuki; Sato, Masamitsu

    2015-01-01

    Spindle microtubules capture and segregate chromosomes and, therefore, their assembly is an essential event in mitosis. To carry out their mission, many key players for microtubule formation need to be strictly orchestrated. Particularly, proteins that assemble the spindle need to be translocated at appropriate sites during mitosis. A small GTPase (hydrolase enzyme of guanosine triphosphate), Ran, controls this translocation. Ran plays many roles in many cellular events: nucleocytoplasmic shuttling through the nuclear envelope, assembly of the mitotic spindle, and reorganization of the nuclear envelope at the mitotic exit. Although these events are seemingly distinct, recent studies demonstrate that the mechanisms underlying these phenomena are substantially the same as explained by molecular interplay of the master regulator Ran, the transport factor importin, and its cargo proteins. Our review focuses on how the transport machinery regulates mitotic progression of cells. We summarize translocation mechanisms governed by Ran and its regulatory proteins, and particularly focus on Ran-GTP targets in fission yeast that promote spindle formation. We also discuss the coordination of the spatial and temporal regulation of proteins from the viewpoint of transport machinery. We propose that the transport machinery is an essential key that couples the spatial and temporal events in cells. PMID:26308057

  16. Nuclear ship accidents, description and analysis

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1993-03-01

    In this report available information on 44 reported nuclear ship events is considered. Of these 6 deals with U.S. ships and 38 with USSR ships. The ships are in almost all cases nuclear submarines. Only events that involve the sinking of vessels, the nuclear propulsion plants, radiation exposures, fires/ explosions, sea-water leaks into the submarines and sinking of vessels are considered. Comments are made on each of the events, and at the end of the report an attempt is made to point out the weaknesses of the submarine designs which have resulted in the accidents. It is emphasized that some of the information of which this report is based, may be of dubious nature. Consequently some of the results of the assessments made may not be correct. (au)

  17. Development of the Nuclear Ship Database. 1. Outline of the Nuclear Ship Experimental Database

    Energy Technology Data Exchange (ETDEWEB)

    Kyouya, Masahiko; Ochiai, Masa-aki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Hashidate, Kouji

    1995-03-01

    We obtained the experimental data on the effects of the ship motions and the change in load and caused by the ship operations, the waves, the winds etc., to the nuclear power plant behavior, through the Power-up Tests and Experimental Voyages of the Nuclear Ship MUTSU. Moreover, we accumulated the techniques, the knowledge and others on the Nuclear Ship development at the each stage of the N.S. MUTSU Research and Development program, such as the design stage, the construction stage, the operation stage and others. These data, techniques, knowledge and others are the assembly of the experimental data and the experiences through the design, the construction and the operation of the first nuclear ship in JAPAN. It is important to keep and pigeonhole these products of the N.S. MUTSU program in order to utilize them effectively in the research and development of the advanced marine reactor, since there is no construction plan of the nuclear ship for the present in JAPAN. We have been carrying out the development of the Nuclear Ship Database System since 1991 for the purpose of effective utilization of the N.S. MUTSU products in the design study of the advanced marine reactors. The part of the Nuclear Ship Database System on the experimental data, called Nuclear Ship Experimental Database, was already accomplished and utilized since 1993. This report describes the outline and the use of the Nuclear Ship Experimental Database.The remaining part of the database system on the documentary data, called Nuclear Ship Documentary Database, are now under development. (author).

  18. Development of the Nuclear Ship Database. 1. Outline of the Nuclear Ship Experimental Database

    International Nuclear Information System (INIS)

    Kyouya, Masahiko; Ochiai, Masa-aki; Hashidate, Kouji.

    1995-03-01

    We obtained the experimental data on the effects of the ship motions and the change in load and caused by the ship operations, the waves, the winds etc., to the nuclear power plant behavior, through the Power-up Tests and Experimental Voyages of the Nuclear Ship MUTSU. Moreover, we accumulated the techniques, the knowledge and others on the Nuclear Ship development at the each stage of the N.S. MUTSU Research and Development program, such as the design stage, the construction stage, the operation stage and others. These data, techniques, knowledge and others are the assembly of the experimental data and the experiences through the design, the construction and the operation of the first nuclear ship in JAPAN. It is important to keep and pigeonhole these products of the N.S. MUTSU program in order to utilize them effectively in the research and development of the advanced marine reactor, since there is no construction plan of the nuclear ship for the present in JAPAN. We have been carrying out the development of the Nuclear Ship Database System since 1991 for the purpose of effective utilization of the N.S. MUTSU products in the design study of the advanced marine reactors. The part of the Nuclear Ship Database System on the experimental data, called Nuclear Ship Experimental Database, was already accomplished and utilized since 1993. This report describes the outline and the use of the Nuclear Ship Experimental Database.The remaining part of the database system on the documentary data, called Nuclear Ship Documentary Database, are now under development. (author)

  19. Fuel exchanger for nuclear ships

    International Nuclear Information System (INIS)

    Suda, Koji; Kanbara, Takahisa; Watanabe, Masaharu.

    1984-01-01

    Purpose: To prevent enviromental contamination landing radioactive materials from the inside of a ship. Constitution: A provisional cabin having a shape covering a reactor hatch and a hatch cover is disposed on the upper deck of a ship body. A ceiling shutter is disposed to the cabin. A protection cylinder having a shutter and a filter fan is attached on the cabin. Materials to be discharged out of the ship are transported to a fuel exchange tower on land by using a crane while being contained in the protection cylinder with the shutter being closed. The protection cylinder is connected by means of a wire rope to a loop-wheel machine which disposed on the trolly of a crane. While the bellows through which the suspending wire for the discharged products passes is perforated, since the inside of the cylinder is depressurized by a filter fan, there is no air leakage through the perforation to the outside. (Ikeda, J.)

  20. Fuel exchanger for nuclear ships

    Energy Technology Data Exchange (ETDEWEB)

    Suda, Koji; Kanbara, Takahisa; Watanabe, Masaharu

    1984-11-29

    To prevent enviromental contamination by radioactive materials from the inside of a ship a provisional cabin having a shape covering a reactor hatch and a hatch cover is disposed on the upper deck of a ship body. A ceiling shutter is disposed to the cabin. A protection cylinder having a shutter and a filter fan is attached on the cabin. Materials to be discharged out of the ship are transported to a fuel exchange tower on land by using a crane while being contained in the protection cylinder with the shutter being closed. The protection cylinder is connected by means of a wire rope to a loop-wheel machine which is disposed on the trolly of a crane. While the bellows through which the suspending wire for the discharged products passes is perforated, since the inside of the cylinder is depressurized by a filter fan, there is no air leakage through the perforation to the outside.

  1. Report of nuclear powered ship meeting

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    The research and development of nuclear powered ships in Japan have been advanced centering around the Japan Nuclear Ship Development Agency established in 1963. It is regretful that the development of ''Mutsu'' is largely behind the schedule due to the radiation leak in 1974, and the expected objective has not yet been attained even today. The government decided to advance the research on the improvement of marine nuclear reactors in 1980, and this new research function was given to the Agency by changing its organization. However, recently various arguments have arisen concerning the way of the research and development of nuclear ships in Japan centering around ''Mutsu'', such as the necessity of developing nuclear ships, the enormous expenditure for the development, the aging of ''Mutsu'' more than 10 years after the construction, the introduction of nuclear ship technology from foreign countries and so on. By the end of fiscal 1984, the Agency is expected to merge with other organization related to atomic energy, therefore, it is necessary to decide the way of research and development. This meeting organized by the Atomic Energy Commission makes this report to show the way of thinking about the above arguments. (Kako, I.)

  2. Report of Nuclear Powered Ship Council

    International Nuclear Information System (INIS)

    1982-01-01

    From the forecast of energy balance in the world to 21st century, the diversification of energy supply and the technical development enabling it are necessary in Japan. The stable supply of marine fuel is important to maintain and develop the national life. At present, as the marine fuel substituting for petroleum, atomic energy is at the position nearest to practical use. In advanced countries, the basic technology required for the practical use of nuclear-powered merchant ships seems to have been established, but Japan is about 10 years behind them due to the delay of the Mutsu project. In order to maintain and improve the technical level of shipbuilders, the independent technology related to nuclear-powered ships must be established in Japan. In the economical examination of nuclear-powered ships, ice breakers and ice breaking tankers are advantageous, but in other types of ships, a number of conditions must be satisfied to be economical. The Mutsu must be operated to collect the data and experience, and the project of an improved marine prototype reactor must be decided. Also a demonstration ship must be built. The standards for the design, construction and operation of nuclear-powered ships and the public acceptance are necessary. (Kako, I.)

  3. Fuel exchanging machine for a nuclear ship

    International Nuclear Information System (INIS)

    Hayashi, Tetsuji.

    1984-01-01

    Purpose: To prevent atmospheric contaminations upon fuel exchange thereby keep the environmental circumstance clean in the periphery of the nuclear ship. Constitution: A nuclear reactor container is disposed to the inside of a containing vessel in the ship body and a shutter is mounted to the upper opening of the ship body. Further, a landing container having a bottom opening equipped with shutter for alingning the upper opening equipped with shuuter of the ship is elevatably suspended to the trolley of a crane by way of a wire rope and a winch, and a fuel exchange cask is elevatably disposed to the inside of the landing container. Further, airs in the inside of the container is adapted to be discharged externally through a filter by means of a blower and the inside is kept at a negative pressure. Thus, since the containing vessel is covered with the landing container upon fuel exchanging operation, atmospheric contamination can be prevented sufficiently. (Sekiya, K.)

  4. Feasibility Study on Nuclear Propulsion Ship according to Economic Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Gil, Youngmi; Yoo, Seongjin; Oh, June; Byun, Yoonchul; Woo, Ilguk [Daewoo Shipbuilding and Marine Engineering Co., Ltd, Seoul (Korea, Republic of); Kim, Jiho; Choi, Suhn [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    The use of nuclear ships has been extending to the icebreaker, the deep-water exploration ship, and the floating nuclear power plant. Prior to developing the new ship, the relevant regulations need to be considered. In this study, we reviewed the nuclear ship-related regulations. In addition, economic value is one of the most important factors which should be considered in the pre-design phase. To evaluate the economics of the nuclear ship, we calculated Capital Expenditure (abbreviated as CAPEX) and Operation Expenditure (abbreviated as OPEX) for various types of ships. We reviewed the nuclear ship-related regulations and evaluated the economics of the nuclear ship compared to the diesel ship. The calculation result shows that economic feasibility of the nuclear ship depends on the oil price as well as the cost of the nuclear reactor.

  5. Change of nuclear reactor installation in the first nuclear ship of Japan Nuclear Ship Development Agency

    International Nuclear Information System (INIS)

    1979-01-01

    The written application concerning the change of nuclear reactor installation in the first nuclear ship was presented from the JNSDA to the prime minister on January 10, 1979. The contents of the change are the repair of the primary and secondary shields of the reactor, the additional installation of a storage tank for liquid wastes, and the extension of the period to stop the reactor in cold state. The inquiry from the prime minister to the Nuclear Safety Commission was made on June 9, 1979, through the examination of safety in the Nuclear Safety Bureau, Science and Technology Agency. The Nuclear Safety Commission instructed to the Committee for the Examination of Nuclear Reactor Safety on June 11, 1979, about the application of criteria stipulated in the law. The relevant letters and the drafts of examination papers concerning the technical capability and the safety in case of the change of nuclear reactor installation in the first nuclear ship are cited. The JNSDA and Sasebo Heavy Industries, Ltd. seem to have the sufficient technical capability to carry out this change. As the result of examination, it is recognized that the application presented by the JNSDA is in compliance with the criteria stipulated in the law concerning the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors. (Kako, I.)

  6. Trace of the nuclear powered ship 'Mutsu'

    International Nuclear Information System (INIS)

    1992-01-01

    The development of the nuclear powered ship 'Mutsu' required the long period of about 30 years from 1963 to 1992. When this period is looked back, it is roughly divided into the period from the initial planning to the construction, the period of the power increase test and the occurrence of radiation leak, the period of the repair of shielding and the general safety checkup as the countermeasures, the period of the checkup and maintenance based on the new research plan, the period of the power increase test and the sea trial, and the period of the experimental voyage after the completion. The course of the development of the nuclear powered ship 'Mutsu' is shown. The design of Mutsu, the incidental land facilities for Mutsu, the power increase test and the experimental voyage of Mutsu, the law system for nuclear powered ships, the research and development of an improved marine nuclear reactor and the development of nuclear powered ships in the world are reported. Nuclear powered warships are operated in USA, USSR, UK, France and China. (K.I.)

  7. Parvoviral nuclear import: bypassing the host nuclear-transport machinery.

    Science.gov (United States)

    Cohen, Sarah; Behzad, Ali R; Carroll, Jeffrey B; Panté, Nelly

    2006-11-01

    The parvovirus Minute virus of mice (MVM) is a small DNA virus that replicates in the nucleus of its host cells. However, very little is known about the mechanisms underlying parvovirus' nuclear import. Recently, it was found that microinjection of MVM into the cytoplasm of Xenopus oocytes causes damage to the nuclear envelope (NE), suggesting that the nuclear-import mechanism of MVM involves disruption of the NE and import through the resulting breaks. Here, fluorescence microscopy and electron microscopy were used to examine the effect of MVM on host-cell nuclear structure during infection of mouse fibroblast cells. It was found that MVM caused dramatic changes in nuclear shape and morphology, alterations of nuclear lamin immunostaining and breaks in the NE of infected cells. Thus, it seems that the unusual nuclear-import mechanism observed in Xenopus oocytes is in fact used by MVM during infection of host cells.

  8. Shipping container for nuclear fuels

    International Nuclear Information System (INIS)

    Housholder, W.R.; Greer, N.L.

    1976-01-01

    A container for nuclear materials is described wherein a specially and uniquely constructed pressure vessel and gamma shield assembly for holding the nuclear materials is provided in a housing, and wherein a positioning means extends between the housing and the assembly for spacing the same, insulation in the housing essentially filling the space between the assembly and housing, the insulation comprising beads, globules or the like of water encapsulated in plastic and which, in one important embodiment, contains neutron absorbing matter

  9. Spent nuclear fuel shipping basket

    International Nuclear Information System (INIS)

    Wells, A.H.

    1990-01-01

    This patent describes a basket for a cask for transporting nuclear fuel elements. It comprises: sleeve members, each of the sleeve members having interior cross-section dimensions for receiving a nuclear fuel assembly such that the assembly is restrained from lateral movement within the sleeve member, apertured disk members, means for axially aligning the apertures in the disk members, and means for maintaining the disk members in fixed spaced relationship to form a disk assembly, comprising an array of disks, the aligned apertures of the disks being adapted to receive the sleeve members and maintain them in fixed spaced relationship

  10. Safe operation of nuclear ships

    International Nuclear Information System (INIS)

    Danilov, L.

    1982-01-01

    A summary is given of the experience with the three Soviet nuclear icebreakers, Lenin, Arktika and Sibir. Engineering problems, especially of reactor maintenance, and the way they have been overcome, are described. Reference is also made to improvements in reactor fuel and core design, and to safety aspects of the refuelling operation. (U.K.)

  11. Historic survey on nuclear merchant ships

    Energy Technology Data Exchange (ETDEWEB)

    Freire, Luciano Ondir, E-mail: luciano.ondir@gmail.com; Andrade, Delvonei Alves de, E-mail: delvonei@ipen.br

    2015-11-15

    Highlights: • The nuclear merchants ships already built are described and studied. • Their history and main architectural choices are presented, focusing nuclear domain. • The typical problems in those projects are discussed. • Some key factors for developing successful nuclear merchant ships are identified. - Abstract: This work provides a survey on past nuclear merchant ships experience. On light of new regulations on CO{sub 2}, SO{sub x} and NO{sub x}, the options for clean naval propulsion need to be studied. Despite many efforts, the only already sea proven emissions-free energy is nuclear power of pressurized water reactor type. Given the past experience on the field, this work provides some information on history, architectures and hints of reasons for the success or failures of each project. It is found that adequate requirements identification must be done keeping economics always in the center of design. Experience shows, except after major catastrophic accidents, public trust may be earned by open dialog and sound engineering practices.

  12. Historic survey on nuclear merchant ships

    International Nuclear Information System (INIS)

    Freire, Luciano Ondir; Andrade, Delvonei Alves de

    2015-01-01

    Highlights: • The nuclear merchants ships already built are described and studied. • Their history and main architectural choices are presented, focusing nuclear domain. • The typical problems in those projects are discussed. • Some key factors for developing successful nuclear merchant ships are identified. - Abstract: This work provides a survey on past nuclear merchant ships experience. On light of new regulations on CO 2 , SO x and NO x , the options for clean naval propulsion need to be studied. Despite many efforts, the only already sea proven emissions-free energy is nuclear power of pressurized water reactor type. Given the past experience on the field, this work provides some information on history, architectures and hints of reasons for the success or failures of each project. It is found that adequate requirements identification must be done keeping economics always in the center of design. Experience shows, except after major catastrophic accidents, public trust may be earned by open dialog and sound engineering practices.

  13. Decommissioning of naval nuclear ships

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1993-10-01

    During the next decade the two major nuclear powers will each have to decommission more than 100 naval nuclear vessels, in particular submarines. The problems connected with this task is considered in this report. Firstly the size of the task is considered, i.e. the number of nuclear vessels that has to be decommissioned. Secondly the reactors of these vessels, their fuel elements, their power level, the number of reactors per vessel and the amount of radioactivity to be handled are discussed. Thirdly the decommissioning procedures, i.e. The removal of fuel from the vessels, the temporary storage of the reactor fuel near the base, and the cleaning and disposal of the reactor and the primary circuit components are reviewed. Finally alternative uses of the newer submarines are briefly considered. It should be emphasizes that much of the detailed information on which this report is based, may be of dubious nature, and that may to some extent affect the validity of the conclusions of the report. (au)

  14. Standardized analyses of nuclear shipping containers

    International Nuclear Information System (INIS)

    Parks, C.V.; Hermann, O.W.; Petrie, L.M.; Hoffman, T.J.; Tang, J.S.; Landers, N.F.; Turner, W.D.

    1983-01-01

    This paper describes improved capabilities for analyses of nuclear fuel shipping containers within SCALE -- a modular code system for Standardized Computer Analyses for Licensing Evaluation. Criticality analysis improvements include the new KENO V, a code which contains an enhanced geometry package and a new control module which uses KENO V and allows a criticality search on optimum pitch (maximum k-effective) to be performed. The SAS2 sequence is a new shielding analysis module which couples fuel burnup, source term generation, and radial cask shielding. The SAS5 shielding sequence allows a multidimensional Monte Carlo analysis of a shipping cask with code generated biasing of the particle histories. The thermal analysis sequence (HTAS1) provides an easy-to-use tool for evaluating a shipping cask response to the accident capability of the SCALE system to provide the cask designer or evaluator with a computational system that provides the automated procedures and easy-to-understand input that leads to standarization

  15. Flooding and sinking of nuclear merchant ships

    International Nuclear Information System (INIS)

    Lettnin, H.K.J.; Wehowsky, P.

    1978-01-01

    In contrast to land-based power plants for ship reactors the marine environment brings up the peril of sinking. But this peril is low for nuclear ships with its high safety standard. An evaluation of casualties from 1964 - 1974 for ships>8000 GRT allows to estimate a very low sink probability for nuclear ships in the range of 10 -7 to 10 -8 p.a. In spite of this low probability a sinking cannot be excluded absolutely. Therefore passive means must be provided for sinking in deep waters: to maintain the integrity of at least one enclosure as activity barrier; to supply seawater into the safety containment for decay heat removal. For sinking in shallow waters and flooding at least one of the redundant decay heat removal systems including power supply stays operable. A mathematical tool is available for the design of flood openings of sufficient cross sections to flood the containment and to reach a pressure balance in case of postulated sinking in deep waters of any depth

  16. Concept Design and Risk Assessment of Nuclear Propulsion Ship

    International Nuclear Information System (INIS)

    Gil, Youngmi; Yoo, Seongjin; Kim, Yeontae; Oh, June; Byun, Yoonchul; Woo, Ilguk; Kim, Jiho; Choi, Suhn

    2014-01-01

    The nuclear propulsion ships (hereinafter referred to as 'nuclear ships') have been considered as an eco-friendly ship. There have historically been warship and submarine with the source of nuclear power. The use of nuclear ships has been recently extending to the icebreaker, the deep-water exploration ship, and the floating nuclear power plant. Prior to developing the new ship, we evaluated the economics of various types of ships and concluded that the container ship could be appropriate for the nuclear propulsion. In order to verify its safety, we performed the ship calculation based on the optimal arrangement of the nuclear reactor. Finally, we verified its safety by the HAZID. In the former research, we confirmed the applicability of the nuclear propulsion system for the large container ship. In this study, we verified the safety of the nuclear ships according to the HAZID analysis. We expect that this research will lead to safe design of the nuclear ships

  17. Concept Design and Risk Assessment of Nuclear Propulsion Ship

    Energy Technology Data Exchange (ETDEWEB)

    Gil, Youngmi; Yoo, Seongjin; Kim, Yeontae; Oh, June; Byun, Yoonchul; Woo, Ilguk [Daewoo Shipbuilding and Marine Engineering Co. Ltd., Seoul (Korea, Republic of); Kim, Jiho; Choi, Suhn [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The nuclear propulsion ships (hereinafter referred to as 'nuclear ships') have been considered as an eco-friendly ship. There have historically been warship and submarine with the source of nuclear power. The use of nuclear ships has been recently extending to the icebreaker, the deep-water exploration ship, and the floating nuclear power plant. Prior to developing the new ship, we evaluated the economics of various types of ships and concluded that the container ship could be appropriate for the nuclear propulsion. In order to verify its safety, we performed the ship calculation based on the optimal arrangement of the nuclear reactor. Finally, we verified its safety by the HAZID. In the former research, we confirmed the applicability of the nuclear propulsion system for the large container ship. In this study, we verified the safety of the nuclear ships according to the HAZID analysis. We expect that this research will lead to safe design of the nuclear ships.

  18. Utilization of nuclear technology to ship

    International Nuclear Information System (INIS)

    Kim, H. C.

    2004-01-01

    The SMART, a medium sized power plant with an output of 330mwth, can be used on barges to generate electric power and water, and can be used to propel container ships. For high speed, to secure the container cargo, and huge container carriers, to lower the operating expenses, the use of nuclear power reactor is essential. To compete in this challenging area with the advanced countries, a well-orchestrated joint effort will be necessary by the government and the industries

  19. Improved hybrid isolator with maglev actuator integrated in air spring for active-passive isolation of ship machinery vibration

    Science.gov (United States)

    Li, Yan; He, Lin; Shuai, Chang-geng; Wang, Chun-yu

    2017-10-01

    A hybrid isolator consisting of maglev actuator and air spring is proposed and developed for application in active-passive vibration isolation system of ship machinery. The dynamic characteristics of this hybrid isolator are analyzed and tested. The stability and adaptability of this hybrid isolator to shock and swing in the marine environment are improved by a compliant gap protection technique and a disengageable suspended structure. The functions of these new engineering designs are proved by analytical verification and experimental validation of the designed stiffness of such a hybrid isolator, and also by shock adaptability testing of the hybrid isolator. Finally, such hybrid isolators are installed in an engineering mounting loaded with a 200-kW ship diesel generator, and the broadband and low-frequency sinusoidal isolation performance is tested.

  20. Concrete shielding for nuclear ship 'Mutsu'

    International Nuclear Information System (INIS)

    Nagase, Tetsuo; Nakajima, Tadao; Okumura, Tadahiko; Saito, Tetsuo

    1983-01-01

    The nuclear ship ''Mutsu'' was constructed in 1970 as the fourth in the world. On September 1, 1974, during the power raising test in the Pacific Ocean, radiation leak was detected. As the result of investigation, it was found that the cause was the fast neutrons streaming through the gap between the reactor pressure vessel and the primary shield. In order to repair the shielding facility, the Japan Nuclear Ship Research Development Agency carried out research and development and shielding design. It was decided to adopt serpentine concrete for the primary shield, which is the excellent moderator of fast neutrons even at high temperature, and heavy concrete for the secondary shield, which is effective for shielding both gamma ray and neutron beam. The repair of shielding was carried out in the Sasebo Shipyard, and completed in August, 1982. The outline of the repair work is reported. The weight increase was about 300 t. The conditions of the shielding design, the method of shielding analysis, the performance required for the shielding concrete, the preliminary experiment on heavy concrete and the construction works of serpentine concrete and heavy concrete are described. (Kako, I.)

  1. Nuclear powered ships. Findings from a feasibility study

    International Nuclear Information System (INIS)

    Namikawa, Shunichiro; Maerli, Morten Bremer; Hoffmann, Peter Nyegaard; Brodin, Erik

    2011-01-01

    Nuclear shipping is attractive for several reasons, one of which is its positive effect on emissions (CO 2 , NOx and SOx). The benefits, however, do not come without risks of possible harmful effects on humans and wildlife. Nuclear ships set themselves apart from conventional ships, as well as from on-shore nuclear power-plants, on several counts. 1) The reactor-unit are non-stationary, and the reactor is subject to the ship motions. 2) Ship reactors must be compact due to space constraints. 3) Special design considerations are required to ensure reactor safety and security, as well as to enable refuelling. 4) A naval nuclear fuel cycle infrastructure for fuel fabrication, handling, and disposal is needed. Technological feasibility of nuclear shipping is by itself inconclusive to a expansion into civilian applications and use. Civilian nuclear propulsion needs to be commercially viable and politically acceptable. Appropriate legislation must be in place, and nuclear shipping concepts with proven safety records and highest possible nuclear proliferation-resistance must be established. Possible 'showstoppers' to a viable nuclear civilian shipping industry are outlined in the paper in view of Political, Technical, Regulatory, Commercial, Safety and Security aspects. Further, different types of ships with different propulsion system are compared in lights of life cycle cost and air emission. (author)

  2. Some considerations on the safety of nuclear ships

    International Nuclear Information System (INIS)

    Kuramoto, Masaaki

    1978-01-01

    For realizing the practical utilization of nuclear merchant ships, it is essential to gain their acceptance by maritime countries on an equal footing with conventional vessels, and to have the administrative procedures for their admission simplified. This, however cannot be expected to be attained overnight, and progressive measures will have to be adopted, to approach the ultimate goal step by step. The first step should be to demonstrate the safety of nuclear propulsion, for which nuclear ships must accumulate their mileages of safe service. The second important step is to simplify the procedures demanded of nuclear ships for access to ports, through the establishment of international safety standards and design criteria, the enforcement of safety measures covering the entrance of nuclear ships into ports, and the assurance of safety in he repair, inspection and refuelling operations of these ships. Among these measures, the considerations relevant to port entry are the subject of vital interest to both ship operators and port authorities

  3. Concrete shielding for nuclear ship 'Mutsu'

    International Nuclear Information System (INIS)

    Nagase, Tetsuo; Saito, Tetsuo

    1983-01-01

    The repair works of the shielding for the nuclear ship ''Mutsu'' were completed in August, 1982. For the primary shielding, serpentine concrete was adopted as it contains a large quantity of water required for neutron shielding, and in the secondary shielding at the upper part of the reactor containment vessel, the original shielding was abolished, and the heavy concrete (high water content, high density concrete) which is effective for neutron and gamma-ray shielding was newly adopted. In this report, the design and construction using these shielding concrete are outlined. In September, 1974, Mutsu caused radiation leak during the test, and the cause was found to be the fast neutrons streaming through a gap between the reactor pressure vessel and the primary shielding. The repair works were carried out in the Sasebo Shipyard. The outline of the repair works of the shielding is described. The design condition for the shielding, the design standard for the radiation dose outside and inside the ship, the method of shielding analysis and the performance required for shielding concrete are reported. The selection of materials, the method of construction and mixing ratio, the evaluation of the soundness and properties of concrete, and the works of placing the shielding concrete are outlined. (Kako, I.)

  4. Shielding repair and comprehensive safety inspection of the nuclear-powered ship Mutsu

    International Nuclear Information System (INIS)

    Takada, Etsuo

    1982-01-01

    Eight years after the radiation leakage accident, the nuclear-powered ship Mutsu returned again to its home port Ominato. During the period, for four years, the n.s. Mutsu was subjected to shielding repair and comprehensive inspection at Sasebo port. In the future, the ship will start on experimental navigation after its functional and power-up tests. The works of shielding repair and the comprehensive inspection with subsequent repair are described in technical aspects. The basic policy of the repair was two points, i.e. the usage of shielding materials excellent in shielding capacity, less in radioactivation and enduring operating temperature, and structural strength resisting ship-hull acceleration, shock and vibration, enabling easy maintenance and inspection. Comprehensive inspection was made on not only machinery integrity but also the design itself. (Mori, K.)

  5. Propulsion of space ships by nuclear explosion

    Science.gov (United States)

    Linhart, J. G.; Kravárik, J.

    2005-01-01

    Recent progress in the research on deuterium-tritium (D-T) inertially confined microexplosions encourages one to reconsider the nuclear propulsion of spaceships based on the concept originally proposed in the Orion project. We discuss first the acceleration of medium-sized spaceships by D-T explosions whose output is in the range of 0.1 10 t of TNT. The launching of such a ship into an Earth orbit or beyond by a large nuclear explosion in an underground cavity is sketched out in the second section of the paper, and finally we consider a hypothetical Mars mission based on these concepts. In the conclusion it is argued that propulsion based on the Orion concept only is not the best method for interplanetary travel owing to the very large number of nuclear explosion required. A combination of a super gun and subsequent rocket propulsion using advanced chemical fuels appears to be the best solution for space flights of the near future.

  6. Port entry of nuclear ships differences, procedures and conditions

    International Nuclear Information System (INIS)

    McMichael, D.; Bianchi, H.

    1978-01-01

    There are about 250 nuclear propelled ships, only 2 of them are merchant ships: the US freighter Savannah and the bulk carrier Otto Hahn of the Federal Republic of Germany. This paper is restricted to the experience with both of these ships, showing partly similar and partly different procedures for port entry. They have called at 107 ports in 40 countries. The Savannah was operated in the periods from 1962 - 1971 and the Otto Hahn is still in operation. The endeavours of the OECD and IMCO to review and to harmonize international rules for nuclear merchant ships should be supported and continued

  7. The matter of probability controlling melting of nuclear ship reactor

    International Nuclear Information System (INIS)

    Pihowicz, W.; Sobczyk, S.

    2008-01-01

    In the first part of this work beside description of split power, power of radioactivity disintegration and afterpower and its ability to extinguish, the genera condition of melting nuclear reactor core and its detailed versions were described. This paper also include the description of consequences melting nuclear reactor core both in case of stationary and mobile (ship) reactor and underline substantial differences. Next, fulfilled with succeed, control under melting of stationary nuclear reactor core was characterized.The middle part describe author's idea of controlling melting of nuclear ship reactor core. It is based on: - the suggestion of prevention pressure's untightness in safety tank of nuclear ship reactor by '' corium '' - and the suggestion of preventing walls of this tank from melting by '' corium ''. In the end the technological and construction barriers of the prevention from melting nuclear ship reactor and draw conclusions was presented. (author)

  8. Noise test system of rotating machinery in nuclear power station based on microphone array

    Science.gov (United States)

    Chang, Xincai; Guan, Jishi; Qi, Liangcai

    2017-12-01

    Rotating machinery plays an important role in all walks of life. Once the equipment fails, equipment maintenance and shutdown will cause great social harm and economic losses. Equipment safety operations at nuclear power stations have always been of top priority. It is prone to noise when the equipment is out of order or aging. Failure to find or develop equipment at the initial stage of equipment failure or ageing will pose a serious threat to the safety of the plant’s equipment. In this paper, sound imaging diagnosis technology is applied as a supplementary method to the condition monitoring and diagnosis system of rotating machinery in nuclear power stations. It provides a powerful guarantee for the condition monitoring and fault diagnosis of rotating machinery in nuclear power stations.

  9. State of the Japanese nuclear research ship MUTSU

    International Nuclear Information System (INIS)

    Lettnin, H.

    1981-01-01

    A short introductory comment of the German-Japanese cooperation on the field of nuclear ship propulsion is given, which since several years had led to the development of a nuclear propelled containership with 80 000 shp. Against this background the cooperation with the Japanese was renewed for checking the shield modification of NS MUTSU by GKSS. Before the modification of the shielding is dealt with in more detail the design concept of ship and reactor plant of the vessel is presented. The observed defects in the shielding during the nuclear commissioning of the vessel are discussed as well as the rebuilding concept of the changed shielding incl. the shielding calculations. The constructive modifications have led to reconsiderations of safety aspects for ship and reactor. Finally a short description of the repair site in Sasebo is given and an outlook on the nuclear ship development in Japan. (orig.) [de

  10. Present state of Japan Nuclear Ship Development Agency

    International Nuclear Information System (INIS)

    Takada, Yoshio

    1981-01-01

    The Japan Nuclear Ship Development Agency held the annual report meeting on April 8, 1981. The main contents were the plan of research and development of nuclear ships hereafter, the present state of the repair works for the nuclear ship ''Mutsu'', the progress of the selection of the new home port and others. In the last year, the function of research was given to the Agency by the revision of the related law. The full-scale repair works for Mutsu were started in August, 1980, and various equipments and shields in the containment vessel and the upper shields of the containment vessel have been removed. Subsequently, new shields are being installed. According to the report by the committee of nuclear ship research and development, the development of Mutsu, which is valuable as the experimental ship, is continued. Moreover, it is proposed to do the research and development of an improved marine nuclear plant for the purposes of securing the economic efficiency, the proving of the reliability of nuclear merchant ships, and the establishment of safety. As the home port for Mutsu, the new port will be constructed on the open sea side in Aomori Prefecture, and as a candidate, Sekine beach in Mutsu City was named. Till the completion of the new home port, Mutsu will be berthed in Ominato home port. The conditions for entering and berthing in Ominato port will be decided later. (Kako, I.)

  11. Annual report of Japan Nuclear Ship Development Agency, 1980

    International Nuclear Information System (INIS)

    1981-01-01

    Japan Nuclear Ship Development Agency executed the works centering around the repair of shielding and the general inspection on safety of the nuclear-Ship Mutsu in the fiscal year 1980. On the other hand, the law revising the law concerning Japan Nuclear Ship Development Agency was enforced, and the Agency was entitled to carry out the research and investigation required for the development of new nuclear ships. As for the repair of reactor shielding, the alteration of the reactor installation was permitted in November, 1979, and the design and the method of construction were approved in August, 1980. The preparatory works were carried out from April to August, 1980, prior to the main works. The repair works were started in August, and the new shields have been manufactured, while the existing shields and the equipments in the containment vessel were removed. The completed new shields have been installed successively in the containment vessel. It was confirmed that there is no problem in the safety of the nuclear ship Mutsu, as the result of the general inspection on safety completed in June, 1980. Maintenance works were carried out for the Mutsu and the normally berthing port. The periodic measurement of radiation dose rate, the selection of the new normally berthing port, the research and development of nuclear ships and others are also reported. (Kako, I.)

  12. Fiscal 1978 annual report of Japan Nuclear Ship Development Agency

    International Nuclear Information System (INIS)

    1979-01-01

    In October, 1978, the nuclear ship Mutsu was moved to Sasebo Port from Ominato Port for shield repair and comprehensive safety check-up and repair; and this was a long-standing problem for the ship. In face of a new energy age, Japan Nuclear Ship Development Agency is endeavoring to bring up the nuclear ship technology in Japan to the top level in the world by successfully completing the n.s. Mutsu through perfect safety and reliability. For Japan, which is a leading country of shipbuilding and merchant shipping, the development of nuclear ships is extremely important. On the activities of the agency from April, 1978, to March, 1979, the following matters are described: safety check and shielding repair of the n.s. Mutsu; Maintenance of the n.s. Mutsu at Ominato and Sasebo ports and its sailing to Sasebo port; works at Sasebo port before and after the arrival of the n.s. Mutsu; maintenance works of the Mutsu facilities at Ominato port; governmental formalities for permission and approval; training of ship crew; administrative works. (J.P.N.)

  13. State of the Japanese nuclear research ship MUTSU

    International Nuclear Information System (INIS)

    Lettnin, H.

    1981-01-01

    A short introductary comment of the German-Japanese cooperation on the field of nuclear ship propulsion is given, which since several years had led to the development of a nuclear propelled containership with 80 000 shp. Against this background the cooperation with the Japanese was renewed for checking the shield modification of NS MUTSU by GKSS. Before the modification of the shielding is dealt with in more detail the design concept of ship and reactor plant of the vessel is presented. The observed defects as well as the rebuilding concept of the changed shielding incl. the shielding calculations. The constructive modifications have led to reconsiderations of safety aspects for ship and reactor. Finally a short description of the repair site in Sasebo is given and an outlook on the nuclear ship development in Japan. (orig.) [de

  14. Nuclear merchant ship propulsion. The present status in the UK

    International Nuclear Information System (INIS)

    Kinsey, R.P.

    1976-01-01

    The latest report of the Nuclear Ship Stearing Group which deals with three important aspects; economic assessments, international safety and operating procedures for nuclear ships, and the industrial capability of the UK shipbuilding and nuclear industries, is discussed. The integral design concept for a pressurised water reactor for use as a marine reactor is considered. The operational safety aspects of such reactors and of the attendant refuelling facilities are discussed. U.K. capability in the whole nuclear merchant ship propulsion project is considered; reference being made to the design and construction of small PWR reactors, the development, design and supply of the nuclear propulsion unit, financial aspects, and the requirement for cooperation between industrial interests and governmental research units. (U.K.)

  15. Collision simulations of an exclusive ship of spent nuclear fuels

    International Nuclear Information System (INIS)

    Kitamura, Ou; Endo, Hisayoshi

    2000-01-01

    Exclusive ships for sea transport of irradiated nuclear fuels operating in Japanese territorial waters are required to be built with the special hull structure against collision. To comply with the official notice 'KAISA No. 520' issued by the Ministry of Transport, the side structure of any such exclusive ship must be designed to secure the specified energy absorption capability based on Minorsky's ship collision model. The Shipbuilding Research Association of Japan (JSRA) has studied the safety in sea transport of nuclear fuels intermittently for these several decades. Recently, the adoption of finite element method has made detailed collision analyses practicable. Since 1998, the regulation research panel No. 46 of JSRA has carried out a series of finite element collision simulations in order to estimate the realistic damage to a typical exclusive ship of spent nuclear fuels. The expected structural responses, global motions and energy absorption capabilities of both colliding and struck ships during collision were investigated. The results of the investigations have shown that the ship is very likely to withstand the collision even with one of the world's largest ship. This is due mainly to her hull structure specially strengthened beyond the crushing strength of the colliding bow structures. (author)

  16. Nuclear shipping and waste disposal cost estimates

    International Nuclear Information System (INIS)

    Hudson, C.R. II.

    1977-11-01

    Cost estimates for the shipping of spent fuel from the reactor, shipping of waste from the reprocessing plant, and disposal of reprocessing plant wastes have been made for five reactor types. The reactors considered are the light-water reactor (LWR), the mixed-oxide-fueled light-water reactor (MOX), the Canadian deuterium-uranium reactor (CANDU), the fast breeder reactor (FBR), and the high-temperature gas-cooled reactor (HTGR). In addition to the cost estimates, this report provides details on the bases and assumptions used to develop the cost estimates

  17. An NEA contribution to the safety of nuclear ships

    International Nuclear Information System (INIS)

    Stadie, K.B.; Thomas, R.A.

    1978-01-01

    The civil nuclear ships put into service so far have performed well and have an excellent safety record. There are substantial differences however between these experimental vessels and a free-ranging fleet of nuclear-powered merchant ships development of which will require satisfactory solutions to certain technical questions, an international consensus on safety requirements, and some form of international arrangement for regulation and surveillance. The paper describes the work sponsored by the OECD Nuclear Energy Agency in this field, and points out areas where future effort should be focussed, as a prerequisite for such future developments

  18. Prospects for applications of ship-propulsion nuclear reactors

    International Nuclear Information System (INIS)

    Mitenkov, F.M.

    1994-01-01

    The use of ship-propulsion nuclear power reactors in remote areas of Russia is examined. Two ship reactors were analyzed: the KLT-40, a 170 MW-thermal reactor; and the KN-3, a 300 MW-thermal reactor. The applications considered were electricity generation, desalination, and drinking water production. Analyses showed that the applications are technically justified and could be economically advantageous. 5 refs., 9 figs., 1 tab

  19. Annual report of Japan Nuclear Ship Development Agency

    International Nuclear Information System (INIS)

    1978-01-01

    Works performed in fiscal 1977 concerning the nuclear ship 'Mutsu' are reported: safety inspection and shielding repair of the Mutsu; maintenance of the Mutsu and its port facilities; permissions by law; P.R. etc. on its prospective repair port; ship crew training; and, organization etc. Safety inspection of the Mutsu was carried out on its both hardware and software. For repair, a final basic design was started. Without ship operation, the Mutsu's hull, reactor plant, etc. and port facilities were subjected to maintenance works. P.R. works on its repair port concentrated on understanding of the local people. (Mori, K.)

  20. Aircraft, ships, spacecraft, nuclear plants and quality

    International Nuclear Information System (INIS)

    Patrick, M.G.

    1984-05-01

    A few quality assurance programs outside the purview of the Nuclear Regulatory Commission were studied to identify features or practices which the NRC could use to enhance its program for assuring quality in the design and construction of nuclear power plants. The programs selected were: the manufacture of large commercial transport aircraft, regulated by the Federal Aviation Administration; US Navy shipbuilding; commercial shipbuilding regulated by the Maritime Administration and the US Coast Guard; Government-owned nuclear plants under the Department of Energy; spacecraft under the National Aeronautics and Space Administration; and the construction of nuclear power plants in Canada, West Germany, France, Japan, Sweden, and the United Kingdom

  1. Annual report of the Japan Nuclear Ship Development Agency, 1979

    International Nuclear Information System (INIS)

    1980-01-01

    The pending repair work of the shielding of the nuclear ship ''Mutsu'' was started at long last, and the development of nuclear ships in Japan is to be accelerated again. The Agency intends to exert more efforts to execute the repair of shielding and the works of the general inspection on safety for ''Mutsu'' rapidly and surely and to attain the expected objective. The energy situation in the world is still in confusion, and all countries, advanced and developing alike, are carrying out the researches to develop and utilize substitute energy. Especially large expectation is entertained in atomic energy which can fill the energy gap for the time being, and the policy to promote positively the improvement of safety and the development of the application to new fields is being taken. In such situation, the Atomic Energy Commission clarified the policy to positively promote the research and development on nuclear ships including the design of new nuclear reactors considering their necessity to relax the restriction of energy supply. As for the ''Mutsu'', the AEC insists that the repair should be completed and the operation test must be executed urgently. Concerning the organization for the research and development, the Agency is to undertake the solution of the pending problems related to the ''Mutsu'', and also is required to have the functions of the research and development aiming at the improvement of the economy and reliability of nuclear ships. In this report, the works of the Agency carried out in 1979 are described. (Kako, I.)

  2. Crash testing of nuclear fuel shipping containers

    International Nuclear Information System (INIS)

    Jefferson, R.M.; Yoshimura, H.R.

    1977-08-01

    In an attempt to understand the dynamics of extra severe transportation accidents and to evaluate state-of-the-art computational techniques for predicting the dynamic response of shipping casks involved in vehicular system crashes, the Environmental Control Technology Division of ERDA undertook a program with Sandia to investigate these areas. The program encompasses the following distinct major efforts. The first of these utilizes computational methods for predicting the effects of the accident environment and, subsequently, to calculate the damage incurred by a container as the result of such an accident. The second phase involves the testing of 1 / 8 -scale models of transportation systems. Through the use of instrumentation and high-speed motion photography the accident environments and physical damage mechanisms are studied in detail. After correlating the results of these first two phases, a full scale event involving representative hardware is conducted. To date two of the three selected test scenarios have been completed. Results of the program to this point indicate that both computational techniques and scale modeling are viable engineering approaches to studying accident environments and physical damage to shipping casks

  3. Crash testing of nuclear fuel shipping containers

    International Nuclear Information System (INIS)

    Jefferson, R.M.; Yoshimura, H.R.

    1977-12-01

    In an attempt to understand the dynamics of extra severe transportation accidents and to evaluate state-of-the-art computational techniques for predicting the dynamic response of shipping casks involved in vehicular system crashes, the Environmental Control Technology Division of ERDA undertook a program with Sandia to investigate these areas. This program, which began in 1975, encompasses the following distinct major efforts. The first of these utilizes computational methods for predicting the effects of the accident environment and, subsequently, to calculate the damage incurred by a container as the result of such an accident. The second phase involves the testing of 1 / 8 -scale models of transportation systems. Through the use of instrumentation and high-speed motion photography, the accident environments and physical damage mechanisms are studied in detail. After correlating the results of these first two phases, a full scale event involving representative hardware is conducted. To date two of the three selected test scenarios have been completed. Results of the program to this point indicate that both computational techniques and scale modeling are viable engineering approaches to studying accident environments and physical damage to shipping casks

  4. Review of the total system related to operation of nuclear-powered ship

    International Nuclear Information System (INIS)

    Takamasa, Tomoji; Miyashita, Kunio

    2000-01-01

    It is essential to establish a marine reactor having excellent safety and reliability, which is capable of competing economically with conventional ships, and which can be accepted by international society, in order to be prepared for practical application of future nuclear-powered ships. For this purpose, it is important not only to demonstrate a marine reactor using a model or test device to simulate actual operation, but also to establish the environmental requirements for operation of a nuclear-powered ship, such as safety standards that are operationally and internationally common for ships, and to establish a repair base for nuclear-powered ships. Systems research for the practical application of nuclear-powered ships was conducted for five years, fiscal years 1992 through 1996, by a group in the Japan Atomic Energy Research Institute (JAERI), under the project title 'Review of the total system related to operation of nuclear-powered ships.' The project sought to summarize requirements for the practical application of nuclear-powered ships from the standpoint of the need side, e.g., what nuclear-powered ships will be requested, and what functions will be provided under the expected future social environment; to show a complete system concept for the operation of nuclear-powered ships; and to clarify the situations creating demand for nuclear-powered ships, as well as the system and environmental conditions to be established for operation of practical nuclear-powered ships. Study considerations included the size of the operation system for a nuclear-powered ship, a scenario for introducing a nuclear-powered container ship, and economic evolution from the effects on the whole shipping system, based on container ships, of introducing a nuclear-powered ship. The results of these considerations were made the framework for constructing an entire system and evaluating its economy. The treatment and disposal of radioactive waste from a nuclear-powered ship, and the

  5. The decommissioning plan of the Nuclear Ship MUTSU

    International Nuclear Information System (INIS)

    Adachi, M.; Matsuo, R.; Fujikawa, S.; Nomura, T.

    1995-01-01

    This paper describes the review about the decommissioning plan and present state of the Nuclear Ship Mutsu. The decommissioning of the Mutsu is carried out by Removal and Isolation method. The procedure of the decommissioning works is presented in this paper. The decommissioning works started in April, 1992 and it takes about four years after her last experimental voyage. (author)

  6. Development of Nuclear ship Engineering Simulation SYstem (NESSY)

    International Nuclear Information System (INIS)

    Kusunoki, Tsuyoshi; Kyouya, Masahiko; Takahashi, Teruo; Kobayashi, Hideo; Ochiai, Masa-aki; Hashidate, Kouji.

    1993-11-01

    NESSY has been developed for design studies of advanced marine reactors as a part of nuclear ship research and development since 1987. Engineering simulation model of the Mutsu, which is the first nuclear ship in Japan, was completed in March of 1993. In this report we concentration on detail description of softwares for Mutsu modeling. The aims of development of NESSY are as follows; (1) Assessment and confirmation on plant performance of an advanced marine reactor in each step of nuclear ship design (2) Development of abnormality diagnosis system and operator support system as a part of enhanced automization study, and study of human interface with hardware The characteristics of NESSY are the followings. (1) Total engineering simulation system simulate simultaneously ship motions, propulsion system behavior, and nuclear plant behavior under given weather and sea conditions. (2) Models based on physical theory as far as possible. (3) The simulator has high extensibility and flexibility. It is able to apply to other reactors, as the simulation model consists of the part of basic model and the part of plant data which are easy to change. After completion of Mutsu modeling, we are planning to utilize this system as one of design tools for an advanced marine reactor. (author)

  7. Dry cask handling system for shipping nuclear fuel

    International Nuclear Information System (INIS)

    Jones, C.R.

    1975-01-01

    A nuclear facility is described for improved handling of a shipping cask for nuclear fuel. After being brought into the building, the cask is lowered into a tank mounted on a transporter, which then carries the tank into a position under an auxiliary well to which it is sealed. Fuel can then be loaded into or unloaded from the cask via the auxiliary well which is flooded. Throughout the procedure, the cask surface remains dry. (U.S.)

  8. Decommissioning plan of the nuclear-powered ship 'Mutsu'

    International Nuclear Information System (INIS)

    1992-01-01

    The nuclear-powered ship 'Mutsu' is to be decommissioned at Sekinehama Port immediately after finishing the experimental voyage based on the 'Fundamental plan on the research required for the development of nuclear ships in Japan Atomic Energy Research Institute' decided in March, 1985. The decommissioning plan which determines the methods of the works regarding the decommissioning and others is as follows. In order to utilize the ship hull of Mutsu, the reactor room including the reactor and shielding is removed in a lump, and the removal and isolation method of preserving it as it is on land is adopted. The measures for environment preservation and ensuring the safety of residents are taken, and the sufficient work control is carried out for preventing accidents and reducing the radiation exposure of workers. The ship is used as the ship with ordinary propulsion system for ocean research and the research and development of marine reactors. The utilization of Sekinehama and Ominato facilities is investigated. The reactor room removed from Mutsu is exhibited to public, being preserved safely in a building. (K.I.)

  9. New start of nuclear-powered ship 'Mutsu'. 2. On decommissioning works

    International Nuclear Information System (INIS)

    Matsuo, Ryusuke

    1996-01-01

    It was decided that 'Mutsu' is decommissioned immediately after the finish of the experimental voyage in the fundamental plan. Therefore, Nuclear-powered Ship Decommissioning Department was organized in Japan Atomic Energy Research Institute in 1992, and the investigation was begun on the measures to abolish the reactor facilities of 'Mutsu'. The fundamental plan was decided to adopt the removal and isolation method for the reactor room including the reactor and shields, to use the ship as the conventional propulsion ocean research ship, and to exhibit the removed reactor chamber under proper control. The required technical assessment and safety examination were carried out based on this fundamental plan. The technical feasibility studies were carried out on the safety of placing 'Mutsu' on a semisubmersible barge, the safety of the cutting works of the hull, the safety of a floating crane, and the safety at the time of accidents. Taking-out of fuel assemblies, the removal works of machinery and equipment in the reactor auxiliary machine room and others, the removal and transport works of the reactor room in a lump, the construction works of the preservation building, and the safety control on the decommissioning works are described. (K.I.)

  10. Structural analysis of aircraft impact on a nuclear powered ship

    International Nuclear Information System (INIS)

    Dietrich, R.

    1976-01-01

    As part of a general safety analysis, the reliability against structural damage due to an aircraft crash on a nuclear powered ship is evaluated. This structural analysis is an aid in safety design. It is assumed that a Phantom military jet-fighter hits a nuclear powered ship. The total reaction force due to such an aircraft impact on a rigid barrier is specified in the guidelines of the Reaktor-Sicherheitskommission (German Safety Advisory Committee) for pressurized water reactors. This paper investigates the aircraft impact on the collision barrier at the side of the ship. The aircraft impact on top of the reactor hatchway is investigated by another analysis. It appears that the most unfavorable angle of impact is always normal to the surface of the collision barrier. Consequently, only normal impact will be considered here. For the specific case of an aircraft striking a nuclear powered ship, the following two effects are considered: Local penetration and dynamic response of the structure. (Auth.)

  11. The United States nuclear merchant ship program

    International Nuclear Information System (INIS)

    Maynard, E.V.

    1978-01-01

    The issues of financial protection contemplate appropriate financing to permit construction of the involved vessels. In addition, the licensing process will require a demonstrated ability for financial response in the event of injury to persons or damage to property. Since the thrust in the United States is to use the Price-Anderson framework for Insurance and Indemnity, much attention is devoted to this legislation. The pre-existing regime is related to the distinguishing requirements of the Maritime field with proposals being advanced to more nearly parallel the insurance coverage philosophy of Europe, i.e., to utilize insurance pools for the nuclear risks and utilize the conventional insurance market for non-nuclear risks. Public affairs issues impact heavily on legislation efforts and thusly become significant in developing a program for Financial Protection

  12. Fuel element shipping shim for nuclear reactor

    International Nuclear Information System (INIS)

    Gehri, A.

    1975-01-01

    A shim is described for use in the transportation of nuclear reactor fuel assemblies. It comprises a member preferably made of low density polyethylene designed to have three-point contact with the fuel rods of a fuel assembly and being of sufficient flexibility to effectively function as a shock absorber. The shim is designed to self-lock in place when associated with the fuel rods. (Official Gazette)

  13. Training of operating personnel for nuclear ships

    International Nuclear Information System (INIS)

    Lakey, J.R.A.; Gibbs, D.C.C.

    1983-01-01

    Training for Nuclear Power Plant Operators is provided by the Royal Navy in support of the Nuclear Submarine Programme which is based on the Pressurised Water Reactor. The Royal naval college has 21 years of experience in this training field in which the core is the preparation of graduate electro-mechanical engineers to assume the duties of marine engineer in command of a team of supporting Engineer Officers of the Watch and Fleet Chief Petty Officers. The paper describes the training programme and shows how it is monitored by academic, professional and naval authorities and indicates the use of feedback from the user. The lynch pin of the programme is a post-graduate diploma course in Nuclear Reactor Technology attended by graduates after gaining some practical experience at sea. The course which is described in detail makes use of simplified simulators and models to develop the principles, these are applied on the JASON Training Reactor with the emphasis on in-core experiments demonstrating reactivity effects and instrumentation interpretation. The training programme provides for interaction between academic education, practical experience, applied education, full plant simulation training and on-the-job training in which boards or examinations have to be successfully passed at each stage. (author)

  14. The law for Japan Nuclear Ship Research and Development Agency

    International Nuclear Information System (INIS)

    1981-01-01

    The agency intends to develop and research nuclear ships according to the principles of the atomic energy act and contribute to advance the utilization of atomic energy and the development of ship building and marine transportation. It shall be a juridical person, and its main office shall be in Tokyo Metropolis. Its capital shall be the sum of 100 million yen paid in by the government and the amounts invested by persons other than the government at the time of establishment. The agency may increase, if necessary, its capital with the approval of the competent minister. It shall define the following matters by its articles: object, name, the place of the office, the matters concerning capital, investments and assets, executives, advisers and meeting, business and its execution, finance and accounting, public announcement and the change of the articles. Its executives consist of a chief director, a representative director, directors not more than 3 and an auditor. The chief director and the auditor are appointed by the competent minister after hearing opinions of the Atomic Energy Commission. The representative and other directors are determined by the chief director with approval of the competent minister. The term of office is four years for the chief director, the representative director and other directors, and two years for the auditor. The agency performs business, such as study and research necessary for the development of nuclear ships, design, building and operation of these ships and the training of crew for these nuclear ships, etc. It is under the superintendence of the competent minister. (Okada, K.)

  15. Shipping

    NARCIS (Netherlands)

    Wijnolst, N.; Wergeland, T.

    1996-01-01

    Shipping is a multi-faceted industry which is rather complex to define from an academic point of view. This book attempts to grasp these complexities and provide the reader with an overview of the main topics and terminology in shipping. The book is based on material from our courses in shipping at

  16. NS OTTO HAHN - the first German nuclear ship

    International Nuclear Information System (INIS)

    1981-01-01

    The NS OTTO HAHN is the first and only European nuclear propelled cargo and research vessel. She entered service in 1968 and was operated for 11 years without any technical failure. The essential experience and know-how about the nuclear propulsion unit is available now. Therefore the ship was decommissioned in 1979. Until the end of 1981 all activated and contaminated components will be removed and decontaminated. The ship can then be released for conventional utilization. In this book the NS OTTO HAHN is described in detail and the experiences of operation as well as research and development activities are reported. All earlier publications of GKSS on the same subject are listed. (orig.) [de

  17. Revised experimental program on the nuclear ship 'Mutsu'

    International Nuclear Information System (INIS)

    Mori, Yuichi

    1985-01-01

    The experimental program on the nuclear ship ''Mutsu'' has been revised by the Government. And, the responsible organization for n. s. Mutsu was turned to Japan Atomic Energy Research Institute (JAERI) from Japan Nuclear-ship Development Agency. The revised, new experimental program is as follows. (1) Experimental navigation of n. s. Mutsu is made with the already loaded 1st reactor core for about one year. (2) The mooring port for n. s. Mutsu is in a minimum scale. (3) Upon termination of the experimental navigation, n. s. Mutsu is immediately decommissioned. (4) Power-up test and experimental navigation of n. s. Mutsu are made in fiscal 1989 to 1990. The policy of research and development with n. s. Mutsu and the works assigned to JAERI with n. s. Mutsu are described. (Mori, K.)

  18. The future of nuclear propulsion in merchant ships

    International Nuclear Information System (INIS)

    Young, R.T.

    1977-01-01

    Attention is paid to a number of issues which must be resolved before any firm commitment to build a commercial nuclear powered ship will be made. Basically, these can be grouped into three major problem areas: first, economic; second, indemnification and liability; and third, port entry and international clearance. It is concluded that there is reason for guarded optimism, as concerted efforts to solve the important issues are now underway. Some examples are briefly discussed

  19. Revision of the basic plans of the first nuclear-powered ship development

    International Nuclear Information System (INIS)

    1978-01-01

    Along with the law for Japan Nuclear Ship Development Agency, the basic plans of development of the first nuclear-powered ship have been revised. After explaining the basic policy concerning the matter, the development program is described as follows: ship type/kind, nuclear power plant, construction, training of ship crew, experimental voyage, compilation of the development results, and works after the experimental voyage. The first nuclear-powered ship of about 8,000 tons gross tonnage, 10,000 horsepower main engine output, and about 16 knots, sea speed will be the ship for special cargo transport and crew training. A pressurized water reactor is used for the power plant. Following the repair of shielding and the overall inspection of safety, the ship is to be completed as early as possible. After completion of the ship, its experimental voyage will be carried out, aiming at the aspects of operational familiarization, ship performance, reliability, port call experience, etc. (Mori, K

  20. The law for Japan Nuclear Ship Development Agency

    International Nuclear Information System (INIS)

    1977-01-01

    The Agency aims at developing nuclear-ships according to the priciples of the Atomic Energy Basic Law to promote the uses of atomic energy and help the progress of shipbuilding and marine transportation. The capital is 100 million yen plus the funds invested by the persons other than the government. The investment certificates are issued for the funds invested. The officers consist of the chief director, the representative director, not more than three directors and one auditor. The chief director and the auditor are appointed by the competent minister (the Prime Minister and the Minister of Transport) consulting with the Atomic Energy Commission. The representative director and directors are nominated by the chief director with approval of the competent minister. The scope of business includes the undertakings concerning nuclear ships, such as; the planning, building and operation; the training of the crew; the research and study; popularization of the results of such operations, etc. These activities are to be made in accordance with the basic program of nuclear-ship development determined by the competent minister. A chapter is dedicated to the finance and accounting, which includes provisions on the business year, authorization of the business program and others, the disposition of the business program and others, the disposition of profits and losses, and loans, etc. The Agency is supervised by the competent minister. (Okada, K.)

  1. A novel nuclear-powered propulsion system for ship

    International Nuclear Information System (INIS)

    Liu Tao; Han Weishi

    2003-01-01

    A novel nuclear-powered propulsion system for ship is presented in this paper. In this system, a minitype liquid sodium-cooled reactor is used as power; alkali-metal thermal-to-electric conversion (AMTEC) cells are utilized to transform the heat energy to electric energy and superconducting magneto-hydrodynamic (MHD) work as propulsion. This nuclear-powered propulsion system has great advantages in low noise, high speed, long survivability and simple manipulation. It has great significance for the development of propulsion system. (author)

  2. Application of the international guidelines for machinery breakdown prevention at nuclear power plants

    International Nuclear Information System (INIS)

    Wendland, W.G.

    2001-01-01

    For more than forty years as a specialized branch of the worldwide insurance industry, the nuclear insurance pools have underwritten property damage protection for nuclear facilities throughout the world. At power plants insured by the pools, an enviable record of operational safety has been attained. Nevertheless, electrical and mechanical equipment does break down occasionally. Although these failures do not necessarily compromise nuclear safety, they can cause significant damage to equipment, leading to a considerable loss of generating revenue and causing sizeable insurance losses. Since insurance companies have a large financial stake in nuclear power plants, their goal is to minimize insurance losses, including the failure of systems and equipment and ensuing consequential damages. To ensure that the insurance risk is properly underwritten, insurance companies analyze loss information, develop loss prevention guidelines and focus loss control activities on those areas where insurance risk is most significant. This paper provides a chronology of the development of the ''International Guidelines for Machinery Breakdown Prevention at Nuclear Power Plants'' and describes the results of insurance inspections conducted using these guidelines. Included is a summary of guideline content and of insurance loss experience between 1962 and 1999. (author)

  3. Impact analysis of spent nuclear fuel shipping casks

    International Nuclear Information System (INIS)

    Huerta, M.; Dennis, A.W.; Yoshimura, R.H.

    1978-07-01

    A presentation made at the CUBE (Computer Use By Engineers) Symposium, October 1976, in Albuquerque, New Mexico is summarized. A full-scale testing program involving impact tests of spent-nuclear-fuel shipping systems is described. This program is being conducted by Sandia Laboratories for the Environmental Control Technology Division of the U.S. Energy Research and Development Administration. The analytical and scale modeling techniques being employed to predict the response of the full-scale system in the very severe impact tests are described. The analytical techniques include lumped parameter modeling of the vehicle and cask system and finite modeling of isolated shipping casks. Some preliminary results from the mathematical analyses and scale model tests demonstrate close agreement between these two techniques. Scale models of the systems are also described and some results presented

  4. Methods for estimating risks to nuclear power plants from shipping

    International Nuclear Information System (INIS)

    Walker, D.H.; Hartman, M.G.; Robbins, T.R.

    1975-01-01

    Nuclear power plants sited on land near shipping lanes or offshore can be exposed to potential risks if there is nearby ship or barge traffic which involves the transport of hazardous cargo. Methods that have been developed for estimating the degree of risk are summarized. Of concern are any accidents which could lead to a release or spill of the hazardous cargo, or to an explosion. A probability of occurrence of the order of 10 -7 per year is a general guideline which has been used to judge whether or not the risk from hazards created by accidents is acceptable. This guideline has been followed in the risk assessment discussed in this paper. 19 references

  5. Conservation of proteo-lipid nuclear membrane fusion machinery during early embryogenesis.

    Science.gov (United States)

    Byrne, Richard D; Veeriah, Selvaraju; Applebee, Christopher J; Larijani, Banafshé

    2014-01-01

    The fusogenic lipid diacylglycerol is essential for remodeling gamete and zygote nuclear envelopes (NE) during early embryogenesis. It is unclear whether upstream signaling molecules are likewise conserved. Here we demonstrate PLCγ and its activator SFK1, which co-operate during male pronuclear envelope formation, also promote the subsequent male and female pronuclear fusion. PLCγ and SFK1 interact directly at the fusion site leading to PLCγ activation. This is accompanied by a spatially restricted reduction of PtdIns(4,5)P2. Consequently, pronuclear fusion is blocked by PLCγ or SFK1 inhibition. These findings identify new regulators of events in the early embryo and suggest a conserved "toolkit" of fusion machinery drives successive NE fusion events during embryogenesis.

  6. Shipping

    OpenAIRE

    Wijnolst, N.; Wergeland, T.

    1996-01-01

    Shipping is a multi-faceted industry which is rather complex to define from an academic point of view. This book attempts to grasp these complexities and provide the reader with an overview of the main topics and terminology in shipping. The book is based on material from our courses in shipping at the universities in Delft and Bergen. As with our lectures, we draw upon quite a va ried material, from research studies at a high academic level to lower level student work and purely descriptive ...

  7. Ship nuclear power device of cable aging management

    International Nuclear Information System (INIS)

    Wei Hua; Chen Miao; Chen Tao

    2012-01-01

    Cable for marine nuclear power plant continuous delivery of electrical energy. Cable is mostly in the high temperature and strong radiation and harsh working environment, and can not be replaced in the lifetime This should be the cable aging management methods through research, maintenance and repair program to provide a scientific basis. Cable aging management approach for a number of different levels of cable management at different levels, relying on computers and other modern tools, the use of information management database software maintenance of the cable through the science of aging control. Cable Aging Management including the scope of cable aging management, classification management basis and used for different levels of management supervision and implementation of means testing approach. Application of the ship that has the operational management science, both planned maintenance to improve the science, but also improves the efficiency of aging management. This management method can be extended to nuclear power plants of cable aging management. (authors)

  8. Shield design development of nuclear propulsion merchant ship

    International Nuclear Information System (INIS)

    Tanaka, Yoshihisa

    1975-01-01

    Shielding design both in Japan and abroad for nuclear propulsion merchant ships is explained, with emphasis on the various technological problems having occurred in the shield design for one-body type and separate type LWRs as conceptual design. The following matters are described: the peculiarities of the design as compared with the case of land-based nuclear reactors, problems in the design standards of shielding, the present status and development of the design methods, and the instances of the design; thereby, the trends of shielding design are disclosed. The following matters are pointed out: Importance of the optimum design, of shielding, significance of radiation streaming through large voids, activation of the secondary water in built-in type steam generators, and the need of the guides for shield design. (Mori, K.)

  9. RETRAN safety analyses of the nuclear-powered ship Mutsu

    International Nuclear Information System (INIS)

    Yoshinori, N.; Ishida, T.; Tanaka, Y.; Yoshiaki, F.

    1983-01-01

    A number of operational transient analyses of the nuclear-powered ship Mutsu have been performed in response to Japanese nuclear safety regulatory concerns. The RETRAN and COBRA-IV computer codes were used to provide a quantitative basis for the safety evaluation of the plant. This evaluation includes a complete loss of load without reactor scram, an excessive load increase incident, and an accidental depressurization of the primary system. The minimum departure from nucleate boiling ratio remained in excess of 1.53 for these three transients. Hence, the integrity of the core was shown to be maintained during these transients. Comparing the transient behaviors with those of land-based pressurized water reactors, the characteristic features of the Mutsu reactor were presented and the safety of the plant under the operational transient conditions was confirmed

  10. Inspection by docking of nuclear-powered ship 'Mutsu'

    International Nuclear Information System (INIS)

    1989-01-01

    Japan Atomic Energy Research Institute carried out the docking and inspection of the nuclear-powered ship 'Mutsu' at Sekinehama Port, Mutsu City, Aomori Prefecture, from the middle of June to late in July, 1989. In this inspection, the Mutsu was mounted on a floating dock off the coast, the dock was towed by tugboats into the port and moored at the pier, and after completing the works in the dock, the dock was towed to the outside of the port, and the Mutsu was launched. The Mutsu was built as a nuclear power experiment ship, and length 130 m, breadth 19 m, depth 13.2 m, design draft at full load 6.9 m, 8242 GT. One PWR of 36 MWt and one steam turbine of 10000 ps are installed, and velocity is 16.5 knots. In September, 1974, after the first criticality, the leak of radioactivity occurred. The repair of shield and general inspection on safety were carried out in Sasebo Shipyard from August, 1980 to August, 1982. Thereafter, the Mutsu stayed in Ominato, but in January, 1988, after the completion of Sekinehama Port, the Mutsu was brought there. The Sekinehama Port, the test and inspection of the Mutsu carried out so far and the plan of hereafter are reported. (K.I.)

  11. Structural analysis of aircraft impact on a nuclear powered ship

    International Nuclear Information System (INIS)

    Dietrich, R.

    1976-01-01

    The paper investigates the aircraft impact on the collision barrier at the side of the ship. The aircraft impact on top of the reactor hatchway is investigated by another analysis. It appears that the most unfavorable angle of impact is always normal to the surface of the collision barrier. Consequently, only normal impact will be considered here. For the specific case of an aircraft striking a nuclear powered ship, the following two effects are considered: Local penetration and dynamic response of the structuure. The local penetration occurs at points where the engines or other rigid objects hit the structure. It is assumed that the aircraft engine is a rigid body projectile and the side wall of the ship is the target. The applied steel penetration formulae for projectiles were empirically derived for military applications, where both the projectile and the target are unlike those of an impact of an aircraft engine. For this reason it is expedient to calculate the upper and the lower limit values of the penetration depths. The results show that the highest penetration depth is less than the sum of all wall thicknesses of the collision barrier. The solution of the dynamic analysis is obtained by using the finite element method. The results are the eigenmodes, the eigenfrequencies, the displacements of the nodes, and the stresses in the applied plane stress elements. It is shown that the maximum stress which only appears in one element is on the same level as the yield stress of the St. 42 steel. The structural analysis shows that the collision barrier is a sufficient safeguard against the perforation of the engine and against the cracking of the structure as a result of the dynamic response to an aircraft impact. (orig./HP) [de

  12. Problems faced by host nations in accepting visits by nuclear powered merchant ships

    International Nuclear Information System (INIS)

    Crancher, D.W.

    1978-01-01

    An international Code of Practice would make a major contribution to the effective regulation of nuclear merchant ships. Ensuring compliance with such a Code would be a significant problem for host nations. An impediment to the development of nuclear shipping is the absence of third party liability provision. There are also problems in host port acceptance into crowded ports and some limitations may be imposed until there is more confidence. There are indications that ship accidents will become the predominant risk and considerably more attention to the problem is required. Waste management need not be a major issue to the acceptance of nuclear merchant ships

  13. Design study of ship based nuclear power reactor

    International Nuclear Information System (INIS)

    Su'ud, Zaki; Fitriyani, Dian

    2002-01-01

    Preliminary design study of ship based nuclear power reactors has been performed. In this study the results of thermohydraulics analysis is presented especially related to behaviour of ship motion in the sea. The reactors are basically lead-bismuth cooled fast power reactors using nitride fuels to enhance neutronics and safety performance. Some design modification are performed for feasibility of operation under sea wave movement. The system use loop type with relatively large coolant pipe above reactor core. The reactors does not use IHX, so that the heat from primary coolant system directly transferred to water-steam loop through steam generator. The reactors are capable to be operated in difference power level during night and noon. The reactors however can also be used totally or partially to produce clean water through desalination of sea water. Due to the influence of sea wave movement the analysis have to be performed in three dimensional analysis. The computation time for this analysis is speeded up using Parallel Virtual Machine (PVM) Based multi processor system

  14. The law for Japan Nuclear Ship Development Agency

    International Nuclear Information System (INIS)

    1978-01-01

    The law prescribes in the 1st chapter the establishment of above mentioned agency as a legal person with its principal office in Tokyo and with the investment of 100 million yens by the government as a part of its capital. The 2nd chapter includes the provisions about officers of the agency, according to them: the agency has a president and a executive director, directors within 3 persons, and a auditor; the president and auditor are to be appointed by the competent Minister after consulting with the Atomic Energy Commission and directors including the executive director should be appointed by the president after receiving the approval of the competent Minister; and terms of their offices are 2 (auditor) to 4 years (others). In the 3rd chapter the business of the agency is defined as to include: the design, construction and operation of nuclear ships; education and training of the crew of those ships; research and studies concerning above listed activities; and others. The 4th chapter prescribes the procedures of finance and accounting of the agency, according to them: the agency's business plan, budget and finance plan should each year be sanctioned by the competent Minister before the beginning of the year; and the financial documents should each year be approved by the Minister after the end of the year. (Matsushima, A.)

  15. Arabidopsis TCP Transcription Factors Interact with the SUMO Conjugating Machinery in Nuclear Foci

    Directory of Open Access Journals (Sweden)

    Magdalena J. Mazur

    2017-11-01

    Full Text Available In Arabidopsis more than 400 proteins have been identified as SUMO targets, both in vivo and in vitro. Among others, transcription factors (TFs are common targets for SUMO conjugation. Here we aimed to exhaustively screen for TFs that interact with the SUMO machinery using an arrayed yeast two-hybrid library containing more than 1,100 TFs. We identified 76 interactors that foremost interact with the SUMO conjugation enzyme SCE1 and/or the SUMO E3 ligase SIZ1. These interactors belong to various TF families, which control a wide range of processes in plant development and stress signaling. Amongst these interactors, the TCP family was overrepresented with several TCPs interacting with different proteins of the SUMO conjugation cycle. For a subset of these TCPs we confirmed that the catalytic site of SCE1 is essential for this interaction. In agreement, TCP1, TCP3, TCP8, TCP14, and TCP15 were readily SUMO modified in an E. coli sumoylation assay. Strikingly, these TCP-SCE1 interactions were found to redistribute these TCPs into nuclear foci/speckles, suggesting that these TCP foci represent sites for SUMO (conjugation activity.

  16. Analysis of shield for the nuclear ship MUTSU

    International Nuclear Information System (INIS)

    Fuse, Takayoshi; Takeuchi, Kiyoshi; Yamaji, Akio

    1975-01-01

    On the nuclear ship MUTSU, a higher-than-expected level of radiation was found, with output raised to 1.4 per cent. To investigate the radiation leakage, the analysis of the shielding problem utilized a four-step sequence of PALLAS-2DCY cylindrical r-z calculations with fixed sources distributions in the core. The neutron dose contours show the importance of streaming in the gap between the reactor vessel and the primary shield. Dominant consideration of thermal insulation exclude shielding from this area resulting in an imbalance in the shielding effectiveness. The neutron dose rate at the upper part of the reactor vessel is increased by neutrons incident on the head from cavity scattering. The calculation indicates that the neutron dose rate at the top of the primary shield is 5 rem/hr at 100 per cent output. (auth.)

  17. Safety for fuel assembly handling in the nuclear ship Mutsu

    International Nuclear Information System (INIS)

    Ando, Yoshio

    1978-01-01

    The safety for fuel assembly handling in the nuclear ship Mutsu is deliberated by the committee of general inspection and repair technique examination for Mutsu. The result of deliberation for both cases of removing fuel assemblies and keeping them in the reactor is outlined. The specification of fuel assemblies, and the nuclides and designed radioactivity of fission products of fuel are described. The possibility of shielding repair work and general safety inspection keeping the fuel assemblies in the reactor, the safety consideration when the fuel assemblies are removed at a quay, in a dry dock and on the ocean, the safety of fuel transport in special casks and fuel storage are explained. It is concluded finally that the safety of shielding repair work and general inspection work is secured when the fuel assemblies are kept in the reactor and also when the fuel assemblies are removed from the reactor by cautious working. (Nakai, Y.)

  18. Evaluation of radioactive inventory of nuclear ship MUTSU

    International Nuclear Information System (INIS)

    Adachi, M.

    1995-01-01

    The operation of the Nuclear Ship MUTSU was terminated in January 1992. Radioactivities and dose rates on the surfaces of reactor components were measured in order to estimate the residual radioactive inventory in the MUTSU. The predicted radioactive inventory due to neutron activation was calculated by using a computer code systems. The results show good correlation between predicted and measured values radioactivities in the core baffle plate. The radioactive inventory was estimated to be 8.4 x 10 14 Bq as of 1.5 years from the final shutdown of reactor operation. The contamination in reactor components was estimated from the contamination level measured in the Japan Power Demonstration Reactor (JPDR), from which the dose rates in the reactor room were calculated. The radioactive inventory due to contamination was estimated at 3.4 x 10 10 Bq. Some difference was found between these calculations and measurements. (Author)

  19. Shielding modification and safety review on the nuclear ship 'Mutsu'

    International Nuclear Information System (INIS)

    Osanai, Masao

    1978-01-01

    The Japan Atomic Energy Commission (JAEC) called on the Japan Nuclear Ship Development Agency (JNSDA) for shielding modification and safety review on the nuclear ship ''Mutsu'', and JNSDA has conducted the research and development (R and D) to meet the request of JAEC for the above two items. Concerning the shield modification, the following matters are described: the study on the cause of radiation leakage which was concluded to the fast neutron streaming, the conceptual design for this modification, the mock up experiment for shielding utilizing JRR-4, the basic design following on the conceptual design, including the detailed drawings of the modified construction and the shielding analysis using RADHEAT-V3 code, and the relating experiments such as the heat transfer test of the primary shielding structure and the test of strength in stranding. As for the safety review, the survey of the troubles and the technical problems having been experienced in the light water reactor plants of land use, for example, fuel integrity, stress corrosion cracking and the leakage of steam generator tubes, the revision of the design so as to adapt to current safety standards and regulations, for example, in-service inspection, the setting of additional leak detectors in the primary cooling system, the modification of emergeney filters, etc., and the review of the design and construction corresponding to recent R and D works, such as re-evaluation of the core design, cooling capability of natural circulation, thermal stress analysis of main pipings, and the evaluation of ECCS performance are presented . (Nakai, Y.)

  20. Nuclear-powered icebreaking container ship via the Northern Sea Route in its economical aspects

    International Nuclear Information System (INIS)

    Kondo, Koichi; Takamasa, Tomoji

    1996-01-01

    In recent years, major maritime nations such as Japan, Russia and Norway have been investigating the use of the Northern Sea Route (NSR) as a sea route between the Far East and Europe, linking the eastern and western parts of the Eurasian continent. In this study, as part of the examination of suitable merchant ships for the NSR, we make an economic comparison between diesel container ships taking the Suez Canal route and NSR nuclear-powered icebreaking container ship carrying the Marine Reactor X (MRX), which is currently being developed at the Japan Atomic Energy Research Institute. Compared to diesel container ships going via the Suez Canal, the first-year transportation cost of NSR nuclear-powered container ship after commissioning is 30-70% higher and the required freight rate (RFR) is 8-40% higher. If the nuclear reactor in nuclear-powered container ship, which is the reason for higher cost, were replaced by the cassette-type MRX, the reusability of the MRX would reduce this cost difference between nuclear-powered and diesel ships. The study also shows that in terms of the total cost including sales opportunity costs, NSR nuclear-powered container ship can compete sufficiently with diesel container ships on the Suez Canal route. (author)

  1. Nuclear or conventional power for surface combatant ships: Department of the Navy. Report to the Congress

    International Nuclear Information System (INIS)

    1977-01-01

    GAO reviewed the controversy over whether the Navy's major surface combatant ships should be all nuclear powered, all conventionally powered, or a mix of both. Nuclear ships are more capable but cost more and their relative cost-effectiveness cannot be measured because Navy analysts cannot quantify many benefits of nuclear power. The Congress, in reviewing Navy shipbuilding plans for surface combatant ships, should be cognizant that buying only conventional ships will maximize naval firepower; buying only nuclear ships will provide mobility and greater freedom from logistics support; and buying a mix is a third option providing, to varying degrees, the advantages and disadvantages of the all-nuclear and all-conventional options

  2. The economic potential of a cassette-type-reactor-installed nuclear ice-breaking container ship

    International Nuclear Information System (INIS)

    Kondo, Koichi; Takamasa, Tomoji

    1999-01-01

    An improved cassette-type marine reactor MRX (Marine Reactor X) which is currently researched and developed by the Japan Atomic Energy Research Institute is designed to be easily removed and transferred to another ship. If the reactor in a nuclear-powered ship, which is the reason for its higher cost, were replaced by the cassette-type-MRX, the reusability of the MRX would reduce the cost difference between nuclear-powered and diesel ships. As an investigation of one aspect of a cassette-type MRX, we attempted in this study to do an economic review of an MRX-installed nuclear-powered ice-breaking container ship sailing via the Arctic Ocean. The transportation cost between the Far East and Europe to carry one TEU (twenty-foot-equivalent container unit) over the entire life of the ship for an MRX (which is used for a 20-year period)-installed container ship sailing via the Arctic Ocean is about 70% higher than the Suez Canal diesel ship, carrying 8,000 TEU and sailing at 25 knots, and about 10% higher than the Suez Canal diesel ship carrying 4,000 TEU and sailing at 34 knots. The cost for a cassette-type-MRX (which is used for a 40-year period, removed and transferred to a second ship after being used for 20 years in the first ship)-installed nuclear-powered container ship is about 7% lower than that for the one operated for 20 years. Considering any loss or reduction in sales opportunities through the extension of the transportation period, the nuclear-powered container ship via the Arctic Sea is a more suitable means of transportation than a diesel ship sailing at 25 knots via the Suez Canal when the value of the commodities carried exceeds 2,800 dollars per freight ton. (author)

  3. Economic potential of nuclear-powered ice-breaking container ship via the northern sea route

    International Nuclear Information System (INIS)

    Takamasa, Tomoji; Kondo, Koichi

    2000-01-01

    An improved cassette-type marine reactor MRX (Marine Reactor X) which is currently researched and developed by the JAERI is designed to be easily removed and transferred to another ship. If the reactor in a nuclear-powered ship, which is the reason for its higher cost, were replaced by the cassette-type-MRX, the reusability of the MRX would reduce the cost difference between nuclear-powered and diesel ships. As an investigation of one aspect of a cassette-type MRX, we attempted in this study to do an economic review of an MRX-installed nuclear-powered ice-breaking container ship sailing via the Arctic Ocean. The transportation cost between the Far East and Europe to carry one TEU (twenty-foot-equivalent container unit) over the entire life of the ship for an MRX (which is used for a 20-year period)-installed container ship sailing via the Arctic Ocean is about 70% higher than the Suez Canal diesel ship, carrying 8,000 TEU and sailing at 25 knots, and about 10% higher than the Suez Canal diesel ship carrying 4,000 TEU and sailing at 34 knots. The cost for a cassette-type-MRX (which is used for a 40-year period, removed and transferred to a second ship after being used for 20 years in the first ship)-installed nuclear-powered container ship is about 7% lower than that for the one operated for 20 years. Considering any loss or reduction in sales opportunities through the extension of the transportation period, the nuclear-powered container ship via the Arctic Sea is a more suitable means of transportation than a diesel ship sailing at 25 knots via the Suez Canal when the value of the commodities carried exceeds 2,800 dollars per freight ton. (author)

  4. Di-nuclear systems studied with the velocity filter SHIP

    Energy Technology Data Exchange (ETDEWEB)

    Heinz, S.; Hessberger, F.P.; Ackermann, D.; Burkhard, H.G.; Khuyagbaatar, J.; Kindler, B.; Lommel, B.; Mann, R.; Maurer, J. [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, Darmstadt (Germany); Comas, V.; Heredia, J. [Institute of Technologies and Applied Sciences, Habana (Cuba); Hofmann, S. [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, Darmstadt (Germany); Goethe-Universitaet Frankfurt, Institut fuer Physik, Frankfurt (Germany); Gan, Z. [Chinese Academy of Sciences, Institute of Modern Physics, Lanzhou (China); Nishio, K. [Japan Atomic Energy Agency (JAEA), Tokai, Ibaraki (Japan); Sulignano, B. [DAPNIA / SPhN, CEA Saclay, Gif-sur-Yvette Cedex (France)

    2008-11-15

    Various nuclear reactions like quasi-fission, fusion-fission or particle and cluster evaporation from excited compound nuclei were studied in heavy-ion reactions at the velocity filter SHIP of GSI. The velocity filter offers the possibility to detect all reaction products under zero degree relative to the beam direction. Together with the measurement of the product velocity distribution this allows for an identification of the underlying reaction mechanism. This article is focussed on reactions of {sup 25}Mg and {sup 64}Ni beams on {sup 206,207}Pb targets at energies of 5.9 x A MeV and 8.7 x A MeV. Besides evaporation residues from {sup 25}Mg+{sup 206}Pb collisions we found evidence for rotation and quasi-fission of nuclear molecules formed in the entrance channel after the capture stage. The break-up of the systems showed a preferred clustering leading to isotopes in the region 84{<=}Z{<=}88 and 122{<=}N{<=}127 of the chart of nuclei. (orig.)

  5. Ship

    OpenAIRE

    Keuning, J.A.

    2008-01-01

    The invention concerns a ship designed for use at high speed and heavy seas having a single long and slender hull with a narrow beam and a more or less vertical bow, whereby the front half of the hull has more or less vertical sides, minimal flare in the bow sections and towards the bow an increase in draught at its center line combined with a more or less similar increase of freeboard and whereby the aft end of the hull has a flat or slightly V-shaped bottom with one or more propellers and/o...

  6. Environmental impact analysis of the Nuclear Merchant Ship Program-addendum. Special study

    International Nuclear Information System (INIS)

    1977-06-01

    This study represents a qualitative extension of an earlier Environmental Impact Analysis of the Nuclear Merchant Ship Program (MarAd, 1975) using an Ultra Large Crude Carrier (ULCC) as the reference ship, to other types of ships including a containership, dry-bulk cargo vessel, and an icebreaking oil tanker. This qualitative analysis shows that, for ships operating into coastal ports (containerships and possibly dry-bulk carriers), both ecological and radiological impacts would be somewhat greater than for the reference ULCC docking at an offshore terminal. These impacts can be kept within the guidelines established for land based nuclear power plants by implementation of appropriate operating procedures

  7. Ship nuclear power plants: system approach designing and optimal parameter selection

    International Nuclear Information System (INIS)

    Dolgov, V.N.

    1995-01-01

    Dependence of basic indices of naval nuclear power installations on combination of thermotechnical parameters is considered. The necessity of new approach to designing naval nuclear power facilities, based on combined analysis of the above facilities and the ship, as a single complex system, is demonstrated. The conclusion is made that unjustified increase in the ship metal capacity, terms and costs of their production takes place in case of disregarding the role of mass and dimensions of nuclear power facilities and consequently their thermotechnical characteristics in formation of the ship displacement tonnage. 2 refs., 3 figs

  8. New start of nuclear-powered ship `Mutsu`. 1. Decommissioning works of `Mutsu` and research and development of nuclear-powered ships hereafter

    Energy Technology Data Exchange (ETDEWEB)

    Inoue, Shoichiro [Japan Atomic Energy Research Inst., Tokyo (Japan)

    1996-02-01

    The nuclear-powered ship `Mutsu` was launched in June, 1969, and used Ominato, Aomori Prefecture, as its home port. The initial criticality of the reactor was attained in August, 1974. However, radiation leak occurred, and the repair of shielding and the general safety checkup were carried out in Sasebo since 1980. The ship moved to the new home port Sekinehama in 1988, and after the trial, it received the certificate of inspection from Science and Technology Agency and Ministry of Transport. Thus `Mutsu` was completed as the nuclear-powered ship. The experimental voyage was begun in February, 1991, and finished in January, 1992. The reconstruction works are in progress to change `Mutsu` to a large ocean observation and research ship. The course of the research and development, the reactor power raising test and the sea trial, the experimental voyage and the results attained by `Mutsu` are reported. One of the important items is the training of the crew who operate nuclear-powered ships and nuclear reactors, and about 400 seamen took part in the operation of `Mutsu`. (K.I.).

  9. New start of nuclear-powered ship 'Mutsu'. 1. Decommissioning works of 'Mutsu' and research and development of nuclear-powered ships hereafter

    International Nuclear Information System (INIS)

    Inoue, Shoichiro

    1996-01-01

    The nuclear-powered ship 'Mutsu' was launched in June, 1969, and used Ominato, Aomori Prefecture, as its home port. The initial criticality of the reactor was attained in August, 1974. However, radiation leak occurred, and the repair of shielding and the general safety checkup were carried out in Sasebo since 1980. The ship moved to the new home port Sekinehama in 1988, and after the trial, it received the certificate of inspection from Science and Technology Agency and Ministry of Transport. Thus 'Mutsu' was completed as the nuclear-powered ship. The experimental voyage was begun in February, 1991, and finished in January, 1992. The reconstruction works are in progress to change 'Mutsu' to a large ocean observation and research ship. The course of the research and development, the reactor power raising test and the sea trial, the experimental voyage and the results attained by 'Mutsu' are reported. One of the important items is the training of the crew who operate nuclear-powered ships and nuclear reactors, and about 400 seamen took part in the operation of 'Mutsu'. (K.I.)

  10. Reliability analysis of emergency decay heat removal system of nuclear ship under various accident conditions

    International Nuclear Information System (INIS)

    Matsuoka, Takeshi

    1984-01-01

    A reliability analysis is given for the emergency decay heat removal system of the Nuclear Ship ''Mutsu'' and the emergency sea water cooling system of the Nuclear Ship ''Savannah'', under ten typical nuclear ship accident conditions. Basic event probabilities under these accident conditions are estimated from literature survey. These systems of Mutsu and Savannah have almost the same reliability under the normal condition. The dispersive arrangement of a system is useful to prevent the reduction of the system reliability under the condition of an accident restricted in one room. As for the reliability of these two systems under various accident conditions, it is seen that the configuration and the environmental condition of a system are two main factors which determine the reliability of the system. Furthermore, it was found that, for the evaluation of the effectiveness of safety system of a nuclear ship, it is necessary to evaluate its reliability under various accident conditions. (author)

  11. International legal problems of topical interest concerning the peaceful navigation of nuclear ships

    International Nuclear Information System (INIS)

    Bernhardt, R.; Rudolf, W.

    1975-01-01

    The lack of internationally accepted laws on the operation of nuclear ships has proved so far perhaps a more serious obstacle to further development than the problems of a technical-economic kind, although international law by no means that inadequate that it could not, at least basically, do justice to the peaceful navigation of nuclear ships. The unsatisfactory legal situation has been caused in the first place by the conduct of the majority of states which, out of fear of the risks of nuclear ships, also questioned those articles of international maritime law which had been undisputed up to then. This goes in particular for the SOLAS convention, the principles of the peaceful crossing of territorial waters and of calling at ports. On the other hand, it ought to be pointed out, too, that the states obviously do not assume that the operation of nuclear ships is using the sea inadmissably under international law. One could see this as a continuation of the strict Trail-Smelter-doctrine which forbids states to allow activities which might have harmful effects on other national territories. There is no doubt, that the uses of nuclear energy belong to these dangerous activites. At the same time, they are accepted under international law, provided that they are supervised legally and provided that appropriate liability arrangments under civil law are at hand. This is the starting point for over coming the legal difficulties in the peaceful navigation of nuclear ships: it is to be treated as a matter of urgency to elaborate and to put into force comprehensive international conventions for the licensing and supervision of nuclear ships and concerning liablilty under civil law of the operators of nuclear ships. The required freedom in the navigation of nuclaer ships can only be achieved by further reglementation under maritime law. (orig./LN) [de

  12. Application of an automatic pattern recognition for aleatory signals for the surveillance of nuclear reactor and rotating machinery

    International Nuclear Information System (INIS)

    Nascimento, J.A. do.

    1982-02-01

    An automatic pattern recognition program PSDREC, developed for the surveillance of nuclear reactor and rotating machinery is described and the relevant theory is outlined. Pattern recognition analysis of noise signals is a powerful technique for assessing 'system normality' in dynamic systems. This program, with applies 8 statistical tests to calculated power spectral density (PSD) distribution, was earlier installed in a PDP-11/45 computer at IPEN. To analyse recorded signals from three systems, namely an operational BWR power reactor (neutron signals), a water pump and a diesel engine (vibration signals) this technique was used. Results of the tests are considered satisfactory. (Author) [pt

  13. Public relations campaign for shipping spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Bushee, Tom [Northern States Power Company, Minneapolis, MN (United States)

    1989-07-01

    An example of positive outcome of proper attitude of the media and public on the occasion of shipping of nuclear fuel is described. Nothing new was invented in the way of public relations issue management. But a combination of a number of proven techniques were put together and the public relations plan that was highly successful. early planning was of great help. Public officials were well informd by means of ANS organized seminars. ANS had experts from Sandia Labs (a major government research facility), General Electric (the cask supplier), the railroad we planned to use and Northern States Power Company on the program to describe what was going to happen and why it was safe. These sessions are believed to head off a major portion of the local opposition. A cooperation was established with the states of Wisconsin and Minnesota in providing shipment-specific training for emergency response personnel along the route. Safety, obviously, was the number one concern expressed by public officials. Knowing that would be the case, it was decided to provide some optional extras to go with the shipments. There was a consultant yo do a safety analysis of all the possible rail routes between the plant and storage facility. Though none was required by law, a shipment-specific emergency response plan which was prepared. Another important effort which was maintained from the beginning was sharing information among the participants. In dealing with the news media, an attemp was made to stick to a single source of information as much as possible. When dealing with the news media, one should refuse to apologize for modern technology. One should attack, at every opportunity, the idea that a ''risk-free'' society is worth the price of returning to the Dark Ages. The contributions of nuclear technology are numerous and far-reaching. Its negative impacts on health and safety have been minor compared with most other major industrial technologies. Certainly there is risk in stepping out

  14. Public relations campaign for shipping spent nuclear fuel

    International Nuclear Information System (INIS)

    Bushee, Tom

    1989-01-01

    An example of positive outcome of proper attitude of the media and public on the occasion of shipping of nuclear fuel is described. Nothing new was invented in the way of public relations issue management. But a combination of a number of proven techniques were put together and the public relations plan that was highly successful. early planning was of great help. Public officials were well informd by means of ANS organized seminars. ANS had experts from Sandia Labs (a major government research facility), General Electric (the cask supplier), the railroad we planned to use and Northern States Power Company on the program to describe what was going to happen and why it was safe. These sessions are believed to head off a major portion of the local opposition. A cooperation was established with the states of Wisconsin and Minnesota in providing shipment-specific training for emergency response personnel along the route. Safety, obviously, was the number one concern expressed by public officials. Knowing that would be the case, it was decided to provide some optional extras to go with the shipments. There was a consultant yo do a safety analysis of all the possible rail routes between the plant and storage facility. Though none was required by law, a shipment-specific emergency response plan which was prepared. Another important effort which was maintained from the beginning was sharing information among the participants. In dealing with the news media, an attemp was made to stick to a single source of information as much as possible. When dealing with the news media, one should refuse to apologize for modern technology. One should attack, at every opportunity, the idea that a r isk-freesociety is worth the price of returning to the Dark Ages. The contributions of nuclear technology are numerous and far-reaching. Its negative impacts on health and safety have been minor compared with most other major industrial technologies. Certainly there is risk in stepping out of

  15. Benchmark study of some thermal and structural computer codes for nuclear shipping casks

    International Nuclear Information System (INIS)

    Ikushima, Takeshi; Kanae, Yoshioki; Shimada, Hirohisa; Shimoda, Atsumu; Halliquist, J.O.

    1984-01-01

    There are many computer codes which could be applied to the design and analysis of nuclear material shipping casks. One of problems which the designer of shipping cask faces is the decision regarding the choice of the computer codes to be used. For this situation, the thermal and structural benchmark tests for nuclear shipping casks are carried out to clarify adequacy of the calculation results. The calculation results are compared with the experimental ones. This report describes the results and discussion of the benchmark test. (author)

  16. Lift-based up-ender and methods using same to manipulate a shipping container containing unirradiated nuclear fuel

    Science.gov (United States)

    Nilles, Michael J.

    2017-08-01

    A shipping container containing an unirradiated nuclear fuel assembly is lifted off the ground by operating a crane to raise a lifting tool comprising a winch. The lifting tool is connected with the shipping container by a rigging line connecting with the shipping container at a lifting point located on the shipping container between the top and bottom of the shipping container, and by winch cabling connecting with the shipping container at the top of the shipping container. The shipping container is reoriented by operating the winch to adjust the length of the winch cabling so as to rotate the shipping container about the lifting point. Shortening the winch cabling rotates the shipping container about the lifting point from a horizontal orientation to a vertical orientation, while lengthening the winch cabling rotates the shipping container about the lifting point from the vertical orientation to the horizontal orientation.

  17. The economic potential of a cassette-type-reactor-installed nuclear ice-breaking container ship

    International Nuclear Information System (INIS)

    Kondo, K.; Takamasa, T.

    2000-01-01

    The design concept of the cassette-type-reactor MRX (Marine Reactor X), being under development in Japan for the nuclear ice-breaker container ship is described. The MRX reactor is the monoblock water-cooled and moderated reactor with passive cooling system of natural circulation. It is shown that application of the reactor being under consideration gives an opportunity to decrease greatly the difference in prices for similar nuclear and diesel ships. Economic estimations for applicability of the nuclear ice-breaker container ship with the MRX reactor in Arctics for transportation of standard containers TEU from Europe to Far East as compared with transportation of the same containers by diesel ships via Suets Canal are made [ru

  18. Mobile-Dose: A Dose-Meter Designed for Use in Automatic Machineries for Dose Manipulation in Nuclear Medicine

    Science.gov (United States)

    de Asmundis, Riccardo; Boiano, Alfonso; Ramaglia, Antonio

    2008-06-01

    Mobile-Dose has been designed for a very innovative use: the integration in a robotic machinery for automatic preparation of radioactive doses, to be injected to patients in Nuclear Medicine Departments, with real time measurement of the activity under preparation. Mobile-Dose gives a constant measurement of the dose during the filling of vials or syringes, triggering the end of the filling process based on a predefined dose limit. Several applications of Mobile-Dose have been delivered worldwide, from Italian hospitals and clinics to European and Japanese ones. The design of such an instrument and its integration in robotic machineries, was required by an Italian company specialised in radiation protection tools for nuclear applications, in the period 2001-2003. At the time of its design, apparently no commercial instruments with a suitable interfacing capability to the external world existed: we designed it in order to satisfy all the strict requirements coming from the medical aspects (precision within 10%, repeatability, stability, time response) and from the industrial conceiving principles that are mandatory to ensure a good reliability in such a complicated environment. The instrument is suitable to be used in standalone mode too, thanks to its portability and compactness and to the intelligent operator panel programmed for this purpose.

  19. Shielding calculations for ships carrying irradiated nuclear fuel

    International Nuclear Information System (INIS)

    Burstall, R.F.; Dean, M.H.

    1983-01-01

    A number of ships have been constructed to carry irradiated fuel from Japan to the UK and France, for reprocessing. About twenty transport flasks may be carried on each voyage. Permanent shielding must be provided on the ships to ensure that no member of the crew receives an annual dose rate greater than a specified limit. As the fuel is of varying type and radiation history, and as flasks of differing designs are used, many calculations are needed. There are a number of difficulties in making shielding calculations for the ships. The geometry is complex, dimensions are large, and considerable air spaces are involved. The paper considers possible methods of calculation. The line-of-sight method is chosen for most of the calculations, for both gamma radiation and neutrons. The basic data which is used in the calculations is described. As the methods of calculation are somewhat approximate, it is necessary to provide confirmation that they are sufficiently accurate. Validation has been provided in two ways. First, measurements have been made on board the ships, and these have been checked against calculation. Second, a simplified model of the flasks and ship has been set up, and calculations checked against more sophisticated methods. Results of the validation checks are presented, and it is shown that adequate accuracy is achieved. (author)

  20. Shielding calculations for ships carrying irradiated nuclear fuel

    International Nuclear Information System (INIS)

    Dean, M.H.

    1985-01-01

    A number of ships have been constructed to carry irradiated fuel from Japan to the U.K. and France, for reprocessing. About 20 transport flasks may be carried on each voyage. Permanent shielding must be provided on the ships to ensure that no member of the crew receives an annual dose greater than a specified limit. As the fuel is of varying type and radiation history, and as flasks of differing designs are used, many shielding calculations are needed. There are a number of difficulties in making shielding calculations for the ships. The geometry is complex, dimensions are large and considerable air spaces are involved. The paper considers possible methods of calculation. The line-of-sight method is chosen for most of the calculations, for both γ-radiation and neutrons. The basic data which is used in the calculations is described. As the methods of calculation are somewhat approximate, it is necessary to provide confirmation that they are sufficiently accurate. Validation has been provided in two ways. First, measurements have been made on board one of the ships, Pacific Crane, and these have been checked against calculation. Second, a simplified model of the flasks and ship has been set up, and calculations checked against more sophisticated methods. Results of the validation checks are presented, and it is shown that adequate accuracy is achieved. (author)

  1. Introduction to the 'CAS' nuclear propulsion plant for ships: specific safety options

    International Nuclear Information System (INIS)

    Verdeau, J.J.; Baujat, J.

    1978-01-01

    After a brief review of the development of nuclear propulsion in FRANCE (Land Based Prototype PAT 1964 - Navy nuclear ships - Advanced Nuclear Boiler Prototype CAP 1975 and now the CAS nuclear plant), the specific safety options of CAS are presented: cold, compartmented fuel (plates); reduced flow during LOCA; permanent cooling of fuel during LOCA; pressurized, entirely passive containment; no control rod ejection and possibility of temporary storage of spent fuel on board [fr

  2. Method of analyzing the shipping inspection water in nuclear fuels

    International Nuclear Information System (INIS)

    Ishikawa, Tatsuo; Izumoji, Yoshiaki.

    1984-01-01

    Purpose: To automatically perform radioactive-corrosion-products removing operation and thereby automatic analysis for shipping inspection water. Method: An radioactive-corrosion-product removing device has a column filled with a chelate resin layer. Shipping-inspection water as a specimen is injected from a sample-water inlet to the column, passes through the chelate resin layer, issues through the sample-water exit and is then stored once in a sample collector. The shipping inspection water sampled in the sampling collector is sent to an inspection port in an on-line or off-line manner and gamma-ray determination is made by a gamma-ray spectrum analyzer. (Horiuchi, T.)

  3. Full-scale tests of spent-nuclear-fuel shipping systems

    International Nuclear Information System (INIS)

    Yoshimura, H.R.; Huerta, M.

    1976-01-01

    Sandia Laboratories will be conducting, for the U.S. Energy Research and Development Administration, a series of tests involving spent-nuclear-fuel shipping systems. Large shipping casks in the 20500 to 70000-kg range will be included in the following full-scale tests: (1) Runaway tractor-trailer crash into a solid concrete barrier while carrying a shipping cask. (2) High-speed locomotive grade-crossing impact with a truck carrying a shipping cask. (3) High-speed derailment, collision, and fire involving a special railcar and shipping cask. The hardware and testing procedures for each of the tests are described. The analysis conducted in advance of the tests addresses the modelling technique used and a description of the scale-model tests. Analytical modelling being done before running the full-scale tests is also described. (author)

  4. Safety considerations in the use of ports and approaches by nuclear merchant ships

    International Nuclear Information System (INIS)

    1968-01-01

    The purpose of this publication is to provide guidance to Governments and Port Authorities on the various procedures and precautionary measures that may be employed when nuclear merchant ships use ports and approaches. The problem is basically that of siting a nuclear reactor in a populated area, with the extra factor of mobility. Added to this is the fact that the safety standards of the nuclear ship may be those of a country other than that of the port of entry. Thus the problem must be solved in international agreements.

  5. Notes on a proposed consultation procedure for the licensing of nuclear ships

    International Nuclear Information System (INIS)

    Devoto, A.

    1978-01-01

    The application of the recommendations adopted by the International Commission on Radiological Protection (see ICRP Publication no. 26) to future nuclear ship projects is discussed. That booklet clarifies the recommendation, adopted in 1965, according to which all doses should be kept as low as possible having regard to social and economic factors. This low level is achieved with justification of nuclear operations and optimisation of safety systems. The need to evaluate collective dose gives rise to special problems with regard to nuclear ships, in view of the variety of population groups or communities involved and the different assessments applied to each [fr

  6. 46 CFR 97.30-5 - Accidents to machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Accidents to machinery. 97.30-5 Section 97.30-5 Shipping... Reports of Accidents, Repairs, and Unsafe Equipment § 97.30-5 Accidents to machinery. (a) In the event of an accident to a boiler, unfired pressure vessel, or machinery tending to render the further use of...

  7. Crash testing of spent-nuclear-fuel shipping systems

    International Nuclear Information System (INIS)

    Yoshimura, H.R.

    1978-01-01

    Full scale testing to date has verified that current analytical tools and the use of scale model testing are both accurate methods for predicting shipping cask response to severe accident conditions. The containers tested are capable of surviving severe transportation accidents

  8. Report on radioactivity monitoring during the visits of nuclear powered ships

    International Nuclear Information System (INIS)

    1977-01-01

    The National Radiation Laboratory of the Department of Health is required under NZAEC Report 500 'New Zealand Code for Nuclear Powered Shipping' (June 1976) to monitor for release of radioactivity during the stay of such a ship in a New Zealand port and to provide technical assistance to Civil Defence organisations charged with dealing with any emergency arising from an accidental release of radioactive materials. This report outlines the activities undertaken for the two visits which took place in 1976

  9. Program to develop analytical tools for environmental and safety assessment of nuclear material shipping container systems

    International Nuclear Information System (INIS)

    Butler, T.A.

    1978-11-01

    This paper describes a program for developing analytical techniques to evaluate the response of nuclear material shipping containers to severe accidents. Both lumped-mass and finite element techniques are employed to predict shipping container and shipping container-carrier response to impact. The general impact problem is computationally expensive because of its nonlinear, three-dimensional nature. This expense is minimized by using approximate models to parametrically identify critical cases before more exact analyses are performed. The computer codes developed for solving the problem are being experimentally substantiated with test data from full-scale and scale-model container drop tests. 6 figures, 1 table

  10. Truck and rail charges for shipping spent fuel and nuclear waste

    International Nuclear Information System (INIS)

    McNair, G.W.; Cole, B.M.; Cross, R.E.; Votaw, E.F.

    1986-06-01

    The Pacific Northwest Laboratory developed techniques for calculating estimates of nuclear-waste shipping costs and compiled a listing of representative data that facilitate incorporation of reference shipping costs into varius logistics analyses. The formulas that were developed can be used to estimate costs that will be incurred for shipping spent fuel or nuclear waste by either legal-weight truck or general-freight rail. The basic data for this study were obtained from tariffs of a truck carrier licensed to serve the 48 contiguous states and from various rail freight tariff guides. Also, current transportation regulations as issued by the US Department of Transportation and the Nuclear Regulatory Commission were investigated. The costs that will be incurred for shipping spent fuel and/or nuclear waste, as addressed by the tariff guides, are based on a complex set of conditions involving the shipment origin, route, destination, weight, size, and volume and the frequency of shipments, existing competition, and the length of contracts. While the complexity of these conditions is an important factor in arriving at a ''correct'' cost, deregulation of the transportation industry means that costs are much more subject to negotiation and, thus, the actual fee that will be charged will not be determined until a shipping contract is actually signed. This study is designed to provide the baseline data necessary for making comparisons of the estimated costs of shipping spent fuel and/or nuclear wastes by truck and rail transportation modes. The scope of the work presented in this document is limited to the costs incurred for shipping, and does not include packaging, cask purchase/lease costs, or local fees placed on shipments of radioactive materials

  11. 46 CFR 58.01-50 - Machinery space, noise.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 2 2010-10-01 2010-10-01 false Machinery space, noise. 58.01-50 Section 58.01-50... MACHINERY AND RELATED SYSTEMS General Requirements § 58.01-50 Machinery space, noise. (a) Each machinery space must be designed to minimize the exposure of personnel to noise in accordance with IMO A.468(XII...

  12. Annual report of the Japan Nuclear Ship Research and Development Agency, for fiscal 1981

    International Nuclear Information System (INIS)

    1982-01-01

    All the works of shielding repair and safety general inspection for the nuclear ship ''Mutsu'' were completed. For advancing the research and development of nucear ships, of course, the data and experience of the behavior of marine nuclear reactors are required, which can be obtained only by operating nuclear ships. The Agency will carry out the experimental voyage after the prescribed tests are finished, and endeavor to attain the objective. A new development was observed on the new home port for the Mutsu. In May, 1981, the agreement was reached among those concerned to decide Sekine Beach, Mutsu City, as the candidate site after the survey and coordination, and to construct the home port as early as possible. The Agency carried out the survey required for the location, and reported in March, 1982, that the construction of the home port is technically feasible, and also the concept of the home port and the incidental facilities on land was informed to Aomori Prefecture. Hereafter, the compensation for fishery and the purchase of land will be actively promoted. In order to ease the restriction on the energy supply for shipping industry, the technical basis for the practical use of nuclear ships must be urgently consolidated. In this report, the works performed by the Agency in fiscal 1981 are described. (Kako, I.)

  13. The tumor suppressor SHIP1 colocalizes in nucleolar cavities with p53 and components of PML nuclear bodies

    OpenAIRE

    Ehm, Patrick; Nalaskowski, Marcus M; Wundenberg, Torsten; Jücker, Manfred

    2015-01-01

    The inositol 5-phosphatase SHIP1 is a negative regulator of signaling processes in haematopoietic cells. By converting PI(3,4,5)P3 to PtdIns(3,4)P2 at the plasma membrane, SHIP1 modifies PI3-kinase mediated signaling. We have recently demonstrated that SHIP1 is a nucleo-cytoplasmic shuttling protein and SHIP1 nuclear puncta partially colocalize with FLASH, a component of nuclear bodies. In this study, we demonstrate that endogenous SHIP1 localizes to intranucleolar regions of both normal and ...

  14. Problems on shipping high-enriched nuclear materials

    International Nuclear Information System (INIS)

    Ganzha, V.V.; Demko, N.A.; Deryavko, I.I.; Zelenski, D.I.; Kolbaenkov, A.N.; Pivovarov, O.S.; Storozhenko, A.N.; Chernyad'ev, V.V.; Yakovlev, V.V.; Gorin, N.V.; Prokhod'ko, A.I.; Sherbina, A.N.; Barsanov, V.I.; Dyakov, E.K.; Tishenko, M.F.; Khlystov, A.I.; Vasil'ev, A.P.; Smetannikov, V.P.

    1998-01-01

    In 1996-1998 all Russian nuclear materials were taken out of the Institute of Atomic Energy of Kazakhstan National Nuclear Centre (IAE NNC RK). In this report there are basic tasks related to the performance of this work. They are: 1) Preparation of Russian nuclear materials (NM) kept at IAE NNC RK for transportation; 2) accounting and control of Russian nuclear materials kept at IAE NNC RK; 3) arrangement of permit papers for NM transportation; 4) NM transportation from IAE NNC RK to the enterprises of Russian MINATOM; 5) provision of nuclear and radiation safety in the course of operations with NM; 6) provision of physical protection for Russian NM

  15. Nuclear accumulation of SHIP1 mutants derived from AML patients leads to increased proliferation of leukemic cells.

    Science.gov (United States)

    Nalaskowski, Marcus M; Ehm, Patrick; Rehbach, Christoph; Nelson, Nina; Täger, Maike; Modest, Kathrin; Jücker, Manfred

    2018-05-28

    The inositol 5-phosphatase SHIP1 acts as negative regulator of intracellular signaling in myeloid cells and is a tumor suppressor in myeloid leukemogenesis. After relocalization from the cytoplasm to the plasma membrane SHIP1 terminates PI3-kinase mediated signaling processes. Furthermore, SHIP1 is also found in distinct puncta in the cell nucleus and nuclear SHIP1 has a pro-proliferative function. Here we report the identification of five nuclear export signals (NESs) which regulate together with the two known nuclear localization signals (NLSs) the nucleocytoplasmic shuttling of SHIP1. Mutation of NLSs reduced the nuclear import and mutation of NESs decreased the nuclear export of SHIP1 in the acute myeloid leukemia (AML) cell line UKE-1. Interestingly, four SHIP1 mutants (K210R, N508D, V684E, Q1153L) derived from AML patients showed a nuclear accumulation after expression in UKE-1 cells. In addition, overexpression of the AML patient-derived mutation N508D caused an increased proliferation rate of UKE-1 cells in comparison to wild type SHIP1. Furthermore, we identified serine and tyrosine phosphorylation as a molecular mechanism for the regulation of nucleocytoplasmic shuttling of SHIP1 where tyrosine phosphorylation of distinct residues i.e. Y864, Y914, Y1021 reduces nuclear localization, whereas serine phosphorylation at S933 enhances nuclear localization of SHIP1. In summary, our data further implicate nuclear SHIP1 in cellular signaling and suggest that enhanced accumulation of SHIP1 mutants in the nucleus may be a contributory factor of abnormally high proliferation of AML cells. Copyright © 2017. Published by Elsevier Inc.

  16. Shielding tests for a new ship for the transport of spent nuclear fuels

    International Nuclear Information System (INIS)

    Ito, D.; Kitano, T.; Akiyama, H.; Ueki, K.; Sanui, T.

    1998-01-01

    a new ship for the transport of spent nuclear fuels which uses serpentine concrete as its major shielding material has been constructed. The shielding calculations are based on DOT3.5 code (CCC-276) and the DLC23). Experiments with Cf-252 and Co-60 sources were carried out to confirm the validity of this method of calculating the shielding effectiveness of serpentine concrete. In these experiments, neutron and gamma-ray dose equivalent rates were measured in various arrangements to simulate the shielding structures of the ship, the calculations for each arrangement were performed by this shielding calculation method. For both neutron and gamma-rays, the calculation results agreed with the experiments very well, confirming that this calculation method used in the ship's shielding design is valid. Two kinds of on-board gamma-ray shielding tests were performed to confirm the ship's actual shielding effectiveness. In one kind of test, gamma-ray dose equivalent rates were measured for each shielding wall using Co-60 sources. In the other kind of test, gamma-ray dose equivalent rates in the ship's accommodation area were measured when a strong Co-60 source was placed in a loaded shipping cask's position. In both gamma-ray shielding tests all measured dose equivalent rates were less than the calculated values, confirming that the ship's actual shielding is sufficient to meet safety requirements. (authors)

  17. Irradiation test on connector part for nuclear instrumentation of nuclear powered ship 'Mutsu'

    International Nuclear Information System (INIS)

    Kudo, Takahiro; Mizushima, Toshihiko; Tsunoda, Tsunemi; Nakazawa, Toshio

    1991-01-01

    The nuclear instrumetnation facility of the nuclear powered ship 'Mutsu' is composed of neutron detectors, signal cables and the circuits for measurement, and ocntinuously monitors neutron flux. Since this facility treats very faint signals, for the signal cables, coaxial cables and triple coaxial cables are used. The coaxial cables for the nuclear instrumentation are equipped with connectors at both ends, and those are called prefabricated cable. The prefabricated cables are connected to neutron detectors, and installed in the detection holes of the primary shielding tank in the containment vessel. Therefore, at the time of reactor operation, they are exposed to high radiation, and the deterioration of the characteristics of the prefabricated cables is feared. For the purpose of confirming that the part of deteriorating the insulation of the prefabricated cables is connectors, and clarifying the cause of the deterioration of insulation in connector part, the irradiation test of this time was carried out. The environment in which the prefabricated cables are laid, the specifications of the cables and connectors, the materials, gamma ray irradiation and the test results are reported. (K.I.)

  18. Nuclear structure studies in the seaborgium region at SHIP

    Energy Technology Data Exchange (ETDEWEB)

    Antalic, S., E-mail: Stanislav.Antalic@fmph.uniba.sk; Andel, B. [Comenius University in Bratislava, 84248 Bratislava (Slovakia); Heßberger, F. P.; Khuyagbaatar, J. [GSI - Helmhotzzentrum für Schwerionenforschung GmbH, 64291 Darmstadt (Germany); Helmholtz Institute in Mainz, 55099 Mainz (Germany); Ackermann, D. [GSI - Helmhotzzentrum für Schwerionenforschung GmbH, 64291 Darmstadt (Germany); GANIL, 14074 Caen (France); Heinz, S.; Hofmann, S.; Kindler, B.; Laatiaoui, M.; Lommel, B. [GSI - Helmhotzzentrum für Schwerionenforschung GmbH, 64291 Darmstadt (Germany); Kalaninová, Z. [Comenius University in Bratislava, 84248 Bratislava (Slovakia); Laboratory of Nuclear Problems, JINR, 141980 Dubna (Russian Federation); Piot, J.; Vostinar, M. [GANIL, 14074 Caen (France)

    2015-10-15

    New decay data for the isotopes {sup 259}Sg and {sup 255}Rf were obtained at the velocity filter SHIP using an α-decay spectroscopy measurement. Both isotopes were produced and studied via a one neutron evaporation channel in the compound fusion reaction {sup 54}Cr+{sup 208}Pb. New isomeric states were observed and the single-particle level systematics for isotones with 151 and 153 neutrons were extended. A change of the ground-state configuration for the heaviest N = 151 isotones was observed. Detailed Monte-Carlo simulation for the α decay of {sup 259}Sg applying the GEANT4 toolkit was performed and compared with experimental data.

  19. Development of NESSY (Nuclear ship Engineering Simulation SYstem) and its application to dynamic analysis

    International Nuclear Information System (INIS)

    Kusunoki, T.; Uematsu, H.; Kobayashi, H.

    1992-01-01

    A marine reactor plant sustains incessant load change and the effects of vibration and ship motions due to the maneuvering and dynamic conditions in the marine environment. The change of process variables of the reactor plant is made in accordance with the load change and other effects, and also results in the propeller revolution change and subsequently affects on ship motions. In order to grasp dynamic behavior of the reactor plant in normal operation, including port entry and departure, and also in abnormal conditions such as anticipated transient and accidents, the Nuclear ship Engineering Simulation SYstem (simply ENSSY, hereinafter) carriers out combined analysis in which the behaviors of the ship propulsion, the reactor plant and the secondary systems are simultaneously calculated in each time step. (author)

  20. The tumor suppressor SHIP1 colocalizes in nucleolar cavities with p53 and components of PML nuclear bodies.

    Science.gov (United States)

    Ehm, Patrick; Nalaskowski, Marcus M; Wundenberg, Torsten; Jücker, Manfred

    2015-01-01

    The inositol 5-phosphatase SHIP1 is a negative regulator of signaling processes in haematopoietic cells. By converting PI(3,4,5)P3 to PtdIns(3,4)P2 at the plasma membrane, SHIP1 modifies PI3-kinase mediated signaling. We have recently demonstrated that SHIP1 is a nucleo-cytoplasmic shuttling protein and SHIP1 nuclear puncta partially colocalize with FLASH, a component of nuclear bodies. In this study, we demonstrate that endogenous SHIP1 localizes to intranucleolar regions of both normal and leukemic haematopoietic cells. In addition, we report that ectopically expressed SHIP1 accumulates in nucleolar cavities and colocalizes with the tumor suppressor protein p53 and components of PML nuclear bodies (e.g. SP100, SUMO-1 and CK2). Moreover, SHIP1 also colocalizes in nucleolar cavities with components of the ubiquitin-proteasome pathway. By using confocal microscopy data, we generated 3D-models revealing the enormous extent of the SHIP1 aggresomes in the nucleolus. Furthermore, treatment of cells with the proteasome inhibitor MG132 causes an enlargement of nucleolar SHIP1 containing structures. Unexpectedly, this accumulation can be partially prevented by treatment with the inhibitor of nuclear protein export Leptomycin B. In recent years, several proteins aggregating in nucleolar cavities were shown to be key factors of neurodegenerative diseases and cancerogenesis. Our findings support current relevance of nuclear localized SHIP1.

  1. CDKL5 influences RNA splicing activity by its association to the nuclear speckle molecular machinery.

    Science.gov (United States)

    Ricciardi, Sara; Kilstrup-Nielsen, Charlotte; Bienvenu, Thierry; Jacquette, Aurélia; Landsberger, Nicoletta; Broccoli, Vania

    2009-12-01

    Mutations in the human X-linked cyclin-dependent kinase-like 5 (CDKL5) gene have been shown to cause severe neurodevelopmental disorders including infantile spasms, encephalopathy, West-syndrome and an early-onset variant of Rett syndrome. CDKL5 is a serine/threonine kinase whose involvement in Rett syndrome can be inferred by its ability to directly bind and mediate phosphorylation of MeCP2. However, it remains to be elucidated how CDKL5 exerts its function. Here, we report that CDKL5 localizes to specific nuclear foci referred to as nuclear speckles in both cell lines and tissues. These sub-nuclear structures are traditionally considered as storage/modification sites of pre-mRNA splicing factors. Interestingly, we provide evidence that CDKL5 regulates the dynamic behaviour of nuclear speckles. Indeed, CDKL5 overexpression leads to nuclear speckle disassembly, and this event is strictly dependent on its kinase activity. Conversely, its down-regulation affects nuclear speckle morphology leading to abnormally large and uneven speckles. Similar results were obtained for primary adult fibroblasts isolated from CDKL5-mutated patients. Altogether, these findings indicate that CDKL5 controls nuclear speckle morphology probably by regulating the phosphorylation state of splicing regulatory proteins. Nuclear speckles are dynamic sites that can continuously supply splicing factors to active transcription sites, where splicing occurs. Notably, we proved that CDKL5 influences alternative splicing, at least as proved in heterologous minigene assays. In conclusion, we provide evidence that CDKL5 is involved indirectly in pre-mRNA processing, by controlling splicing factor dynamics. These findings identify a biological process whose disregulation might affect neuronal maturation and activity in CDKL5-related disorders.

  2. Act N0 65-956 of 12 November 1965 on the third party liability of operators of nuclear ships

    International Nuclear Information System (INIS)

    1965-01-01

    This Act determines the liability of operators of nuclear ships according to the general principles of the Paris Convention. In particular, such operators are solely liable for nuclear damage caused by a nuclear incident up to a limit of 500 millions French francs. With regard to French nuclear ships and insofar as the security provided by the operator is insufficient to meet claims for which he is liable up to the above-mentioned limit, the State intervenes to that amount. (NEA) [fr

  3. The conceptual solutions concerning decommissioning and dismantling of Russian civil nuclear powered ships

    International Nuclear Information System (INIS)

    Kulikov, Konstantin N.; Nizamutdinov, Rinat A.; Abramov, Andrey N.

    2013-01-01

    From 1959 up to 1991 nine civil nuclear powered ships were built in Russia: eight ice-breakers and one lash lighter carrier (cargo ship). At the present time three of them were taking out of service: ice-breaker 'Lenin' is decommissioned as a museum and is set for storage in the port of Murmansk, nuclear ice-breakers 'Arktika' and 'Sibir' are berthing. The ice-breakers carrying rad-wastes appear to be a possible source of radiation contamination of Murmansk region and Kola Bay because the ship long-term storage afloat has the negative effect on hull's structures. As the result of this under the auspices of the Federal Targeted Program 'Nuclear and Radiation Safety of Russia for 2008 and the period until 2015' the conception and projects of decommissioning of nuclear-powered ships are developed by the State corporation Rosatom with the involvement of companies of United Shipbuilding Corporation. In developing the principal provisions of conception of decommissioning and dismantling of icebreakers the technical and economic assessment of dismantling options in ship-repairing enterprises of North-West of Russia was performed. The paper contains description of options, research procedure, analysis of options of decommissioning and dismantling of nuclear ice-breakers, taking into account the principle of optimization of potential radioactive effect to personnel, human population and environment. The report's conclusions contain the recommendations for selection of option for development of nuclear icebreaker decommissioning and dismantling projects. (authors)

  4. Licensing requirements for nuclear merchant ships in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Schafstall, H.-G.

    1978-01-01

    The procedure of approval in the Federal Republic of Germany will be discussed, referring to the participated authorities and organizations. Rules and guidelines relevant for licensing are mentioned in the frame of legal positions. After presentation of general aspects of basic licensing requirements more detailed information is given relative to their accomplishment demonstrated on the German Nuclear Contained Ship NCS-80-Project

  5. Preliminary analysis of start up characteristics on SPWR with NESSY (Nuclear ship Engineering Simulation SYstem)

    International Nuclear Information System (INIS)

    Kusunoki, Tsuyoshi; Kyouya, Masahiko; Sako, Kiyoshi

    1993-09-01

    NESSY (Nuclear ship Engineering Simulation SYstem) has been developed to design advanced marine reactors. SPWR (System integrated PWR) has been designed by JAERI. It doesn't have control rod, and starts up by dilution of boron. we analyzed start up behavior of SPWR by NESSY, and evaluated the safety characteristics on start up and appropriate range of start up rate. (author)

  6. Confirmation of safety (important matters to be confirmed by the administration office having jurisdiction) of the first nuclear-powered ship 'Mutsu' in Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    1988-01-01

    After the deliberation on this safety confirmation, which was reported on September 22, 1987, by the Science and Technology Agency, the Nuclear Safety Commission started the investigation and deliberation from the 32nd regular meeting on September 24, 1987. As the result of examining on making the radiation measurement facilities for the time of accidents on board the first nuclear-powered ship 'Mutsu' into the fixed type, it was recognized to be appropriate. The contents of the investigation were the reqirements of the guideline, and the design of the radiation measurement facilities for the time of accidents such as high level containment vessel area monitors, high level reactor auxiliary machinery room area monitors, high level exhaust stack gas monitors, high level main steam pipe monitors and the radiation monitoring panel. It was confirmed that the proper countermeasures based on the features of the nuclear-powered ship 'Mutsu' have been taken for the radiation measurement facilities for the time of accidents on the basis of the basic concept referring to the guideline. (Kako, I.)

  7. Painting for nuclear power stations and machinery and equipments according to quality assurance program of ANSI

    International Nuclear Information System (INIS)

    Fukuda, Shinzo; Tsuchiya, Yukikazu.

    1979-01-01

    Recently, painting for nuclear power stations is carried out with the paints made domestically, and these paints are tested and judged generally according to the items of performance evaluation decided by the American National Standard Institute. In Japan, there is no standard regarding the paints for nuclear power stations. Painting is very important process, and it is appropriate to introduce quality assurance program into it. In this paper, the contents of ANSI standard concerning the paints and painting for nuclear power stations are explained, and the outline of the painting of heat exchangers carried out in accordance with the quality assurance program in the Tamano Shipyard, Mitsui Shipbuilding and Engineering Co., Ltd., is described. The test items for evaluating the general performance of the paints, the testing method for evaluating the endurance at the time of an accident, the quality assurance for the paints used for the facilities handling radiation and others are explained. Various problems arise when the quality assurance program of ANSI is applied actually to painting. It is difficult to judge the quality of paints and painting with numerical values, and much efforts were required to establish the quality assurance organization. The conditions for painting, the handling of many documents, the measures to unsatisfactory painting and so on caused much difficulties. (Kako, I.)

  8. Shipping and storage cask data for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, E.R.; Notz, K.J.

    1988-11-01

    This document is a compilation of data on casks used for the storage and/or transport of commercially generated spent fuel in the US based on publicly available information. In using the information contained in the following data sheets, it should be understood that the data have been assembled from published information, which in some instances was not internally consistent. Moreover, it was sometimes necessary to calculate or infer the values of some attributes from available information. Nor was there always a uniform method of reporting the values of some attributes; for example, an outside surface dose of the loaded cask was sometimes reported to be the maximum acceptable by NRC, while in other cases the maximum actual dose rate expected was reported, and in still other cases the expected average dose rate was reported. A summary comparison of the principal attributes of storage and transportable storage casks is provided and a similar comparison for shipping casks is also shown. References to source data are provided on the individual data sheets for each cask.

  9. Shipping and storage cask data for spent nuclear fuel

    International Nuclear Information System (INIS)

    Johnson, E.R.; Notz, K.J.

    1988-11-01

    This document is a compilation of data on casks used for the storage and/or transport of commercially generated spent fuel in the US based on publicly available information. In using the information contained in the following data sheets, it should be understood that the data have been assembled from published information, which in some instances was not internally consistent. Moreover, it was sometimes necessary to calculate or infer the values of some attributes from available information. Nor was there always a uniform method of reporting the values of some attributes; for example, an outside surface dose of the loaded cask was sometimes reported to be the maximum acceptable by NRC, while in other cases the maximum actual dose rate expected was reported, and in still other cases the expected average dose rate was reported. A summary comparison of the principal attributes of storage and transportable storage casks is provided and a similar comparison for shipping casks is also shown. References to source data are provided on the individual data sheets for each cask

  10. Calculation of releases of radioactive materials in gaseous effluents from nuclear-powered merchant ships (NMS-GEFF code)

    International Nuclear Information System (INIS)

    Cardile, F.P.; Bangart, R.L.; Collins, J.T.

    1978-06-01

    The Intergovernmental Maritime Consultative Organization IMCO) is currently preparing guidelines concerning the safety of nuclear-powered merchant ships. An important aspect of these guidelines is the determination of the releases of radioactive material in effluents from these ships and the control exercised by the ships over these releases. To provide a method for the determination of these releases, the NRC staff has developed a computerized model, the NMS-GEFF Code, which is described in the following chapters. The NMS-GEFF Code calculates releases of radioactive material in gaseous effluents for nuclear-powered merchant ships using pressurized water reactors

  11. The potential risks from Russian nuclear ships. NKS-SBA-1 status report

    Energy Technology Data Exchange (ETDEWEB)

    Oelgaard, P.L. [Risoe National Lab., Roskilde (Denmark)

    2001-11-01

    A review is given of the information available on the Russian nuclear ships including submarines, cruisers and ice-breaking ships with special emphasis on the vessels of the Northern Fleet and the Russian icebreakers. A significant part of these ships has today been taken out of active service, and they are in various stages of decommissioning. Information on the decommissioned vessels, their storage sites and the procedures planned for the further decommissioning works is discussed. The handling of spent nuclear fuel is also considered. The various types of accidents, which might occur with these ships, operational as well as decommissioned, are considered, and examples of actual accidents with operational vessels are presented. The types of accidents considered include criticality accidents, loss-of-coolant accidents, fires/explosions and sinking. Some measures taken by the Russians to avoid such accidents are discussed. The special problems connected to the two decommissioned submarines of the Northern Fleet, which have damaged cores, are mentioned. In appendices data on the Russian nuclear vessels are presented. (au)

  12. Confirmation of the safety of 'Mutsu', the first nuclear ship in Japan

    International Nuclear Information System (INIS)

    1981-01-01

    The Nuclear Safety Commission deliberated on the ''confirmation of the safety in the first nuclear ship ''Mutsu'' in Japan reported to it by the Committee on Examination of Reactor Safety, and acknowledged the policy toward the safety of the ship by the Science and Technology Agency. The CERS, requested by the NSC, had studied as to whether the judgement and policy by the STA toward the safety of the reactor installation in the n.s. Mutsu were appropriate. Safety confirmation concerns the following matters: reliability of the heat exchanger, piping, valves, etc., which are not duplicated with those in the emergency core cooling system, common use items for safety protection system and instrumentation and control system, fire protection, abnormal transients during operation, operation of the emergency core cooling system, analysis simulating the TMI nuclear power accident in the United States, etc. (J.P.N.)

  13. The present status of Japan Nuclear Ship Development Agency in fiscal 1981

    International Nuclear Information System (INIS)

    1982-01-01

    In the nuclear ship ''Mutsu'', the repair of shielding on the ship itself was completed in March, and on the reactor plant in January, 1982. Comprehensive safety check-up on both hardware and software, started in October, 1975, has been finished within fiscal 1981, except some on hardware. On the basis of the results, repair work is in progress to raise the safety and reliability of the reactor plant. As the new home port of the n.s. Mutsu, the Sekinehama area in Aomori Prefecture has been chosen as its candidate, where site survey was carried out. The following matters are described: shielding repair work on the ship hull and reactor plant, safety check-up on reactor plant components and plant design, the analysis of reactor plant accident, the candidate home port for the n.s. Mutsu and the results of its site survey. (J.P.N.)

  14. Conclusions from collision examinations for nuclear merchant ships in the FRG

    International Nuclear Information System (INIS)

    Woisin, G.

    1978-01-01

    In Germany model tests have been performed for the utilization of a resisting type barrier instead of an energy absorbing type barrier, the latter used in nuclear merchant ships up to now only. After reviewing the model technique the results of nine tests with the new barrier are discussed. Calculations performed to the newly raised questions of the shock accelerations of the reactor plant and of possible overstressing of the hull are reported. The new design has many advantages with respect to safety and to the arrangement of a reactor plant in a ship too. Some questions partly remain unanswered at the moment concerning oblique collisions to the ends of the barrier and the possible effects of bulk cargo in holds close to the bow in striking ships of smaller size

  15. Incentives for the allowance of burnup credit in the design of spent nuclear fuel shipping casks

    International Nuclear Information System (INIS)

    Sanders, T.L.; Westfall, R.M.; Jones, R.H.

    1987-01-01

    An analysis has been completed which indicates that the consideration of spent fuel histories ('burnup credit') in the criticality design of spent fuel shipping casks could result in considerable public risk benefits and cost savings in the transport of spent nuclear fuel. Capacities of casks could be increased considerably in some cases. These capacity increases result in lower public and occupational exposures to ionizing radiation due to the reduced number of shipments necessary to transport a given amount of fuel. Additional safety benefits result from reduced non-radiological risks to both public and occupational sectors. In addition, economic benefits result from lower in-transit shipping costs, reduced transportation fleet capital costs, and fewer cask handling requirements at both shipping and receiving facilities

  16. Shielding designs and tests of a new exclusive ship for transporting spent nuclear fuels

    International Nuclear Information System (INIS)

    Ono, M.; Ito, D.; Kitano, T.; Ueki, K.; Akiyama, H.; Obara, I.; Sanui, T.

    2000-01-01

    The Rokuei-Maru, a ship built specially for the transport of spent nuclear fuels in casks, was launched April in 1996. She is the first ship to comply with special Japanese regulations, KAISA 520, based on the INF code. DOT3.5 and MCNP-4A were used for the evaluation of dose equivalent rates of her shielding structures. On-board gamma-ray shielding tests were executed to confirm the effectiveness of the ship's shielding performance. The tests confirmed that effective shielding has been achieved and the dose equivalent rate in the accommodation and other inhabited spaces is sufficiently lower than the regulated limitations. This was achieved by employing the appropriate calculation methods and shielding materials. (author)

  17. An integrated pusher-guide-boat for ship nuclear propulsion

    International Nuclear Information System (INIS)

    Baujat, Jacques.

    1974-01-01

    The pusher guide-boat is characterized in that it comprises a streamlined enclosure with a front surface and an upper surface, containing a nuclear-power generating plant and means for converting the thus-generated power into mechanical energy used for actuating the pusher-boat propelling parts situated rearwardly, and in that the streamlined enclosure comprises, on its front surface and on at least a portion of its upper surface, areas for the contact thereof with respective portions of the vessel driven by said pusher-boat and means for fastening the latter to the vessel, said pusher-boat being also provided with water-ballasts [fr

  18. Statistics of meteorology for dose evaluation of crews of nuclear ship

    International Nuclear Information System (INIS)

    Imai, Kazuhiko; Chino, Masamichi

    1981-01-01

    For the purpose of the dose evaluation of crews of a nuclear ship, the statistics of wind speed and direction relative to the ship is discussed, using wind data which are reported from ships crusing sea around Japan Island. The analysis on the data shows that the occurrence frequency of wind speed can be fitted with the γ-distribution having parameter p around 3 and wind direction frequency can be treated as a uniform distribution. Using these distributions and taking the ship speed u 3 and the long-term mean speed of natural wind anti u as constant parameters, frequency distribution of wind speed and direction relative to the ship was calculated and statistical quantities necessary for dose evaluation were obtained in the way similar to the procedure for reactor sites on land. The 97% value of wind speed u 97 , which should be used in the dose evaluation for accidental releases may give conservative doses, if it is evaluated as follows, u 97 = 0.64 u sub(s) in the cases u sub(s) > anti u, and u 97 = 0.86 anti u in the cases u sub(s) < anti u including u sub(s) = 0. (author)

  19. Passage of nuclear powered ships in territorial waters and their stay in harbours

    International Nuclear Information System (INIS)

    Lucchini, L.; Voelckel, M.

    1975-01-01

    The specificity of rules governing entry of nuclear ships in the territorial waters of a State and their liability are reviewed. The concept of innocent passage prevailing for navigation in territorial waters is examined as are the protective measures taken by the Host State, in particular the prior authorisation characterizing thate State's discretionary powers of acceptance or refusal to admit the nuclear ship and the control over it. Liability rules and the nature of liability are analysed on the basis of agreements on the Savannah and the Otto Hahn. The importance of State intervention is demonstrated in its relationship with the operator particularly regarding control of operation and financial assistance. Also mentioned is liability for breach of the rules of procedure laid down in bilateral agreements, and in this context, a study is made of the rules of conduct for nuclear ships in territorial waters set out in the Savannah and Otto Hahn agreements. The liability of the coastal State is reviewed from the viewpoint of its grounds and possibilities of extension, given the development of nuclear navigation and the importance attached to protection against marine environmental pollution [fr

  20. Development of advanced automatic operation system for nuclear ship. 1. Perfect automatic normal operation

    International Nuclear Information System (INIS)

    Nakazawa, Toshio; Yabuuti, Noriaki; Takahashi, Hiroki; Shimazaki, Junya

    1999-02-01

    Development of operation support system such as automatic operating system and anomaly diagnosis systems of nuclear reactor is very important in practical nuclear ship because of a limited number of operators and severe conditions in which receiving support from others in a case of accident is very difficult. The goal of development of the operation support systems is to realize the perfect automatic control system in a series of normal operation from the reactor start-up to the shutdown. The automatic control system for the normal operation has been developed based on operating experiences of the first Japanese nuclear ship 'Mutsu'. Automation technique was verified by 'Mutsu' plant data at manual operation. Fully automatic control of start-up and shutdown operations was achieved by setting the desired value of operation and the limiting value of parameter fluctuation, and by making the operation program of the principal equipment such as the main coolant pump and the heaters. This report presents the automatic operation system developed for the start-up and the shutdown of reactor and the verification of the system using the Nuclear Ship Engineering Simulator System. (author)

  1. Monitoring of Radionuclides in Ship Ballast Water Following the Fukushima Nuclear Accident

    International Nuclear Information System (INIS)

    Abdul Kadir Ishak; Wo, Y.M.; Muhamat Omar

    2011-01-01

    Ballast water is the waters taken into the ship compartment to provide stability. It is taken on board at the port before the voyage begins and discharged at the port of call (arrival) while loading cargoes. Ballast is primarily composed of water and is full of stones, sediment, and thousands of living species. The quantity of water taken depends on the size of the ship and it can reach up to 10,000 tonnes. As a well known fact, Daiichi nuclear plant in Fukushima had released radioactive contaminated water into its surrounding sea and being dispersed by currents and tides. Therefore, ships travel between Malaysia and Japan in particular those from the affected regions and travel to Malaysia without cargoes will have a risk of transporting back radioactive contaminated water from Japan and released it at local ports. Malaysian Marine Department with the cooperation of Malaysian Nuclear Agency have been analysing the concentrations of several radionuclides in the ship's ballast water and sediment. This is to ensure the effective dosage is safe to the crews and general public as well to fulfill the permissible limit of 1 mSv/yr gazetted by the authorities. It is also to monitor that the contaminated water is not discharged into our marine environment. (author)

  2. Shielding analysis method applied to nuclear ship 'MUTSU' and its evaluation based on experimental analyses

    International Nuclear Information System (INIS)

    Yamaji, Akio; Miyakoshi, Jun-ichi; Iwao, Yoshiaki; Tsubosaka, Akira; Saito, Tetsuo; Fujii, Takayoshi; Okumura, Yoshihiro; Suzuoki, Zenro; Kawakita, Takashi.

    1984-01-01

    Procedures of shielding analysis are described which were used for the shielding modification design of the Nuclear Ship ''MUTSU''. The calculations of the radiation distribution on board were made using Sn codes ANISN and TWOTRAN, a point kernel code QAD and a Monte Carlo code MORSE. The accuracies of these calculations were investigated through the analysis of various shielding experiments: the shield tank experiment of the Nuclear Ship ''Otto Hahn'', the shielding mock-up experiment for ''MUTSU'' performed in JRR-4, the shielding benchmark experiment using the 16 N radiation facility of AERE Harwell and the shielding effect experiment of the ship structure performed in the training ship ''Shintoku-Maru''. The values calculated by the ANISN agree with the data measured at ''Otto Hahn'' within a factor of 2 for fast neutrons and within a factor of 3 for epithermal and thermal neutrons. The γ-ray dose rates calculated by the QAD agree with the measured values within 30% for the analysis of the experiment in JRR-4. The design values for ''MUTSU'' were determined in consequence of these experimental analyses. (author)

  3. Knowledge-based full-automatic control system for a nuclear ship reactor

    International Nuclear Information System (INIS)

    Shimazaki, J.; Nakazawa, T.; Yabuuchi, N.

    2000-01-01

    Plant operations aboard nuclear ships require quick judgements and actions due to changing marine conditions such as wind, waves and currents. Furthermore, additional human support is not available for nuclear ship operation at sea, so advanced automatic operations are necessary to reduce the number of operators required finally. Therefore, an advanced automatic operating system has been developed based on operational knowledge of nuclear ship 'Mutsu' plant. The advanced automatic operating system includes both the automatic operation system and the operator-support system which assists operators in completing actions during plant accidents, anomaly diagnosis and plant supervision. These system are largely being developed using artificial intelligent techniques such as neural network, fuzzy logic and knowledge-based expert. The automatic operation system is fundamentally based upon application of an operator's knowledge of both normal (start-up to rated power level) and abnormal (after scram) operations. Comparing plant behaviors from start-up to power level by the automatic operation with by 'Mutsu' manual operation, stable automatic operation was obtained almost same as manual operation within all operating limits. The abnormal automatic system was for hard work of manual operations after scram or LOCA accidents. An integrating system with the normal and the abnormal automatic systems are being developed for interacting smoothly both systems. (author)

  4. Probabilistic risk assessment on maritime spent nuclear fuel transportation (Part II: Ship collision probability)

    International Nuclear Information System (INIS)

    Christian, Robby; Kang, Hyun Gook

    2017-01-01

    This paper proposes a methodology to assess and reduce risks of maritime spent nuclear fuel transportation with a probabilistic approach. Event trees detailing the progression of collisions leading to transport casks’ damage were constructed. Parallel and crossing collision probabilities were formulated based on the Poisson distribution. Automatic Identification System (AIS) data were processed with the Hough Transform algorithm to estimate possible intersections between the shipment route and the marine traffic. Monte Carlo simulations were done to compute collision probabilities and impact energies at each intersection. Possible safety improvement measures through a proper selection of operational transport parameters were investigated. These parameters include shipment routes, ship's cruise velocity, number of transport casks carried in a shipment, the casks’ stowage configuration and loading order on board the ship. A shipment case study is presented. Waters with high collision probabilities were identified. Effective range of cruising velocity to reduce collision risks were discovered. The number of casks in a shipment and their stowage method which gave low cask damage frequencies were obtained. The proposed methodology was successful in quantifying ship collision and cask damage frequency. It was effective in assisting decision making processes to minimize risks in maritime spent nuclear fuel transportation. - Highlights: • Proposes a probabilistic framework on the safety of spent nuclear fuel transportation by sea. • Developed a marine traffic simulation model using Generalized Hough Transform (GHT) algorithm. • A transportation case study on South Korean waters is presented. • Single-vessel risk reduction method is outlined by optimizing transport parameters.

  5. Report of the Committee on the Survey of Hull Bottom of Nuclear Ship Mutsu

    International Nuclear Information System (INIS)

    1979-01-01

    The nuclear ship Mutsu arrived the Sasebo Shipyard, Sasebo Heavy Industries Co., Ltd., in October, 1978, to repair the shielding for the reactor and to inspect generally the safety. The docking works were not carried out since 1972 for the Mutsu, therefore it was decided to admit the Mutsu in a dock to put the hull in order. To prepare for starting the output test again, it is necessary to grasp the state of the hull part below water line and take appropriate measures as occasions demand, therefore the Japan Nuclear Ship Development Agency established the Committee on the Survey of Hull Bottom of Nuclear Ship Mutsu in July, 1979. Three meetings of the committee were held from July 2 to September 19, and the draft of the report was drawn up. The Mutsu entered No. 5 dock of the Sasebo Shipyard on July 9, and left on July 23, and the survey of the hull bottom was carried out during that period. The results of the survey are reported as follows: the state of bottom shell plates, the state of aft part and the propeller, the state of sea chests, the state of the electrical corrosion protection of bottom shell plates and the state of sea valves. The problem to be specially mentioned was not found, and it was recognized that the sound maintenance has been carried out. (Kako, I.)

  6. A comparison of recent results from HONDO III with the JSME nuclear shipping cask benchmark calculations

    International Nuclear Information System (INIS)

    Key, S.W.

    1985-01-01

    The results of two calculations related to the impact response of spent nuclear fuel shipping casks are compared to the benchmark results reported in a recent study by the Japan Society of Mechanical Engineers Subcommittee on Structural Analysis of Nuclear Shipping Casks. Two idealized impacts are considered. The first calculation utilizes a right circular cylinder of lead subjected to a 9.0 m free fall onto a rigid target, while the second calculation utilizes a stainless steel clad cylinder of lead subjected to the same impact conditions. For the first problem, four calculations from graphical results presented in the original study have been singled out for comparison with HONDO III. The results from DYNA3D, STEALTH, PISCES, and ABAQUS are reproduced. In the second problem, the results from four separate computer programs in the original study, ABAQUS, ANSYS, MARC, and PISCES, are used and compared with HONDO III. The current version of HONDO III contains a fully automated implementation of the explicit-explicit partitioning procedure for the central difference method time integration which results in a reduction of computational effort by a factor in excess of 5. The results reported here further support the conclusion of the original study that the explicit time integration schemes with automated time incrementation are effective and efficient techniques for computing the transient dynamic response of nuclear fuel shipping casks subject to impact loading. (orig.)

  7. 46 CFR 78.33-5 - Accidents to machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 3 2010-10-01 2010-10-01 false Accidents to machinery. 78.33-5 Section 78.33-5 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) PASSENGER VESSELS OPERATIONS Reports of Accidents, Repairs, and Unsafe Equipment § 78.33-5 Accidents to machinery. (a) In the event of an accident...

  8. 46 CFR 185.208 - Accidents to machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Accidents to machinery. 185.208 Section 185.208 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) SMALL PASSENGER VESSELS (UNDER 100 GROSS TONS) OPERATIONS Marine Casualties and Voyage Records § 185.208 Accidents to machinery. The owner, managing...

  9. 46 CFR 122.208 - Accidents to machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Accidents to machinery. 122.208 Section 122.208 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) SMALL PASSENGER VESSELS CARRYING MORE THAN 150... Voyage Records § 122.208 Accidents to machinery. The owner, managing operator, or master shall report...

  10. 46 CFR 109.205 - Inspection of boilers and machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Inspection of boilers and machinery. 109.205 Section 109... OPERATIONS Tests, Drills, and Inspections § 109.205 Inspection of boilers and machinery. The chief engineer or engineer in charge, before he assumes charge of the boilers and machinery of a unit shall inspect...

  11. 46 CFR 252.33 - Hull and machinery insurance.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Hull and machinery insurance. 252.33 Section 252.33... Subsidy Rates § 252.33 Hull and machinery insurance. (a) Subsidy items. The fair and reasonable net premium costs (including stamp taxes) of hull and machinery, increased value, excess general average...

  12. 46 CFR 282.23 - Hull and machinery insurance.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Hull and machinery insurance. 282.23 Section 282.23... COMMERCE OF THE UNITED STATES Calculation of Subsidy Rates § 282.23 Hull and machinery insurance. (a) Subsidy items. The fair and reasonable net premium costs (including stamp taxes) of hull and machinery...

  13. 46 CFR 196.30-5 - Accidents to machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Accidents to machinery. 196.30-5 Section 196.30-5... Reports of Accidents, Repairs, and Unsafe Equipment § 196.30-5 Accidents to machinery. (a) In the event of an accident to a boiler, unfired pressure vessel, or machinery tending to render the further use of...

  14. STEADY-SHIP: a computer code for three-dimensional nuclear and thermal-hydraulic analyses of marine reactors

    International Nuclear Information System (INIS)

    Itagaki, Masafumi; Naito, Yoshitaka; Tokuno, Yukio; Matsui, Yasushi.

    1988-01-01

    A code STEADY-SHIP has been developed to calculate three-dimensional distributions of neutron flux, power and coolant temperature in the reactor core of the nuclear ship MUTSU. The code consists of two parts, that is, a few-group three-dimensional neutron diffusion module DIFFUSION-SHIP and a thermal-hydraulic module HYDRO-SHIP: In the DIFFUSION-SHIP the leakage iteration method is used for solving the three-dimensional neutron diffusion equation with small computer core memory and short computing time; The HYDRO-SHIP performs the general thermal-hydraulic calculation for evaluating feedbacks required in the neutronic calculation by the DIFFUSION-SHIP. The macroscopic nuclear constants are generated by a module CROSS-SHIP as functions of xenon poison, fuel temperature, moderator temperature and moderator density. A module LOCAL-FINE has the capability of computing a detailed rod power distribution for each local node in the core, using the boundary conditions on the surface of the node which were supplied by the STEADY-SHIP whole-core calculation. The applicability of this code to marine reactors has been demonstrated by comparing the computed results with the data measured during the MUTSU land-loaded core critical experiments and with the data obtained during the hot-zero-power tests performed for the actual MUTSU plant. (author)

  15. Case study for one-piece removal method of reactor vessel of nuclear ship 'Mutsu'

    International Nuclear Information System (INIS)

    Nagane, Satoru; Kitahara, Katsumi; Yoshikawa, Seiji; Miyasaka, Yasuhiko; Fukumura, Nobuo; Nisizawa, Ichiou

    2010-01-01

    A reactor installed at the center part of the nuclear ship 'Mutsu' has been stored safely and exhibited in a reactor room building since 1996. The reactor vessel and its internals are key components because of main radioactive wastes for the reasonable decommissioning plan in the future. This report describes the one-piece removal method as the one package of the reactor vessel with its internals intact with a shipping container or additional shields. The reactor vessel package (Max.100ton) will be classified acceptable for burial at the low level radioactive waste (LLW), which will be buried at a LLW pit facility under waste disposal regulations. And also, the package will be classified as an IP-2-equivalent package according to the requirement for Shipments and Packagings. (author)

  16. Reactor dynamics experiment of nuclear ship Mutsu using pseudo random signal (II). The second experiment

    International Nuclear Information System (INIS)

    Hayashi, Koji; Shimazaki, Junya; Nabeshima, Kunihiko; Ochiai, Masaaki; Shinohara, Yoshikuni; Inoue, Kimihiko.

    1995-01-01

    In order to investigate dynamics of the reactor plant of the nuclear ship Mutsu, the second reactor noise experiment using pseudo random binary sequences (PRBS) was performed on August 30, 1991 in the third experimental navigation. The experiments using both reactivity and load disturbances were performed at 50% of reactor power and under a quiet sea condition. Each PRBS was applied by manual operation of the control rod or the main steam valve. Various signals of the plant responses and of the acceleration of ship motion were measured. Furthermore, natural reactor noise signals were measured after each PRBS experiment in order to evaluate the effects of the PRBS disturbances. This paper summarizes the planning of the experiment, the instruction for the experiment and logs, the data recording conditions, recorded signal wave forms and the results of power spectral analysis. (author)

  17. Reactor dynamics experiment of nuclear ship Mutsu using pseudo random signal (III). The third experiment

    International Nuclear Information System (INIS)

    Hayashi, Koji; Shimazaki, Junya; Nabeshima, Kunihiko; Ochiai, Masaaki; Shinohara, Yoshikuni; Inoue, Kimihiko.

    1995-03-01

    In order to investigate dynamics of the reactor plant of the nuclear ship Mutsu, the third reactor noise experiment using pseudo random binary sequences (PRBS) was performed on September 16, 1991 in the third experimental navigation. The experiments using both reactivity and load disturbances were performed at 70% of reactor power and under a normal sea condition. Each PRBS was applied by manual operation of the control rod or the main steam valve. Various signals of the plant responses and of the acceleration of ship motion were measured. Furthermore, natural reactor noise signals were measured after each PRBS experiment in order to evaluate the effects of the PRBS disturbances. This paper summarizes the planning of the experiment, the instruction for the experiment and logs, the data recording conditions, recorded signal wave forms and the results of power spectral analysis. (author)

  18. Ship-Based Nuclear Energy Systems for Accelerating Developing World Socioeconomic Advance

    Science.gov (United States)

    Petroski, Robert; Wood, Lowell

    2014-07-01

    Technological, economic, and policy aspects of supplying energy to newly industrializing and developing countries using ship-deployed nuclear energy systems are described. The approach analyzed comprises nuclear installations of up to gigawatt scale deployed within currently mass-produced large ship hulls which are capable of flexibly supplying energy for electricity, water desalination and district heating-&-cooling with low latencies and minimized shoreside capital expenditures. Nuclear energy is uniquely suited for mobile deployment due to its combination of extraordinary energy density and high power density, which enable enormous supplies of energy to be deployed at extremely low marginal costs. Nuclear installations on ships also confer technological advantages by essentially eliminating risk from earthquakes, tsunamis, and floods; taking advantage of assured access to an effectively unlimited amount of cooling water, and involving minimal onshore preparations and commitments. Instances of floating nuclear power stations that have been proposed in the past, some of which are currently being pursued, have generally been based on conventional LWR technology, moreover without flexibility or completeness of power output options. We consider nuclear technology options for their applicability to the unique opportunities and challenges of a marine environment, with special attention given to low-pressure, high thermal margin systems with continuous and assured afterheat dissipation into the ambient seawater. Such systems appear promising for offering an exceptionally high degree of safety while using a maximally simple set of components. We furthermore consider systems tailored to Developing World contexts, which satisfy societal requirements beyond electrification, e.g., flexible sourcing of potable water and HVAC services, servicing time-varying user requirements, and compatibility with the full spectrum of local renewable energy supplies, specifically including

  19. An adaptive simulation model for analysis of nuclear material shipping operations

    International Nuclear Information System (INIS)

    Boerigter, S.T.; Sena, D.J.; Fasel, J.H.

    1998-01-01

    Los Alamos has developed an advanced simulation environment designed specifically for nuclear materials operations. This process-level simulation package, the Process Modeling System (ProMoS), is based on high-fidelity material balance criteria and contains intrinsic mechanisms for waste and recycle flows, contaminant estimation and tracking, and material-constrained operations. Recent development efforts have focused on coupling complex personnel interactions, personnel exposure calculations, and stochastic process-personnel performance criteria to the material-balance simulation. This combination of capabilities allows for more realistic simulation of nuclear material handling operations where complex personnel interactions are required. They have used ProMoS to assess fissile material shipping performance characteristics at the Los Alamos National Laboratory plutonium facility (TA-55). Nuclear material shipping operations are ubiquitous in the DOE complex and require the largest suite of varied personnel interacting in a well-timed manner to accomplish the task. They have developed a baseline simulation of the present operations and have estimated the operational impacts and requirement of the pit production mission at TA-55 as a result of the SSM-PEIS. Potential bottlenecks have been explored and mechanisms for increasing operational efficiency are identified

  20. Modification of the Japanese first nuclear ship reactor for a regional energy supply system

    International Nuclear Information System (INIS)

    Sato, K.; Shimazu, Y.; Narabayashi, T.; Tsuji, M.

    2008-01-01

    Nuclear Ship Mutsu was developed as the first experimental nuclear ship of Japan. It has several advantages as a prototype for regional energy supply system. Considering the attractive advantages of the Mutsu reactor, we investigated the feasibility of development of a small regional energy system by adopting the Mutsu reactor as a starting model. The system could supply with not only electricity but also heat. Heat could be used for hot-water supply, a heating system of a house, melting snow and so on, especially for those in northern part of Japan. The system should satisfy the requirements for GEN IV systems and the current regulations. From this point of view, the modification of the reactor was initiated by taking into improvements and technology of the state of arts to fulfill the requirements such as (1) Longer core life without refueling, (2) Reactivity adjustment for load change without control rods or soluble boron, (3) Simpler operations for load changes and (4) Ultimate safety with sufficient passive capability. Currently it is assumed to use basic standard 17x17 fuel assembly design for WH type PWRs. Nuclear design calculations are carried out by 'SRAC 2002 ', which has been developed in Japan Atomic Energy Agency. Several problems have not been solved yet, but we confirmed the proposed core has about 10 years life time. So the proposed core has a possibility to be used for a small regional energy system. (authors)

  1. 46 CFR 32.35-1 - Boilers and machinery-TB/ALL.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 1 2010-10-01 2010-10-01 false Boilers and machinery-TB/ALL. 32.35-1 Section 32.35-1 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY TANK VESSELS SPECIAL EQUIPMENT, MACHINERY, AND HULL REQUIREMENTS Main and Auxiliary Machinery § 32.35-1 Boilers and machinery—TB/ALL. Boilers, main and auxiliary...

  2. 46 CFR 169.631 - Separation of machinery and fuel tank spaces from accommodation spaces.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Separation of machinery and fuel tank spaces from accommodation spaces. 169.631 Section 169.631 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED... machinery and fuel tank spaces from accommodation spaces. (a) Machinery and fuel tank spaces must be...

  3. 46 CFR 169.629 - Compartments containing gasoline machinery or fuel tanks.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Compartments containing gasoline machinery or fuel tanks. 169.629 Section 169.629 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) NAUTICAL... gasoline machinery or fuel tanks. Spaces containing gasoline machinery or fuel tanks must have natural...

  4. Building of Nuclear Ship Engineering Simulation System development of the simulator for the integral type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Takahashi, Teruo; Shimazaki, Junya; Yabuuchi, Noriaki; Fukuhara, Yosifumi; Kusunoki, Takeshi; Ochiai, Masaaki [Department of Nuclear Energy Systems, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan); Nakazawa, Toshio [Department of HTTR Project, Oarai Research Establishment, Japan Atomic Energy Research Institute, Oarai, Ibaraki (Japan)

    2000-03-01

    JAERI had carried out the design study of a light-weight and compact integral type reactor of power 100 MW{sub th} with passive safety as a power source for the future nuclear ships, and completed an engineering design. To confirm the design and operation performance and to utilize the study of automation of the operations of reactor, we developed a real-time simulator for the integral type reactor. This simulator is a part of Nuclear Ship Engineering Simulation System (NESSY) and on the same hardware as 'Mutsu' simulator which was developed to simulate the first Japanese nuclear ship Mutsu'. Simulation accuracy of 'Mutsu' simulator was verified by comparing the simulation results With data got in the experimental voyage of 'Mutsu'. The simulator for the integral type reactor uses the same programs which were used in 'Mutsu' simulator for the separate type PWR, and the simulated results are approximately consistent with the calculated values using RELAP5/MOD2 (The later points are reported separately). Therefore simulation accuracy of the simulator for the integral type reactor is also expected to be reasonable, though it is necessary to verify by comparing with the real plant data or experimental data in future. We can get the perspectives to use as a real-time engineering simulator and to achieve the above-mentioned aims. This is a report on development of the simulator for the integral type reactor mainly focused on the contents of the analytical programs expressed the structural features of reactor. (author)

  5. 46 CFR 91.15-1 - Standards in inspection of hulls, boilers, and machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Standards in inspection of hulls, boilers, and machinery... hulls, boilers, and machinery. In the inspection of hulls, boilers, and machinery of vessels, the..., respecting material and inspection of hulls, boilers, and machinery, and the certificate of classification...

  6. 46 CFR 189.15-1 - Standards in inspection of hulls, boilers, and machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Standards in inspection of hulls, boilers, and machinery... inspection of hulls, boilers, and machinery. In the inspection of hulls, boilers, and machinery of vessels... chapter, respecting material and construction of hulls, boilers, and machinery, and certificate of...

  7. 46 CFR 71.15-1 - Standards in inspection of hulls, boilers, and machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 3 2010-10-01 2010-10-01 false Standards in inspection of hulls, boilers, and machinery..., boilers, and machinery. In the inspection of hulls, boilers, and machinery of vessels, the standards... and inspection of hulls, boilers, and machinery, and the certificate of classification referring...

  8. The PEACE PIPE: Recycling nuclear weapons into a TRU storage/shipping container

    International Nuclear Information System (INIS)

    Floyd, D.; Edstrom, C.; Biddle, K.; Orlowski, R.; Geinitz, R.; Keenan, K.; Rivera, M.

    1997-01-01

    This paper describes results of a contract undertaken by the National Conversion Pilot Project (NCPP) at the Rocky Flats Environmental Technology Site (RFETS) to fabricate stainless steel ''pipe'' containers for use in certification testing at Sandia National Lab, Albuquerque to qualify the container for both storage of transuranic (TRU) waste at RFETS and other DOE sites and shipping of the waste to the Waste Isolation Pilot Project (WIPP). The paper includes a description of the nearly ten-fold increase in the amount of contained plutonium enabled by the product design, the preparation and use of former nuclear weapons facilities to fabricate the components, and the rigorous quality assurance and test procedures that were employed. It also describes how stainless steel nuclear weapons components can be converted into these pipe containers, a true ''swords into plowshare'' success story

  9. The Brussels Nuclear Ship Convention and its impact on the German Atomic Energy Act

    International Nuclear Information System (INIS)

    Bernaerts, A.

    1976-01-01

    Although the Brussels Nuclear Ship Liability Convention of 1962, whose incorporation into German law was agreed upon by the German Federal Parliament (the Bundestag) in 1975, will have only minor international significance once it has entered into force, it will yet provide a new legal basis for the nuclear liability of the German vessel N.S. 'Otto Hahn' for the periods of her stay within the Federal Republic of Germany. However, there is no smooth concurrence of the Brussels Convention and the German Atomic Energy Act adapted to the Paris Liability Convention in 1975. This means that a number of questions still need to be resolved with respect to the protection of victims and the liability of shipowners. (orig.) [de

  10. The analysis of thermal-hydraulic performances of nuclear ship reactor

    International Nuclear Information System (INIS)

    Wakabayashi, Shinshichi; Hamada, Masao

    1975-01-01

    Thermal-hydraulic performances in the core of nuclear ship reactor was analysed by thermal-hydraulic analyser codes, AMRTC and COBRA-11+DNBCAL. This reactor is of a pressurized water type and incorporates the steam generator within the reactor vessel with the rated power of 330 MWt, which is developed by Nuclear Ship Research Panel Seven (NSR-7) in The Shipbuilding Research Association of Japan. Fuel temperature distributions, coolant temperature distributions, void fractions in coolant and minimum burn out ratio etc. were calculated. Results are as follows; a) The maximum temperature of fuel center is 1,472 0 C that corresponds to 53% as small as the melting point (2,800 0 C). b) Subcooled boiling exists in the core and the maximum void fraction is less than 4%. c) The minimum burn out ratio is not less than the minimum allowable limit of 1.25. It was found from the results of analysis that this reactor was able to be operated wide margin with respect to thermal-hydraulic design limits at the rated power. (auth.)

  11. Nuclear Structure of the Heaviest Elements – Investigated at SHIP-GSI

    Directory of Open Access Journals (Sweden)

    Heßberger Fritz Peter

    2014-03-01

    Full Text Available The quest for the heaviest nuclei that can exist is a basic topic in natural science as their stability is characterized by a delicate interplay of short range nuclear forces acting between the nucleons (protons and neutrons and long-range Coulomb forces acting solely between charged particles, i.e. the protons. As the stability of a nucleus is strongly correlated to its structure, understanding the nuclear structure of heaviest nuclei is presently a main challenge of experimental and theoretical investigations concerning the field of Superheavy Elements. At the velocity filter SHIP at GSI Darmstadt an extensive program on nuclear structure investigations has been started about a decade ago. The project covered both as well systematic investigations of single particle levels in odd-mass isotopes populated by α-decay as investigation of two- or fourquasi-particle states forming K isomers and was supplemented by direct mass measurements at SHIPTRAP and investigation of spontaneous fission properties. Recent experimental studies allowed to extend the systematics of low lying levels in N = 151 and N = 153 up to 255Rf and 259Sg, investigation of possible relations between nuclear structure and fission properties of odd-mass nuclei and investigation of shell strengths at N = 152 and towards N = 162.

  12. Investigation of active interrogation techniques to detect special nuclear material in maritime environments: Boarded search of a cargo container ship

    International Nuclear Information System (INIS)

    Grogan, Brandon R.; Henkel, James J.; Johnson, Jeffrey O.; Mihalczo, John T.; Miller, Thomas M.; Patton, Bruce W.

    2013-01-01

    The detonation of a terrorist nuclear weapon in the United States would result in the massive loss of life and grave economic damage. Even if a device was not detonated, its known or suspected presence aboard a cargo container ship in a U.S. port would have major economic and political consequences. One possible means to prevent this threat would be to board a ship at sea and search for the device before it reaches port. The scenario considered here involves a small Coast Guard team with strong intelligence boarding a container ship to search for a nuclear device. Using active interrogation, the team would nonintrusively search a block of shipping containers to locate the fissile material. Potential interrogation source and detector technologies for the team are discussed. The methodology of the scan is presented along with a technique for calculating the required interrogation source strength using computer simulations. MCNPX was used to construct a computer model of a container ship, and several search scenarios were simulated. The results of the simulations are presented in terms of the source strength required for each interrogation scenario. Validation measurements were performed in order to scale these simulation results to expected performance. Interrogations through the short (2.4 m) axis of a standardized shipping container appear to be feasible given the entire range of container loadings tested. Interrogations through several containers at once or a single container through its long (12.2 m) axis do not appear to be viable with a portable interrogation system

  13. Investigation of active interrogation techniques to detect special nuclear material in maritime environments: Boarded search of a cargo container ship

    Energy Technology Data Exchange (ETDEWEB)

    Grogan, Brandon R., E-mail: groganbr@ornl.gov; Henkel, James J.; Johnson, Jeffrey O.; Mihalczo, John T.; Miller, Thomas M.; Patton, Bruce W.

    2013-12-01

    The detonation of a terrorist nuclear weapon in the United States would result in the massive loss of life and grave economic damage. Even if a device was not detonated, its known or suspected presence aboard a cargo container ship in a U.S. port would have major economic and political consequences. One possible means to prevent this threat would be to board a ship at sea and search for the device before it reaches port. The scenario considered here involves a small Coast Guard team with strong intelligence boarding a container ship to search for a nuclear device. Using active interrogation, the team would nonintrusively search a block of shipping containers to locate the fissile material. Potential interrogation source and detector technologies for the team are discussed. The methodology of the scan is presented along with a technique for calculating the required interrogation source strength using computer simulations. MCNPX was used to construct a computer model of a container ship, and several search scenarios were simulated. The results of the simulations are presented in terms of the source strength required for each interrogation scenario. Validation measurements were performed in order to scale these simulation results to expected performance. Interrogations through the short (2.4 m) axis of a standardized shipping container appear to be feasible given the entire range of container loadings tested. Interrogations through several containers at once or a single container through its long (12.2 m) axis do not appear to be viable with a portable interrogation system.

  14. Nuclear Criticality Safety Evaluation of the 9965, 9968, 9972, 9973, 9974, and 9975 Shipping Casks

    International Nuclear Information System (INIS)

    Frost, R.L.

    1999-01-01

    A Nuclear Criticality Safety Evaluation (NCSE) has been performed for the 9965, 9968, 9972, 9973, 9974, and 9975 SRS-designed shipping casks. This was done in support of the recertification effort for the 9965 and 9968, and the certification of the newly designed 9972-9975 series. The analysis supports the use of these packages as Fissile Class I for shipment of fissionable material from the SRS FB-Line, HB-Line, and from Lawrence Livermore national Laboratory. six different types of material were analyzed with varying Isotopic composition, of both oxide and metallic form. The mass limits required to support the fissile Class I rating for each of the envelopes are given in the Table below. These mass limits apply if DOE approves an exception as described in 10 CFR 71.55(c), such that water leakage into the primary containment vessel does not need to be considered in the criticality analysis. If this exception is not granted, the mass limits are lower than those shown below. this issue is discussed in detail in sections 5 and 6 of the report.One finding from this work is important enough to highlight in the abstract. The fire tests performed for this family of shipping casks indicates only minimal charring of the Celotex thermal insulation. Analysis of the casks with no Celotex insulation (assuming it has all burned away), results in values of k-eff that exceed 1.0. Therefore, the Celotex insulation must remain intact in order to guarantee sub criticality of the 9972-9975 family of shipping casks

  15. Full scale simulations of accidents on spent-nuclear-fuel shipping systems

    International Nuclear Information System (INIS)

    Yoshimura, H.R.

    1978-01-01

    In 1977 and 1978, five first-of-a-kind full scale tests of spent-nuclear-fuel shipping systems were conducted at Sandia Laboratories. The objectives of this broad test program were (1) to assess and demonstrate the validity of current analytical and scale modeling techniques for predicting damage in accident conditions by comparing predicted results with actual test results, and (2) to gain quantitative knowledge of extreme accident environments by assessing the response of full scale hardware under actual test conditions. The tests were not intended to validate the present regulatory standards. The spent fuel cask tests fell into the following configurations: crashes of a truck-transport system into a massive concrete barrier (100 and 130 km/h); a grade crossing impact test (130 km/h) involving a locomotive and a stalled tractor-trailer; and a railcar shipping system impact into a massive concrete barrier (130 km/h) followed by fire. In addition to collecting much data on the response of cask transport systems, the program has demonstrated thus far that current analytical and scale modeling techniques are valid approaches for predicting vehicular and cask damage in accident environments. The tests have also shown that the spent casks tested are extremely rugged devices capable of retaining their radioactive contents in very severe accidents

  16. Nuclear waste shipping container response to severe accident conditions, A brief critique of the modal study

    International Nuclear Information System (INIS)

    Audin, L.

    1990-12-01

    The Modal Study (NUREG/CR-4829) attempts to upgrade the analysis of spent nuclear fuel transportation accidents, and to verify the validity of the present regulatory scheme of cask performance standards as a means to minimize risk. While an improvement over many prior efforts in this area (such as NUREG-0170), it unfortunately fails to create a realistic simulation either of a shipping cask, the severe conditions to which it could be subjected, or the potential damage to the spent fuel cargo during an accident. There are too many deficiencies in its analysis to allow acceptance of its results for the presumed cask design, and many pending changes in new containers, cargoes and shipping patterns will limit applicability of the Modal Study to future shipments. In essence, the Modal Study is a good start, but is too simplistic, incomplete, outdated and open to serious question to be used as the basis for any present-day environmental or risk assessment of spent fuel transportation. It needs to be redone, with peer review during its production and experimental verification of its assumptions, before it has any relevance to the shipments planned to Yucca Mountain. Finally, it must be expanded into a full risk assessment by inputing its radiological release fractions and probabilities into a valid dispersal simulation to properly determine the impact of its results. 51 refs

  17. Results of the power-up test of the nuclear-powered ship MUTSU and test programs of her experimental voyages

    International Nuclear Information System (INIS)

    Ochiai, Masa-aki; Ishida, Toshihisa; Itagaki, Masafumi; Sakamoto, Yukio; Kyouya, Masahiko

    1991-01-01

    The power-up test of N.S. MUTSU was performed successfully almost on schedule in spite of minor troubles resolved in a short time, and the results of various areas were satisfactory. The official sea trial was well carried out. Then, the ship was officially designated the first nuclear ship in Japan. Experimental voyages are to be performed to yield profitable data for further research on nuclear ships in the future. (author)

  18. CASKETSS: a computer code system for thermal and structural analysis of nuclear fuel shipping casks

    International Nuclear Information System (INIS)

    Ikushima, Takeshi

    1989-02-01

    A computer program CASKETSS has been developed for the purpose of thermal and structural analysis of nuclear fuel shipping casks. CASKETSS measn a modular code system for CASK Evaluation code system Thermal and Structural Safety. Main features of CASKETSS are as follow; (1) Thermal and structural analysis computer programs for one-, two-, three-dimensional geometries are contained in the code system. (2) Some of the computer programs in the code system has been programmed to provide near optimal speed on vector processing computers. (3) Data libralies fro thermal and structural analysis are provided in the code system. (4) Input data generator is provided in the code system. (5) Graphic computer program is provided in the code system. In the paper, brief illustration of calculation method, input data and sample calculations are presented. (author)

  19. Measurement of xenon reactivity in the reactor of the nuclear ship 'MUTSU'

    International Nuclear Information System (INIS)

    Itagaki, Masafumi; Miyoshi, Yoshinori; Gakuhari, Kazuhiko; Okada, Noboru.

    1993-01-01

    This report deals with the measurement of reactivity changes caused by the increase and decrease of xenon concentration in the reactor core of the nuclear ship 'MUTSU' after a change from long-term operation at 70 % to zero power. The change in xenon reactivity was compensated by control-rod movements and the compensated reactivity was measured using a digital reactivity meter. The xenon override peak was recognized five and half hours after the start of power reduction. The equilibrium and peak reactivities of xenon were estimated by reading the initial and peak values of a theoretical curve which was fitted to the measured variation in xenon reactivity. The xenon reactivity results obtained by the present method can be considered to be accurate since no control-rod worth data were used and the measured quantity was the reactivity itself. (author)

  20. Measurements of streaming neutrons on nuclear ship 'Mutsu' by a two-detector-method

    International Nuclear Information System (INIS)

    Kobayashi, Iwao; Yamazaki, Hiroshi; Ryufuku, Hiroshi.

    1976-01-01

    Streaming neutrons escaping through an air gap located between the pressure vessel and the primary shield of the Nuclear Ship ''Mutsu'' were measured by applying the two-detector-method. The two detectors consisted of a single BF 3 counter provided alternatively with different covering arrangements - (a) 3mm thick steel tube + layers of polyethylene sheeting with total thickness of 30mm + 1mm thick Cd plate and (b) same covering as (a) + polyethylene boxing 20mm thick. In order to derive from the count rates obtained with the detectors described above the absolute values of neutron flux and dose equivalent rate, the detectors were calibrated in laboratory by comparison with a reference detector system in neutron field created around a 252 Cf source and TCA, a light-water moderated critical assembly. The conversion from measured counts to neutron flux and neutron dose equivalent rate was estimated to incur errors of +-15 and +-40%, respectively. (auth.)

  1. The application of land-based computerized spectrometers for effluent monitoring aboard nuclear powered ships. Final technical report

    International Nuclear Information System (INIS)

    Kamykowski, E.A.

    1975-12-01

    This report assesses the applicability of computer-based, Ge(Li) detector spectroscopy systems as effluent monitors aboard nuclear powered ships. A survey of the principal commercial spectrometers, in light of the expected shipboard use, indicates these systems may be employed for automatic radioisotope analysis in a seagoing environment if adequate protective measures are adopted

  2. Impact of nuclear fuel cycle centers on shipping special nuclear materials and wastes

    International Nuclear Information System (INIS)

    Blomeke, J.O.

    1975-01-01

    The impact of integrated nuclear fuel cycle facilities on the transportation sector appears from this admittedly rather narrow study to be of only marginal significance. However, there are other factors which must be taken into account such as nuclear safeguards, economics, and radiological, ecological, institutional, and sociological impacts. Unless more clear-cut advantages can be shown by on-going studies for some of these other considerations, the regimentation and control of industry that would result from the imposition of the integrated fuel cycle facility concept probably could not be justified. (auth)

  3. Nuclear export of human hepatitis B virus core protein and pregenomic RNA depends on the cellular NXF1-p15 machinery.

    Science.gov (United States)

    Yang, Ching-Chun; Huang, Er-Yi; Li, Hung-Cheng; Su, Pei-Yi; Shih, Chiaho

    2014-01-01

    Hepatitis B virus (HBV) core protein (HBc) can shuttle between nucleus and cytoplasm. Cytoplasm-predominant HBc is clinically associated with severe liver inflammation. Previously, we found that HBc arginine-rich domain (ARD) can associate with a host factor NXF1 (TAP) by coimmunoprecipitation. It is well known that NXF1-p15 heterodimer can serve as a major export receptor of nuclear mRNA as a ribonucleoprotein complex (RNP). In the NXF1-p15 pathway, TREX (transcription/export) complex plays an important role in coupling nuclear pre-mRNA processing with mRNA export in mammalian cells. Here, we tested the hypothesis whether HBc and HBV specific RNA can be exported via the TREX and NXF1-p15 mediated pathway. We demonstrated here that HBc can physically and specifically associate with TREX components, and the NXF1-p15 export receptor by coimmunoprecipitation. Accumulation of HBc protein in the nucleus can be induced by the interference with TREX and NXF1-p15 mediated RNA export machinery. HBV transcripts encodes a non-spliced 3.5 kb pregenomic RNA (pgRNA) which can serve as a template for reverse transcription. Cytoplasmic HBV pgRNA appeared to be reduced by siRNA treatment specific for the NXF1-p15 complex by quantitative RT-qPCR and Northern blot analyses. This result suggests that the pgRNA was also exported via the NXF1-p15 machinery. We entertain the hypothesis that HBc protein can be exported as an RNP cargo via the mRNA export pathway by hijacking the TREX and NXF1-p15 complex. In our current and previous studies, HBc is not required for pgRNA accumulation in the cytoplasm. Furthermore, HBc ARD can mediate nuclear export of a chimeric protein containing HBc ARD in a pgRNA-independent manner. Taken together, it suggests that while both pgRNA and HBc protein exports are dependent on NXF1-p15, they are using the same export machinery in a manner independent of each other.

  4. The creation of the analytical information system to serve the process of complex decommissioning of nuclear submarines (NSM) and surface ships (SS) with nuclear power installations (NPI)

    International Nuclear Information System (INIS)

    Terentiev, V.G.; Yakovlev, N.E.; Tyurin, A.V.

    2002-01-01

    Management of the decommissioning of nuclear vessels includes information collection, accumulation, systematisation and analysis on the complex utilization of nuclear submarines and surface ships with nuclear power installations and on treatment of spent nuclear fuel and radioactive wastes. The relevant data on radiation and ecology, science and technology, law and economy, administration and management should be properly processed. The general objective of the analytical information system (AIS) development, described in the present paper, is the efficiency upgrading for nuclear submarine utilization management and decision making. The report considers information provision and functioning principles as well as software/hardware solutions associated with the AIS creation. (author)

  5. 46 CFR 169.315 - Ventilation (other than machinery spaces).

    Science.gov (United States)

    2010-10-01

    ... section is satisfied, a vessel having only a natural ventilation system must satisfy the following: V/A≥1... 46 Shipping 7 2010-10-01 2010-10-01 false Ventilation (other than machinery spaces). 169.315... SCHOOL VESSELS Construction and Arrangement Hull Structure § 169.315 Ventilation (other than machinery...

  6. Investigation regarding the safety of handling the fuel assemblies for the nuclear ship 'Mutsu'

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    It was concluded previously that the general inspection of safety and the repair of shielding can be carried out as the fuel assemblies are charged, and the safety can be secured sufficiently. According to the decision by the meeting of cabinet ministers concerned with the nuclear ship ''Mutsu'', the Mutsu General Inspection and Repair Technology Investigation Committee investigated on the basic concept regarding the method and the safety of taking out, transporting and preserving the fuel assemblies. 112 fuel rods and 9 burnable poison rods are arranged into the square grid of 11 x 11 in a fuel assembly, and 32 fuel assemblies are employed. The contents of the investigation are the outline of the fuel assemblies, the present states of nuclear fission products, surface dose rate and soundness of the fuel assemblies, the safety of taking out, transporting and preserving the fuel assemblies, the measures required for securing the safety, and the place for taking out the fuel assemblies. In case of taking out, transporting and preserving the fuel assemblies, it is considered in view of the present state of the fuel assemblies that the safety can be secured sufficiently if the works are carried out carefully by taking the methods and conditions investigated into consideration. Also the committee reached already the conclusion described at the outset. (Kako, I.)

  7. Radiation technologies in metallurgy and machinery

    International Nuclear Information System (INIS)

    Meshkov, I.N.

    1990-01-01

    Applications of electron beam accelerators for technologies in metallurgy and machinery are discussed. Processes described are provided with special industrial accelerators, developed in the Institute of Nuclear Physics, Novosibirsk. (author)

  8. Spent Nuclear Fuel Transportation: An Examination of Potential Lessons Learned From Prior Shipping Campaigns

    International Nuclear Information System (INIS)

    M. Keister; K, McBride

    2006-01-01

    The Nuclear Waste Policy Act of 1982 (NWPA), as amended, assigned the Department of Energy (DOE) responsibility for developing and managing a Federal system for the disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for accepting, transporting, and disposing of SNF and HLW at the Yucca Mountain repository (if licensed) in a manner that protects public health, safety, and the environment; enhances national and energy security; and merits public confidence. OCRWM faces a near-term challenge--to develop and demonstrate a transportation system that will sustain safe and efficient shipments of SNF and HLW to a repository. To better inform and improve its current planning, OCRWM has extensively reviewed plans and other documents related to past high-visibility shipping campaigns of SNF and other radioactive materials within the United States. This report summarizes the results of this review and, where appropriate, lessons learned. The objective of this lessons learned study was to identify successful, best-in-class trends and commonalities from past shipping campaigns, which OCRWM could consider when planning for the development and operation of a repository transportation system. Note: this paper is for analytical and discussion purposes only, and is not an endorsement of, or commitment by, OCRWM to follow any of the comments or trends. If OCRWM elects to make such commitments at a future time, they will be appropriately documented in formal programmatic policy statements, plans and procedures. Reviewers examined an extensive study completed in 2003 by DOE's National Transportation Program (NTP), Office of Environmental Management (EM), as well as plans and documents related to SNF shipments since issuance of the NTP report. OCRWM examined specific planning, business, institutional and operating practices that have been identified by DOE, its transportation contractors

  9. Nucleocytoplasmic trafficking of Nipah virus W protein involves multiple discrete interactions with the nuclear import and export machinery

    International Nuclear Information System (INIS)

    Audsley, Michelle D.; Jans, David A.; Moseley, Gregory W.

    2016-01-01

    Paramyxoviruses replicate in the cytoplasm with no obvious requirement to interact with the nucleus. Nevertheless, the W protein of the highly lethal bat-borne paramyxovirus Nipah virus (NiV) is known to undergo specific targeting to the nucleus, mediated by a single nuclear localisation signal (NLS) within the C-terminal domain. Here, we report for the first time that additional sites modulate nucleocytoplasmic localisation of W. We show that the N-terminal domain interacts with importin α1 and contributes to nuclear accumulation of W, indicative of a novel N-terminal NLS. We also find that W undergoes exportin-1 mediated nuclear export, dependent on a leucine at position 174. Together, these data enable significant revision of the generally accepted model of W trafficking, with implications for understanding of the mechanisms of NiV immune evasion. - Highlights: • A new model for Nipah virus W protein nucleocytoplasmic trafficking is proposed. • Nipah W protein is shown to undergo active nuclear export via exportin-1. • Nipah W nuclear import is mediated by multiple nuclear localisation signals.

  10. Safety investigation of 'Mutsu', the first nuclear ship in Japan (the correspondence to the guideline of safety design examination, etc.)

    International Nuclear Information System (INIS)

    1981-01-01

    Japan Nuclear Ship Development Agency had made previously application for the permission of the alteration of the reactor installation in the nuclear ship Mutsu (the first of this kind in Japan), based on the overall safety investigation of the ship made by JNDA. Taking the opportunity of the governmental safety examination concerning the permission, the correspondence of the safety aspects of the n.s. Mutsu to the existing guidelines for the safety of nuclear reactor facilities was examined. These results to further enhance the safety of the n.s. Mutsu are described concerning the following matters: the safety design examination guideline for power-generating LWR facilities (58 items); the safety evaluation guideline for power-generating LWR facilities (the analysis of abnormal transients during operation and accidents); the safety countermeasures to be adopted in the reactor plant of the n.s. Mutsu from the situation of the TMI nuclear accident in U.S. (7 in design and 10 in operation management); the analysis simulating the TMI accident. (J.P.N.)

  11. Dual Neutral Particle Beam Interrogation of Intermodal Shipping Containers for Special Nuclear Material

    Science.gov (United States)

    Keith, Rodney Lyman

    Intermodal shipping containers entering the United States provide an avenue to smuggle unsecured or stolen special nuclear material (SNM). The only direct method fielded to indicate the presence of SNM is by passive photon/neutron radiation detection. Active interrogation using neutral particle beams to induce fission in SNM is a method under consideration. One by-product of fission is the creation of fragments that undergo radioactive decay over a time period on the order of tens of seconds after the initial event. The "delayed" gamma-rays emitted from these fragments over this period are considered a hallmark for the presence of SNM. A fundamental model is developed using homogenized cargos with a SNM target embedded at the center and computationally interrogated using simultaneous neutron and photon beams. Findings from analysis of the delayed gamma emissions from these experiments are intended to mitigate the effects of poor quality information about the composition and disposition of suspect cargo before examination in an active interrogation portal.

  12. Analysis of a hypothetical dropped spent nuclear fuel shipping cask impacting a floor mounted crush pad

    International Nuclear Information System (INIS)

    Hawkes, B.D.; Uldrich, E.D.

    1998-03-01

    A crush pad has been designed and analyzed to absorb the kinetic energy of a hypothetically dropped spent nuclear fuel shipping cask into a 44-ft. deep cask unloading pool at the Idaho Chemical Processing Plant. The 110-ton Large Cell Cask was assumed to be accidentally dropped onto the parapet of the unloading pool, causing the cask to tumble through the pool water and impact the floor mounted crush pad with the cask's top corner. The crush pad contains rigid polyurethane foam, which was modeled in a separate computer analysis to simulate the manufacturer's testing of the foam and to determine the foam's stress and strain characteristics. This computer analysis verified that the foam was accurately represented in the analysis to follow. A detailed non-linear, dynamic finite element analysis was then performed on the crush pad and adjacent pool structure to assure that a drop of this massive cask does not result in unacceptable damage to the storage facility. Additionally, verification was made that the crush pad adequately protects the cask from severe impact loading. At impact, the cask has significant vertical, horizontal and rotational velocities. The crush pad absorbs much of the energy of the cask through plastic deformation during primary and secondary impacts. After the primary impact with the crush pad, the cask still has sufficient energy to rebound and rotate until it impacts the pool wall. An assessment is made of the damage to the crush pad and pool wall and of the impact loading on the cask

  13. Control-rod interference effects observed during reactor physics experiments with nuclear ship 'MUTSU'

    International Nuclear Information System (INIS)

    Itagaki, Masafumi; Miyoshi, Yoshinori; Gakuhari, Kazuhiko; Okada, Noboru; Sakai, Tomohiro.

    1993-01-01

    The control rods in the reactor of the nuclear ship MUTSU are classified into four groups: groups G1 and G2 are located in the central part of the core, while groups G3 and G4 are in the peripheral zone of the core. Several types of mutual interference effects among these control-rod groups were observed during reactor physics experiments with this reactor. During normal hot operations, positive shadowing was dominant between the G1 and G2 groups; the degree of the shadowing effect of one rod group depended on the position of the other rod group. Both positive and negative shadowing effects occurred between an inner rod group (G1 or G2) and an outer group (G3 or G4) depending on the three-dimensional arrangement of the control rods. The rod worths of G1 and G2 increased as a result of slight core burnup, about 1,400 MWd/t, mainly due to the decrease in shadowing effects resulting from a change in control-rod pattern. A three-dimensional diffusion calculation with internal control-rod boundary conditions has proved to be useful for analyzing these various interaction effects. (author)

  14. Comparison between measured and design dose rate equivalents on board of Nuclear Ship Mutsu

    International Nuclear Information System (INIS)

    Yamaji, Akio; Sakamoto, Yukio

    1993-01-01

    The power-up test of the Nuclear Ship Mutsu was restarted in March 1990 and completed successfully in February 1991. The experimental voyages were carried out for about one year and all experiments were completed in February 1992. A comparison between the measured and design dose rate equivalents on board is described with showing a modified method in the shielding design. The measured values were obtained extensively in the cavity between the primary and secondary shields, in the double bottom, outside the secondary shield, and on the surface of the main coolant loop. The shielding design calculations were made with the most conservative geometries and material compositions within the allowed tolerance. In addition, a conservative model was adopted in case of performing the approximation due to the geometrical restriction of calculation code. The computational accuracies were evaluated based on various experimental analyses. The evaluated value was used as the design value. The shield structures were determined with a judgement that the real value does not exceed the design value. The adequacy of the judgement was confirmed by measurements on board. The measured dose rate equivalents in all positions on board satisfied the design criteria. (author)

  15. Calculation of radiation dose rates from a spent nuclear fuel shipping cask

    International Nuclear Information System (INIS)

    Chen, S.Y.; Yuan, Y.C.

    1988-01-01

    Radiation doses from a spent nuclear fuel cask are usually from various phases of operations during handling, shipping, and storage of the casks. Assessment of such doses requires knowledge of external radiation dose rates at various locations surrounding a cask. Under current practices, dose rates from gamma photons are usually estimated by means of point- or line-source approaches incorporating the conventional buildup factors. Although such simplified approaches may at times be easy to use, their accuracy has not been verified. For example, those simplified methods have not taken into account influencing factors such as the geometry of the cask and the presence of the ground surface, and the effects of these factors on the calculated dose rates are largely unknown. Moreover, similar empirical equations for buildup factors currently do not exist for neutrons. The objective of this study is to use a more accurate approach in calculating radiation dose rates for both neutrons and gamma photons from a spent fuel cask. The calculation utilizes the more sophisticated transport method and takes into account the geometry of the cask and the presence of the ground surface. The results of a detailed study of dose rates in the near field (within 20 meters) are presented and, for easy application, the cask centerline dose rates are fitted into empirical equations at cask centerline distances up to 2000 meters from the surface of the cask

  16. A biochemical framework for eIF4E-dependent mRNA export and nuclear recycling of the export machinery.

    Science.gov (United States)

    Volpon, Laurent; Culjkovic-Kraljacic, Biljana; Sohn, Hye Seon; Blanchet-Cohen, Alexis; Osborne, Michael J; Borden, Katherine L B

    2017-06-01

    The eukaryotic translation initiation factor eIF4E acts in the nuclear export and translation of a subset of mRNAs. Both of these functions contribute to its oncogenic potential. While the biochemical mechanisms that underlie translation are relatively well understood, the molecular basis for eIF4E's role in mRNA export remains largely unexplored. To date, over 3000 transcripts, many encoding oncoproteins, were identified as potential nuclear eIF4E export targets. These target RNAs typically contain a ∼50-nucleotide eIF4E sensitivity element (4ESE) in the 3' UTR and a 7-methylguanosine cap on the 5' end. While eIF4E associates with the cap, an unknown factor recognizes the 4ESE element. We previously identified cofactors that functionally interacted with eIF4E in mammalian cell nuclei including the leucine-rich pentatricopeptide repeat protein LRPPRC and the export receptor CRM1/XPO1. LRPPRC simultaneously interacts with both eIF4E bound to the 5' mRNA cap and the 4ESE element in the 3' UTR. In this way, LRPPRC serves as a specificity factor to recruit 4ESE-containing RNAs within the nucleus. Further, we show that CRM1 directly binds LRPPRC likely acting as the export receptor for the LRPPRC-eIF4E-4ESE RNA complex. We also found that Importin 8, the nuclear importer for cap-free eIF4E, imports RNA-free LRPPRC, potentially providing both coordinated nuclear recycling of the export machinery and an important surveillance mechanism to prevent futile export cycles. Our studies provide the first biochemical framework for the eIF4E-dependent mRNA export pathway. © 2017 Volpon et al.; Published by Cold Spring Harbor Laboratory Press for the RNA Society.

  17. Development of advanced automatic control system for nuclear ship. 2. Perfect automatic operation after reactor scram events

    International Nuclear Information System (INIS)

    Yabuuchi, Noriaki; Nakazawa, Toshio; Takahashi, Hiroki; Shimazaki, Junya; Hoshi, Tsutao

    1997-11-01

    An automatic operation system has been developed for the purpose of realizing a perfect automatic plant operation after reactor scram events. The goal of the automatic operation after a reactor scram event is to bring the reactor hot stand-by condition automatically. The basic functions of this system are as follows; to monitor actions of the equipments of safety actions after a reactor scram, to control necessary control equipments to bring a reactor to a hot stand-by condition automatically, and to energize a decay heat removal system. The performance evaluation on this system was carried out by comparing the results using to Nuclear Ship Engineering Simulation System (NESSY) and the those measured in the scram test of the nuclear ship 'Mutsu'. As the result, it was showed that this system had the sufficient performance to bring a reactor to a hot syand-by condition quickly and safety. (author)

  18. Development of advanced automatic control system for nuclear ship. 2. Perfect automatic operation after reactor scram events

    Energy Technology Data Exchange (ETDEWEB)

    Yabuuchi, Noriaki; Nakazawa, Toshio; Takahashi, Hiroki; Shimazaki, Junya; Hoshi, Tsutao [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-11-01

    An automatic operation system has been developed for the purpose of realizing a perfect automatic plant operation after reactor scram events. The goal of the automatic operation after a reactor scram event is to bring the reactor hot stand-by condition automatically. The basic functions of this system are as follows; to monitor actions of the equipments of safety actions after a reactor scram, to control necessary control equipments to bring a reactor to a hot stand-by condition automatically, and to energize a decay heat removal system. The performance evaluation on this system was carried out by comparing the results using to Nuclear Ship Engineering Simulation System (NESSY) and the those measured in the scram test of the nuclear ship `Mutsu`. As the result, it was showed that this system had the sufficient performance to bring a reactor to a hot syand-by condition quickly and safety. (author)

  19. Development of an improved genetic algorithm and its application in the optimal design of ship nuclear power system

    International Nuclear Information System (INIS)

    Jia Baoshan; Yu Jiyang; You Songbo

    2005-01-01

    This article focuses on the development of an improved genetic algorithm and its application in the optimal design of the ship nuclear reactor system, whose goal is to find a combination of system parameter values that minimize the mass or volume of the system given the power capacity requirement and safety criteria. An improved genetic algorithm (IGA) was developed using an 'average fitness value' grouping + 'specified survival probability' rank selection method and a 'separate-recombine' duplication operator. Combining with a simulated annealing algorithm (SAA) that continues the local search after the IGA reaches a satisfactory point, the algorithm gave satisfactory optimization results from both search efficiency and accuracy perspectives. This IGA-SAA algorithm successfully solved the design optimization problem of ship nuclear power system. It is an advanced and efficient methodology that can be applied to the similar optimization problems in other areas. (authors)

  20. 46 CFR 111.103-1 - Power ventilation systems except machinery space ventilation systems.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Power ventilation systems except machinery space ventilation systems. 111.103-1 Section 111.103-1 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY... Power ventilation systems except machinery space ventilation systems. Each power ventilation system must...

  1. 46 CFR 167.65-60 - Examination of boilers and machinery by engineer.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Examination of boilers and machinery by engineer. 167.65-60 Section 167.65-60 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) NAUTICAL... machinery by engineer. It shall be the duty of an engineer when he assumes charge of the boilers and...

  2. 46 CFR 182.465 - Ventilation of spaces containing diesel machinery.

    Science.gov (United States)

    2010-10-01

    ... furnish natural or powered supply and exhaust ventilation. The total inlet area and the total outlet area... 46 Shipping 7 2010-10-01 2010-10-01 false Ventilation of spaces containing diesel machinery. 182... Ventilation of spaces containing diesel machinery. (a) A space containing diesel machinery must be fitted with...

  3. 46 CFR 97.15-15 - Examination of boilers and machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Examination of boilers and machinery. 97.15-15 Section... VESSELS OPERATIONS Tests, Drills, and Inspections § 97.15-15 Examination of boilers and machinery. It shall be the duty of the chief engineer when assuming charge of the boilers and machinery of a vessel to...

  4. 46 CFR 78.17-30 - Examination of boilers and machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 3 2010-10-01 2010-10-01 false Examination of boilers and machinery. 78.17-30 Section... OPERATIONS Tests, Drills, and Inspections § 78.17-30 Examination of boilers and machinery. It shall be the duty of the chief engineer when assuming charge of the boilers and machinery of a vessel to examine...

  5. 46 CFR 196.15-15 - Examination of boilers and machinery.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Examination of boilers and machinery. 196.15-15 Section... VESSELS OPERATIONS Test, Drills, and Inspections § 196.15-15 Examination of boilers and machinery. (a) It shall be the duty of the chief engineer when he assumes charge of the boilers and machinery of a vessel...

  6. 46 CFR 116.620 - Ventilation of machinery and fuel tank spaces.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Ventilation of machinery and fuel tank spaces. 116.620... AND ARRANGEMENT Ventilation § 116.620 Ventilation of machinery and fuel tank spaces. In addition to the requirements of this subpart, ventilation systems for spaces containing machinery or fuel tanks...

  7. 29 CFR 1915.162 - Ship's boilers.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 7 2010-07-01 2010-07-01 false Ship's boilers. 1915.162 Section 1915.162 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR (CONTINUED) OCCUPATIONAL SAFETY AND HEALTH STANDARDS FOR SHIPYARD EMPLOYMENT Ship's Machinery and Piping Systems § 1915.162 Ship's boilers. (a) Before...

  8. Licensing procedures for a dedicated ship for carrying spent nuclear fuel and radioactive waste. Report from workshop held at GOSAOMNADZOR, Moscow 2 -3 July 2001

    Energy Technology Data Exchange (ETDEWEB)

    Sneve, Margorzata K.; Bergman, Curt; Markarov, Valentin

    2001-07-01

    The report describes information exchange and discussion about the licensing principles and procedures for spent nuclear fuel and radioactive waste transportation at sea. Russian health, environment and safety requirements for transportation of waste by ships. (Author)

  9. Seismic tipping analysis of a spent nuclear fuel shipping cask sitting on a crush pad

    International Nuclear Information System (INIS)

    Uldrich, E.D.; Hawkes, B.D.

    1998-04-01

    A crush pad has been designed and analyzed to absorb the kinetic energy of an accidentally dropped spent nuclear fuel shipping cask into a 44 ft. deep cask unloading pool. Conventional analysis techniques available for evaluating a cask for tipping due to lateral seismic forces assume that the cask rests on a rigid surface. In this analysis, the cask (110 tons) sits on a stainless steel encased (0.25 in. top plate), polyurethane foam (4 ft. thick) crush pad. As the cask tends to rock due to horizontal seismic forces, the contact area between the cask and the crush pad is reduced, increasing the bearing stress, and causing the pivoting corner of the cask to depress into the crush pad. As the crush pad depresses under the cask corner, the pivot point shifts from the corner toward the cask center, which facilitates rocking and potential tipping of the cask. Subsequent rocking of the cask may deepen the depression, further contributing to the likelihood of cask tip over. However, as the depression is created, the crush pad is absorbing energy from the rocking cask. Potential tip over of the cask was evaluated by performing a non-linear, dynamic, finite element analysis with acceleration time history input. This time history analysis captured the effect of a deforming crush pad, and also eliminated conservatisms of the conventional approaches. For comparison purposes, this analysis was also performed with the cask sitting on a solid stainless steel crush pad. Results indicate that the conventional methods are quite conservative relative to the more exacting time history analysis. They also indicate that the rocking motion is less on the foam crush pad than on the solid stainless steel pad

  10. Spent nuclear fuel shipping cask handling capabilities of commercial light water reactors

    International Nuclear Information System (INIS)

    Daling, P.M.; Konzek, G.J.; Lezberg, A.J.; Votaw, E.F.; Collingham, M.I.

    1985-04-01

    This report describes an evaluation of the cask handling capabilities of those reactors which are operating or under construction. A computerized data base that includes cask handling information was developed with information from the literature and utility-supplied data. The capability of each plant to receive and handle existing spent fuel shipping casks was then evaluated. Modal fractions were then calculated based on the results of these evaluations and the quantities of spent fuel projected to be generated by commercial nuclear power plants through 1998. The results indicated that all plants are capable of receiving and handling truck casks. Up to 118 out of 130 reactors (91%) could potentially handle the larger and heavier rail casks if the maximum capability of each facility is utilized. Design and analysis efforts and physical modifications to some plants would be needed to achieve this high rail percentage. These modifications would be needed to satisfy regulatory requirements, increase lifting capabilities, develop rail access, or improve other deficiencies. The remaining 12 reactors were determined to be capable of handling only the smaller truck casks. The percentage of plants that could receive and handle rail casks in the near-term would be reduced to 64%. The primary reason for a plant to be judged incapable of handling rail casks in the near-term was a lack of rail access. The remaining 36% of the plants would be limited to truck shipments. The modal fraction calculations indicated that up to 93% of the spent fuel accumulated by 1998 could be received at federal storage or disposal facilities via rail (based on each plant's maximum capabilities). If the near-term cask handling capabilities are considered, the rail percentage is reduced to 62%

  11. Response to severe changes of load on the reactor system of nuclear ship Mutsu

    International Nuclear Information System (INIS)

    Ishida, Toshihisa; Kusunoki, Tsuyoshi; Ochiai, Masa-aki; Tanaka, Yoshimi; Yao, Toshiaki; Inoue, Kimio.

    1993-01-01

    The response of the nuclear power system of N.S. Mutsu to severe changes of load have been studied from records taken during the power-raising tests performed on the ship in 1990. The records examined were those involving the most severe load changes foreseen for marine reactors: (a) sharp load increase with total steam flow raised from 25 to 70 % rated full flow in 13s, (b) crash astern maneuver with the position of propulsion turbine command handle changed-taking several seconds-from cruising ahead to STOP, and after about 50s, further changed-taking 30s-to bring the astern propulsion turbine to full speed-to consume approximately 60 % rated total steam flow and (c) turbine trip with the ahead turbine intentionally tripped when operating at roughly 100 % rated total steam flow. The foregoing records from load changes-of severity beyond what is foreseen for land-based reactors-proved that the Mutsu reactor is capable of responding smoothly and securely to such severe load changes. These load changes occasioned relatively large mismatches between reactor power supply and steam flow demand, but with notable freedom from any conspicuous overshooting or hunting of the reactor power. This performance can be attributed to (a) correct functioning of the automatic power control system, (b) effective contribution of the self-regulating reactor control property deriving from the large negative feedback between moderator temperature and reactivity, and (c) the ample inventories of coolant in the primary and secondary loops. The responses to load change are discussed covering those relevant to (a) reactor power, (b) primary loop pressure, and (c) steam generator pressure, with particular reference to the differences seen in response to mild and to severe load changes. (author)

  12. Utilization of uranium cost/benefit study for nuclear powered merchant ships. Special study

    International Nuclear Information System (INIS)

    Smith, E.R.

    1977-05-01

    This study presents a cost/benefit analysis for the utilization of uranium in merchant ships versus the use of uranium for the generation of electricity in central power stations. The study concludes that an alternative naval fuel to oil must be developed for the merchant marine to reduce U.S. dependency upon foreign supplies of a critical fuel. The study further indicates that use of uranium for ship propulsion results in transport of large quantities of needed import/exports while the residual oil saved will generate the same quantity of electricity in a central power station as the uranium used for ship propulsion

  13. Nuclear criticality safety studies applicable to spent fuel shipping cask designs and spent fuel storage

    International Nuclear Information System (INIS)

    Tang, J.S.

    1980-11-01

    Criticality analyses of water-moderated and reflected arrays of LWR fresh and spent fuel assemblies were carried out in this study. The calculated results indicate that using the assumption of fresh fuel loading in spent fuel shipping cask design leads to assembly spacings which are about twice the spacings of spent fuel loadings. Some shipping cask walls of composite lead and water are more effective neutron reflectors than water of 30.48 cm

  14. Improving machinery reliability

    CERN Document Server

    Bloch, Heinz P

    1998-01-01

    This totally revised, updated and expanded edition provides proven techniques and procedures that extend machinery life, reduce maintenance costs, and achieve optimum machinery reliability. This essential text clearly describes the reliability improvement and failure avoidance steps practiced by best-of-class process plants in the U.S. and Europe.

  15. 46 CFR 167.15-25 - Inspection standards for hulls, boilers and machinery.

    Science.gov (United States)

    2010-10-01

    ... SCHOOLS PUBLIC NAUTICAL SCHOOL SHIPS Inspections § 167.15-25 Inspection standards for hulls, boilers and... 46 Shipping 7 2010-10-01 2010-10-01 false Inspection standards for hulls, boilers and machinery... inspection. These rules may be purchased from the American Bureau of Shipping (ABS), ABS Plaza, 16855...

  16. Noise source analysis of nuclear ship Mutsu plant using multivariate autoregressive model

    International Nuclear Information System (INIS)

    Hayashi, K.; Shimazaki, J.; Shinohara, Y.

    1996-01-01

    The present study is concerned with the noise sources in N.S. Mutsu reactor plant. The noise experiments on the Mutsu plant were performed in order to investigate the plant dynamics and the effect of sea condition and and ship motion on the plant. The reactor noise signals as well as the ship motion signals were analyzed by a multivariable autoregressive (MAR) modeling method to clarify the noise sources in the reactor plant. It was confirmed from the analysis results that most of the plant variables were affected mainly by a horizontal component of the ship motion, that is the sway, through vibrations of the plant structures. Furthermore, the effect of ship motion on the reactor power was evaluated through the analysis of wave components extracted by a geometrical transform method. It was concluded that the amplitude of the reactor power oscillation was about 0.15% in normal sea condition, which was small enough for safe operation of the reactor plant. (authors)

  17. Model of a Nuclear Security Naval Agency for radiation control of the Industrial Complex of of Submarine Construction and Maintenance Ship with Nuclear Propulsion

    International Nuclear Information System (INIS)

    Lins Junior, Amilton de Sousa

    2017-01-01

    Due to the construction, by Brazilian Navy, of a Submarine Construction and Maintenance Ship with Nuclear Propulsion, where, among other activities, the commissioning and exchange of the fuel elements of the reactor in the future Nuclear Submarine, and of a Naval Base where the Nuclear Submarine and the Conventional Submarines, it is necessary the establishment of a Nuclear Security Naval Agency to monitor activities involving ionizing radiation sources and nuclear materials aimed at the radiological protection of exposed occupationally individuals (IOE), the general public and the environment. It should be noted that nuclear and radioactive material will be present only in a part of the yard called Radiological Complex. Therefore, the development of a structure for the control of the Radiological Complex is fundamental, considering that the future licensing process will be unprecedented in Brazil and will face several difficulties. This work presents a model of a structure for the radiological control of the industrial complex for the construction and maintenance of the submarine with nuclear propulsion, as well as the fundamental concepts of the activities, such as inspection, regulations and authorizations, to be carried out by the various component sectors of the Nuclear Security Naval Agency. (author)

  18. Suggestions of radiation protection instruments in ships used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants

    International Nuclear Information System (INIS)

    Warenmo, G.

    1979-01-01

    Some radiation protection measures are necessary in ships which will be used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants in order to protect the crew from unnecessarily high radiation doses and to ensure that not allowable values occur. Such measures are discussed in this report as well as suitable radiation protection instruments for such ships. (E.R.)

  19. Analysis, scale modeling, and full-scale test of a railcar and spent-nuclear-fuel shipping cask in a high-velocity impact against a rigid barrier

    International Nuclear Information System (INIS)

    Huerta, M.

    1981-06-01

    This report describes the mathematical analysis, the physical scale modeling, and a full-scale crash test of a railcar spent-nuclear-fuel shipping system. The mathematical analysis utilized a lumped-parameter model to predict the structural response of the railcar and the shipping cask. The physical scale modeling analysis consisted of two crash tests that used 1/8-scale models to assess railcar and shipping cask damage. The full-scale crash test, conducted with retired railcar equipment, was carefully monitored with onboard instrumentation and high-speed photography. Results of the mathematical and scale modeling analyses are compared with the full-scale test. 29 figures

  20. 46 CFR 182.460 - Ventilation of spaces containing machinery powered by, or fuel tanks for, gasoline.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Ventilation of spaces containing machinery powered by, or fuel tanks for, gasoline. 182.460 Section 182.460 Shipping COAST GUARD, DEPARTMENT OF HOMELAND..., gasoline. (a) A space containing machinery powered by, or fuel tanks for, gasoline must have a ventilation...

  1. Nuclear criticality safety assessment of ORR, NBS, and HFBR fuel element shipping package

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1979-01-01

    A fuel element shipping package employing a borated-phenolic foam as a thermal insulating material is designed to transport as many as seven fuel elements for use in the Oak Ridge Research Reactor, the Brookhaven Fast Beam Reactor, or the National Bureau of Standards Reactor. This report presents the criticality safety evaluation and demonstrates that the requirements for a Fissile Class I package are satisfied by the design

  2. The legal position of nuclear ships according to the drafts of the third UN-conference on the law of the sea

    International Nuclear Information System (INIS)

    Rauschning, D.G.

    1978-01-01

    At the end of the 6th session of the Third UN-Conference on the Law of the Sea an Informal Composite Negotiating text has emerged. Art. 19 ICNT, which defines innocent passage, contains no express limitation on nuclear shipping, while Art. 23 presupposes that nuclear ships have this right, provided they carry documents and observe special precautionary measures established by international agreements. A certificate of nuclear safety pursuant to Chapter VIII of SOLAS must be recognized by contracting states and coastal states may require liability coverage. Coastal state lack competences to regulate design, construction, manning or equipment of foreign ships or to impose requirements which have the practical effect of denying innocent passage. The right of passage also prevails in the special economic zones and in archipelagic waters

  3. Use of Russian technology of ship reactors with lead-bismuth coolant in nuclear power

    International Nuclear Information System (INIS)

    Zrodnikov, A.V.; Chitaykin, V.I.; Gromov, B.F.; Grigoryv, O.G.; Dedoul, A.V.; Toshinsky, G.I.; Dragunov, Yu.G.; Stepanov, V.S.

    2000-01-01

    The experience of using lead-bismuth coolant in Russian nuclear submarine reactors has been presented. The fundamental statements of the concept of using the reactors cooled by lead-bismuth alloy in nuclear power have been substantiated. The results of developments for using lead bismuth coolant in nuclear power have been presented. (author)

  4. Advanced ship systems condition monitoring for enhanced inspection, maintenance and decision making in ship operations

    OpenAIRE

    Lazakis, Iraklis; Dikis, Konstantinos; Michala, Anna Lito; Theotokatos, Gerasimos

    2016-01-01

    Structural and machinery failures in the day-to-day ship operations may lead to major accidents, endangering crew and\\ud passengers onboard, posing a threat to the environment, damaging the ship itself and having a great impact in terms of business\\ud losses. In this respect, this paper presents the INCASS (Inspection Capabilities for Enhanced Ship Safety) project which aims\\ud bringing an innovative solution to the ship inspection regime through the introduction of enhanced inspection of shi...

  5. Cavitation in Hydraulic Machinery

    Energy Technology Data Exchange (ETDEWEB)

    Kjeldsen, M.

    1996-11-01

    The main purpose of this doctoral thesis on cavitation in hydraulic machinery is to change focus towards the coupling of non-stationary flow phenomena and cavitation. It is argued that, in addition to turbulence, superimposed sound pressure fluctuations can have a major impact on cavitation and lead to particularly severe erosion. For the design of hydraulic devices this finding may indicate how to further limit the cavitation problems. Chapter 1 reviews cavitation in general in the context of hydraulic machinery, emphasizing the initial cavitation event and the role of the water quality. Chapter 2 discusses the existence of pressure fluctuations for situations common in such machinery. Chapter 3 on cavitation dynamics presents an algorithm for calculating the nucleation of a cavity cluster. Chapter 4 describes the equipment used in this work. 53 refs., 55 figs.,10 tabs.

  6. CASKETSS-2: a computer code system for thermal and structural analysis of nuclear fuel shipping casks (version 2)

    International Nuclear Information System (INIS)

    Ikushima, Takeshi

    1991-08-01

    A computer program CASKETSS-2 has been developed for the purpose of thermal and structural analysis of nuclear fuel shipping casks. CASKETSS-2 means a modular code system for CASK Evaluation code system Thermal and Structural Safety (Version 2). Main features of CASKETSS-2 are as follow; (1) Thermal and structural analysis computer programs for one-, two-, three-dimensional geometries are contained in the code system. (2) There are simplified computer programs and a detailed one in the structural analysis part in the code system. (3) Input data generator is provided in the code system. (4) Graphic computer program is provided in the code system. In the paper, brief illustration of calculation method, input data and sample calculations are presented. (author)

  7. Analysis of ex-core detector response measured during nuclear ship Mutsu land-loaded core critical experiment

    International Nuclear Information System (INIS)

    Itagaki, M.; Abe, J.I.; Kuribayashi, K.

    1987-01-01

    There are some cases where the ex-core neutron detector response is dependent not only on the fission source distribution in a core but also on neutron absorption in the borated water reflector. For example, an unexpectedly large response variation was measured during the nuclear ship Mutsu land-loaded core critical experiment. This large response variation is caused largely by the boron concentration change associated with the change in control rod positioning during the experiment. The conventional Crump-Lee response calculation method has been modified to take into account this boron effect. The correction factor in regard to this effect has been estimated using the one-dimensional transport code ANISN. The detector response variations obtained by means of this new calculation procedure agree well with the measured values recorded during the experiment

  8. Development and demonstration of surveillance and diagnostics of rotating machinery for reducing radiation exposure to nuclear power plant personnel: Final report

    International Nuclear Information System (INIS)

    Allen, J.W.; Bohanick, J.S.

    1988-01-01

    This program was designed to reduce radiation exposure to power plant personnel resulting from inspection, maintenance, and repair of rotating equipment. The new rotating machinery monitoring system for this program was installed at GGNS during August 1983. This document provides a functional description of the hardware and software that comprise the system and discusses the application of the monitoring system to achieving overall program goals. The analyses of the monitored rotating machinery during the plant startup phase and after the plant's first fuel cycle are presented in addition to the radiation dose reduction which occurred as a direct and indirect result of the RMSS. The dose reduction program at GGNS is reviewed and recommendations made to incorporate this program with the RMSS. 28 refs., 64 figs., 43 tabs

  9. 46 CFR 35.25-1 - Examination of boilers and machinery by engineer-T/ALL.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 1 2010-10-01 2010-10-01 false Examination of boilers and machinery by engineer-T/ALL... Engine Department § 35.25-1 Examination of boilers and machinery by engineer—T/ALL. It shall be the duty of an engineer when assuming charge of the boilers to examine the same forthwith and thoroughly. If...

  10. 46 CFR 177.620 - Ventilation of machinery and fuel tank spaces.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Ventilation of machinery and fuel tank spaces. 177.620... fuel tank spaces. In addition to the requirements of this subpart, ventilation systems for spaces containing machinery or fuel tanks must comply with the requirements of part 182 of this chapter. ...

  11. Roadmapping - A Tool for Resolving Science and Technology Issues Related to Processing, Packaging, and Shipping Nuclear Materials and Waste

    International Nuclear Information System (INIS)

    Luke, Dale Elden; Dixon, Brent Wayne; Murphy, James Anthony

    2002-01-01

    Roadmapping is an effective methodology to identify and link technology development and deployment efforts to a program's or project's needs and requirements. Roadmapping focuses on needed technical support to the baselines (and to alternatives to the baselines) where the probability of success is low (high uncertainty) and the consequences of failure are relatively high (high programmatic risk, higher cost, longer schedule, or higher ES and H risk). The roadmap identifies where emphasis is needed, i.e., areas where investments are large, the return on investment is high, or the timing is crucial. The development of a roadmap typically involves problem definition (current state versus the desired state) and major steps (functions) needed to reach the desired state. For Nuclear Materials (NM), the functions could include processing, packaging, storage, shipping, and/or final disposition of the material. Each function is examined to determine what technical development would be needed to make the function perform as desired. This requires a good understanding of the current state of technology and technology development and validation activities to ensure the viability of each step. In NM disposition projects, timing is crucial. Technology must be deployed within the project window to be of value. Roadmaps set the stage to keep the technology development and deployment focused on project milestones and ensure that the technologies are sufficiently mature when needed to mitigate project risk and meet project commitments. A recent roadmapping activity involved a 'cross-program' effort, which included NM programs, to address an area of significant concern to the Department of Energy (DOE) related to gas generation issues, particularly hydrogen. The roadmap that was developed defined major gas generation issues within the DOE complex and research that has been and is being conducted to address gas generation concerns. The roadmap also provided the basis for sharing

  12. Bacterial mitotic machineries

    DEFF Research Database (Denmark)

    Gerdes, Kenn; Møller-Jensen, Jakob; Ebersbach, Gitte

    2004-01-01

    Here, we review recent progress that yields fundamental new insight into the molecular mechanisms behind plasmid and chromosome segregation in prokaryotic cells. In particular, we describe how prokaryotic actin homologs form mitotic machineries that segregate DNA before cell division. Thus, the P......M protein of plasmid R1 forms F actin-like filaments that separate and move plasmid DNA from mid-cell to the cell poles. Evidence from three different laboratories indicate that the morphogenetic MreB protein may be involved in segregation of the bacterial chromosome.......Here, we review recent progress that yields fundamental new insight into the molecular mechanisms behind plasmid and chromosome segregation in prokaryotic cells. In particular, we describe how prokaryotic actin homologs form mitotic machineries that segregate DNA before cell division. Thus, the Par...

  13. Vibration of hydraulic machinery

    CERN Document Server

    Wu, Yulin; Liu, Shuhong; Dou, Hua-Shu; Qian, Zhongdong

    2013-01-01

    Vibration of Hydraulic Machinery deals with the vibration problem which has significant influence on the safety and reliable operation of hydraulic machinery. It provides new achievements and the latest developments in these areas, even in the basic areas of this subject. The present book covers the fundamentals of mechanical vibration and rotordynamics as well as their main numerical models and analysis methods for the vibration prediction. The mechanical and hydraulic excitations to the vibration are analyzed, and the pressure fluctuations induced by the unsteady turbulent flow is predicted in order to obtain the unsteady loads. This book also discusses the loads, constraint conditions and the elastic and damping characters of the mechanical system, the structure dynamic analysis, the rotor dynamic analysis and the system instability of hydraulic machines, including the illustration of monitoring system for the instability and the vibration in hydraulic units. All the problems are necessary for vibration pr...

  14. Re-evaluation of the criticality experiments of the ''Otto Hahn Nuclear Ship'' reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lengar, I.; Snoj, L.; Rogan, P.; Ravnik, M. [Jozef Stefan Institute, Ljubljana (Slovenia)

    2008-11-15

    Several series of experiments with a FDR reactor (advanced pressurized light water reactor) were performed in 1972 in the Geesthacht critical facility ANEX. The experiments were performed to test the core prior to its usage for the propulsion of the first German nuclear merchant ship ''Otto-Hahn''. In the present paper a calculational re-evaluation of the experiments is described with the use of the up-to date computer codes (Monte-Carlo code MCNP5) and nuclear data (ENDF/B-VI release 6). It is focused on the determination of uncertainties in the benchmark model of the experimental set-up, originating mainly from the limited set of information still available about the experiments. Effects of the identified uncertainties on the multiplication factor were studied. The sensitivity studies include parametric variation of material composition and geometry. The combined total uncertainty being found 0.0050 in k{sub eff}, the experiments are qualified as criticality safety benchmark experiments. (orig.)

  15. Investigation on structural analysis computer program of spent nuclear fuel shipping cask

    International Nuclear Information System (INIS)

    Yagawa, Ganki; Ikushima, Takeshi.

    1987-10-01

    This report describes the results done by the Sub-Committee of Research Cooperation Committee (RC-62) of the Japan Society of Mechanical Engineers under the trust of the Japan Atomic Energy Research Institute. The principal fulfilments and accomplishments are summarized as follows: (1) Regarding the survey of structural analysis methods of spent fuel shipping cask, several documents, which explain the features and applications of the exclusive computer programs for impact analysis on the basis of 2 or 3 dimensional finite element or difference methods such as HONDO, STEALTH and DYNA-3D, were reviewed. (2) In comparative evaluation of the existing computer programs, the common benchmark test problems for 9 m vertical drop impact of the axisymmetric lead cylinder with and without stainless steel clads were adopted where the calculational evaluations for taking into account the strain rate effect were carried out. (3) Evaluation of impact analysis algorithm of computer programs were conducted and the requirements for computer programs to be developed in future and an index for further studies have been clarified. (author)

  16. Nuclear criticality safety analysis for the traveller PWR fuel shipping package

    International Nuclear Information System (INIS)

    Vescovi, P.J.; Kent, N.A.; Casado, C.A.

    2004-01-01

    The Traveller PWR fresh fuel shipping package represents a radical departure from conventional PWR fuel package designs. Two immediately noticeable features of the Traveller are that it carries a single fuel assembly instead of two as do other package designs, and that it has built-in moderator, which forms part of the flux-trap system. The criticality safety case shows that the Traveller satisfies both U.S. and IAEA licensing requirements, and demonstrates that the package remains acceptably subcritical under normal conditions and hypothetical accident conditions of transport. This paper looks at the modeling techniques that were used to analyze the several accident scenarios that were considered, including: Lattice pitch expansion; Lattice pitch expansion along the fuel assembly length; Preferential flooding (selective flooding of different cavities); Differential flooding (varying water levels inside different cavities); Partial flooding (varying water density); Axial rod displacement; o Sensitivity studies of variable foam densities and boron content in packaging; Analysis for carrying loose rods in a rodbox; The criticality safety case for the Traveller proved to be a successful cooperative effort between ENUSA and Westinghouse

  17. Nuclear criticality safety analysis for the traveller PWR fuel shipping package

    Energy Technology Data Exchange (ETDEWEB)

    Vescovi, P.J.; Kent, N.A.; Casado, C.A. [Westinghouse Electric Co., LLC, Columbia, SC (United States)]|[ENUSA Industrias Avanzadas SA, Madrid (Spain)

    2004-07-01

    The Traveller PWR fresh fuel shipping package represents a radical departure from conventional PWR fuel package designs. Two immediately noticeable features of the Traveller are that it carries a single fuel assembly instead of two as do other package designs, and that it has built-in moderator, which forms part of the flux-trap system. The criticality safety case shows that the Traveller satisfies both U.S. and IAEA licensing requirements, and demonstrates that the package remains acceptably subcritical under normal conditions and hypothetical accident conditions of transport. This paper looks at the modeling techniques that were used to analyze the several accident scenarios that were considered, including: Lattice pitch expansion; Lattice pitch expansion along the fuel assembly length; Preferential flooding (selective flooding of different cavities); Differential flooding (varying water levels inside different cavities); Partial flooding (varying water density); Axial rod displacement; o Sensitivity studies of variable foam densities and boron content in packaging; Analysis for carrying loose rods in a rodbox; The criticality safety case for the Traveller proved to be a successful cooperative effort between ENUSA and Westinghouse.

  18. Investigation on structural analysis computer program of spent nuclear fuel shipping cask, (2)

    International Nuclear Information System (INIS)

    Yagawa, Ganki; Ikushima, Takeshi.

    1987-10-01

    This report describes the results (II) done by the Sub-Committee of Research Cooperation Committee (RC-62) of the Japan Society of Mechanical Engineers under the trust of the Japan Atomic Energy Research Institute. The principal fulfilments and accomplishments are summarized as follows: (1) Regarding the survey of structural analysis methods of spent fuel shipping cask, several documents, which explain the features and applications of the exclusive computer programs for impact analysis on the basis of 2 or 3 dimensional finite element or difference methods, were reviewed. (2) In comparative evaluation of the existing computer programs, the common benchmark test problems for drop impact of the axisymmetric cylinder and plate were adopted the calculational evaluations for taking into account the strain rate effect of material properties, effect of artificial viscosity and effect of time integration step size were carried out. (3) Evaluation of impact analysis algorithm of computer programs were conducted and the requirements for computer programs to be developed in future and an index for further studies have been clarified. (author)

  19. General re-evaluation of the safety on the nuclear ship 'Mutsu' and its repair work

    International Nuclear Information System (INIS)

    1980-01-01

    According to the proposition by the Committee for Investigation Radiation Leak on Mutsu, the works of the general re-evaluation of safety were started after the approval by the Committee for Investigating General Re-evaluation and Repair Techniques for Mutsu. The contents of the general re-evaluation of safety are the inspection of the machines and equipments in the nuclear reactor plant, the review of the design of the nuclear reactor plant, the analysis of the nuclear reactor plant behavior in accidents, and the related experimental researches. These works have been carried out for five years, and problem did not arise at all regarding the nuclear reactor so far, but from the viewpoint of improving the safety and reliability further, it was decided to carry out the repair work based on the general re-evaluation of safety. The contents of the repair work are the improvement of the emergency core-cooling system, the improvement of the safety protection system, the improvement of the radiation monitoring equipments, the improvement of the containment vessel boundary, the improvement of the actuators for technological safety facilities, the improvement of the method controlling secondary water quality, and other repair works. The progress of the general re-evaluation of safety is reported. (Kako, I.)

  20. The concept of underground nuclear heat and power plants (UNHPP) of upgraded safety, developed on the basis of ship-building technologies

    International Nuclear Information System (INIS)

    Pashin, V.M.; Petrov, Eh.L.; Shalik, G.P.; Khazov, B.S.; Malyshev, S.P.

    1996-01-01

    A concept of underground nuclear heat and power plants (UNHPP) of upgraded safety on the basis of ship-building technologies is considered, in which the priority is set to population security and environmental protection. Ways of realization of ziro radiation risk for the population residing in a close vicinity of UNHPP are substantiated. basic principles of the concept are formulated which envisage the use of ship propulsion reactor facilities that have been multiply tested in operation. The sources of economic competitiveness of UNHPPs, as compared with the existing NPPs, are shown

  1. Development and demonstration of surveillance and diagnostics of rotating machinery for reducing radiation exposure to nuclear power plant personnel: Appendices: Final report

    International Nuclear Information System (INIS)

    Allen, J.W.; Bohanick, J.S.

    1988-01-01

    This program was designed to reduce radiation exposure to power plant personnel resulting from inspection, maintenance, and repair of rotating equipment. The new rotating machinery monitoring system for this program was installed at GGNS during August 1983. The following nine appendices are presented: signals monitored at GGNS; definition of characterized spectral values; instructions for alignment and balance programs; machine diagrams; FFT program; software module descriptions; sample radiation survey forms used for exposure study; radiation exposure compared to other plants; and a technical section instruction for the vibration monitoring program at GGNS

  2. Superconducting magnets for model ship propulsion and for material tests of a nuclear fusion reactor

    International Nuclear Information System (INIS)

    Horiuchi, T.; Matsumoto, K.; Monju, Y.; Tatara, I.; Hamada, M.

    1982-01-01

    Nuclear fusion reactors, magnetically levitated trains, and MHD generators, etc., all need a very high magnetic field; which in order to be attained a means the application of superconductors is inevitable. This paper describes the development of ''CRYOZITT'', a superconductor featuring high current density and high mechanical strength. CRYOZITT has already been used in the manufacture of two race-track shaped superconducting magnets, and delivered to highly satisfied customers. (author)

  3. Modification of Japanese first nuclear ship reactor for a regional energy supply system using gadolinia as a burnable poison

    International Nuclear Information System (INIS)

    Sato, Kotaro; Shimazu, Yoichiro; Narabayashi, Tadashi; Tsuji, Masashi

    2009-01-01

    In our laboratory, a small regional energy supply system which uses a small nuclear reactor has been studied for a long time. This system could supply not only heat but also electricity. Heat could be used for hot-water supply, a heating system of a house, melting snow and so on. In this point, this system seems to be useful for the places like northern part of Japan where it snows in winter. This reactor is based on Nuclear Ship Mutsu which was developed as the first nuclear ship of Japan about 40 years ago. It has several advantages for a small reactor. For example, its moderator temperature coefficient is always to be deeply negative because boric acid solution is not used in moderator and coolant. This can lead to a self-controlled operation without control rod maneuvering for load change. But some modifications have been performed in order to satisfy requirements such as (1) longer core life without refueling and reshuffling, (2) reactivity adjustment for load change without control rods or soluble boron, (3) simpler operations for load changes and (4) ultimate safety with sufficient passive capability. In our previous study, we confirmed the core based on Mutsu core had longer core life (about 10 years) using high uranium enrichment fuel (more than 5wt%) and current 17x17 fuel assemblies. We also confirmed excess reactivity during the cycle could be suppressed using combination of erbium oxide (Er 2 O 3 ) and gadolinium oxide (Gd 2 O 3 ) as burnable poisons. Er 2 O 3 has advantages such that criticality safety can be kept even if uranium enrichment is more than 5wt% and burnup characteristics of the core can be gradual. But at this time there are 2 problems to apply for the core using Er 2 O 3 in Japan. First problem is that more than 5wt% enrichment fuel is not yet accepted in Japan. Second problem is that there are no experiences of using Er 2 O 3 in commercial reactors in Japan. Considering these problems, we have to modify the design of the core, using

  4. 46 CFR 167.15-20 - Inspections of nautical school ships.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Inspections of nautical school ships. 167.15-20 Section... NAUTICAL SCHOOL SHIPS Inspections § 167.15-20 Inspections of nautical school ships. (a) At each annual inspection, or oftener if deemed necessary, the inspector will inspect the hull, boilers, machinery...

  5. Thermal hydro-dynamic behavior of the nuclear-powered ship Mutsu in the power-up test

    International Nuclear Information System (INIS)

    Ishida, Toshihisa; Kusunoki, Tsuyoshi; Tanaka, Yoshimi; Yao, Toshiaki; Inoue, Kimio; Ochiai, Masa-aki

    1991-01-01

    The first Japanese nuclear ship N.S. Mutsu was tested with heavy load changes as ones of the full scale start-up tests. This paper describes the results of power increasing test, test of crash astern propulsion from ahead cruising, and turbine trip test; In the power increasing test, the main steam flow rate increased from 20 % flow to 70 % flow in 13 seconds; In the test of crash astern propulsion from ahead cruising, an astern turbine maneuvering handle was drawn to the position equivalent to about 60 % reactor power in 30 seconds after an ahead turbine stopping; In the turbine trip test, the ahead turbine was tripped manually at about 100 % power operation. From these tests it was verified that the Mutsu reactor is capable to respond smoothly and safely to the heavy load change without reactor scram, without workings of the pressurizer relief valve and main steam dump valve, and without need of any manual adjustment of the reactor control system. (author)

  6. Improvement of nuclear ship engineering simulation system. Hardware renewal and interface improvement of the integral type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Takahashi, Hiroki; Kyoya, Masahiko; Shimazaki, Junya [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Kano, Tadashi [KCS, Co., Mito, Ibaraki (Japan); Takahashi, Teruo [Energis, Co., Kobe, Hyogo (Japan)

    2001-10-01

    JAERI had carried out the design study about a lightweight and compact integral type reactor (an advanced marine reactor) with passive safety equipment as a power source for the future nuclear ships, and completed an engineering design. We have developed the simulator for the integral type reactor to confirm the design and operation performance and to utilize the study of automation of the reactor operation. The simulator can be used also for future research and development of a compact reactor. However, the improvement in a performance of hardware and a human machine interface of software of the simulator were needed for future research and development. Therefore, renewal of hardware and improvement of software have been conducted. The operability of the integral-reactor simulator has been improved. Furthermore, this improvement with the hardware and software on the market brought about better versatility, maintainability, extendibility and transfer of the system. This report mainly focuses on contents of the enhancement in a human machine interface, and describes hardware renewal and the interface improvement of the integral type reactor simulator. (author)

  7. 77 FR 70526 - Shipping Coordinating Committee; Notice of Committee Meeting

    Science.gov (United States)

    2012-11-26

    ... from machinery spaces --Development of requirements for ships carrying hydrogen and compressed natural gas vehicles --Consideration of IACS unified interpretations --Harmonization of the requirements for the location of entrances, air inlets and openings in the superstructures of tankers --Development of...

  8. Structural code benchmarking for the analysis of impact response of nuclear material shipping casks

    International Nuclear Information System (INIS)

    Glass, R.E.

    1984-01-01

    The Transportation Technology Center at Sandia National Laboratories has initiated a program to benchmark thermal and structural codes that are available to the nuclear material transportation community. The program consists of the following five phrases: (1) code inventory and review, (2) development of a cask-like set of problems, (3) multiple independent numerical analyses of the problems, (4) transfer of information, and (5) performance of experiments to obtain data for comparison with the numerical analyses. This paper will summarize the results obtained by the independent numerical analyses. The analyses indicate the variability that can be expected both due to differences in user-controlled parameters and from code-to-code differences. The results show that in purely elastic analyses, differences can be attributed to user controlled parameters. Model problems involving elastic/plastic material behavior and large deformations, however, have greater variability with significant differences reported for implicit and explicit integration schemes in finite element programs. This variability demonstrates the need to obtain experimental data to properly benchmark codes utilizing elastic/plastic material models and large deformation capability

  9. Matrix analysis of electrical machinery

    CERN Document Server

    Hancock, N N

    2013-01-01

    Matrix Analysis of Electrical Machinery, Second Edition is a 14-chapter edition that covers the systematic analysis of electrical machinery performance. This edition discusses the principles of various mathematical operations and their application to electrical machinery performance calculations. The introductory chapters deal with the matrix representation of algebraic equations and their application to static electrical networks. The following chapters describe the fundamentals of different transformers and rotating machines and present torque analysis in terms of the currents based on the p

  10. Pumping machinery theory and practice

    CERN Document Server

    Badr, Hassan M

    2014-01-01

    Pumping Machinery Theory and Practice comprehensively covers the theoretical foundation and applications of pumping machinery. Key features: Covers characteristics of centrifugal pumps, axial flow pumps and displacement pumpsConsiders pumping machinery performance and operational-type problemsCovers advanced topics in pumping machinery including multiphase flow principles, and two and three-phase flow pumping systemsCovers different methods of flow rate control and relevance to machine efficiency and energy consumptionCovers different methods of flow rate control and relevance to machine effi

  11. Safeness of radiological machinery

    International Nuclear Information System (INIS)

    Yokoyama, Shun

    1979-01-01

    The human factors affecting the safeness of radiological machinery, which are often very big and complicated machines, are described from the stand point of handling. 20 to 50% of the troubles on equipments seem to be caused by men. This percentage will become even higher in highly developed equipments. Human factors have a great influence on the safeness of radiological equipments. As the human factors, there are sensory factors and knowledge factors as well as psychological factors, and the combination of these factors causes mishandling and danger. Medical services at present are divided in various areas, and consist of the teamwork of the people in various professions. Good human relationship, education and control are highly required to secure the safeness. (Kobatake, H.)

  12. Necrosome core machinery: MLKL.

    Science.gov (United States)

    Zhang, Jing; Yang, Yu; He, Wenyan; Sun, Liming

    2016-06-01

    In the study of regulated cell death, the rapidly expanding field of regulated necrosis, in particular necroptosis, has been drawing much attention. The signaling of necroptosis represents a sophisticated form of a death pathway. Anti-caspase mechanisms (e.g., using inhibitors of caspases, or genetic ablation of caspase-8) switch cell fate from apoptosis to necroptosis. The initial extracellular death signals regulate RIP1 and RIP3 kinase activation. The RIP3-associated death complex assembly is necessary and sufficient to initiate necroptosis. MLKL was initially identified as an essential mediator of RIP1/RIP3 kinase-initiated necroptosis. Recent studies on the signal transduction using chemical tools and biomarkers support the idea that MLKL is able to make more functional sense for the core machinery of the necroptosis death complex, called the necrosome, to connect to the necroptosis execution. The experimental data available now have pointed that the activated MLKL forms membrane-disrupting pores causing membrane leakage, which extends the prototypical concept of morphological and biochemical events following necroptosis happening in vivo. The key role of MLKL in necroptosis signaling thus sheds light on the logic underlying this unique "membrane-explosive" cell death pathway. In this review, we provide the general concepts and strategies that underlie signal transduction of this form of cell death, and then focus specifically on the role of MLKL in necroptosis.

  13. Shipping Fairways

    Data.gov (United States)

    Department of Homeland Security — Various shipping zones delineate activities and regulations for marine vessel traffic. Traffic lanes define specific traffic flow, while traffic separation zones...

  14. Adaptive Beamforming Algorithms for Tow Ship Noise Canceling

    NARCIS (Netherlands)

    Robert, M.K.; Beerens, S.P.

    2002-01-01

    In towed array sonar, the directional noise originating from the tow ship, mainly machinery and hydrodynamic noise, often limits the sonar performance. When processed with classical beamforming techniques, loud tow ship noise induces high sidelobes that may hide detection of quiet targets in forward

  15. Ship Vibrations

    DEFF Research Database (Denmark)

    Sørensen, Herman

    1997-01-01

    Methods for calculating natural frequencies for ship hulls and for plates and panels.Evaluation of the risk for inconvenient vibrations on board......Methods for calculating natural frequencies for ship hulls and for plates and panels.Evaluation of the risk for inconvenient vibrations on board...

  16. Study and full-scale test of a high-velocity grade-crossing simulated accident of a locomotive and a nuclear-spent-fuel shipping cask

    International Nuclear Information System (INIS)

    Huerta, M.; Yoshimura, H.R.

    1983-02-01

    This report described structural analyses of a high-speed impact between a locomotive and a tractor-trailer system carrying a nuclear-spent-fuel shipping cask. The analyses included both mathematical and physical scale-modeling of the system. The report then describes the full-scale test conducted as part of the program. The system response is described in detail, and a comparison is made between the analyses and the actual hardware response as observed in the full-scale test. 34 figures

  17. 46 CFR 167.65-70 - Reports of accidents, repairs, and unsafe boilers and machinery by engineers.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Reports of accidents, repairs, and unsafe boilers and... of accidents, repairs, and unsafe boilers and machinery by engineers. (a) Before making repairs to a boiler of a nautical school ship the engineer in charge shall report, in writing, the nature of such...

  18. Test Ship

    Data.gov (United States)

    Federal Laboratory Consortium — The U. S. Navy dedicated the decommissioned Spruance Class destroyer ex-PAUL F. FOSTER (EDD 964), Test Ship, primarily for at sea demonstration of short range weapon...

  19. Evaluation of mechanical properties and low velocity impact characteristics of balsa wood and urethane foam applied to impact limiter of nuclear spent fuel shipping cask

    Energy Technology Data Exchange (ETDEWEB)

    Goo, Junsung; Shin, Kwangbok [Hanbat Nat' l Univ., Daejeon (Korea, Republic of); Choi, Woosuk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-11-15

    The paper aims to evaluate the low velocity impact responses and mechanical properties of balsa wood and urethane foam core materials and their sandwich panels, which are applied as the impact limiter of a nuclear spent fuel shipping cask. For the urethane foam core, which is isotropic, tensile, compressive, and shear mechanical tests were conducted. For the balsa wood core, which is orthotropic and shows different material properties in different orthogonal directions, nine mechanical properties were determined. The impact test specimens for the core material and their sandwich panel were subjected to low velocity impact loads using an instrumented testing machine at impact energy levels of 1, 3, and 5J. The experimental results showed that both the urethane foam and the balsa wood core except in the growth direction (z-direction) had a similar impact response for the energy absorbing capacity, contact force, and indentation. Furthermore, it was found that the urethane foam core was suitable as an impact limiter material owing to its resistance to fire and low cost, and the balsa wood core could also be strongly considered as an impact limiter material for a lightweight nuclear spent fuel shipping cask.

  20. The Planning, Licensing, Modifications, and Use of a Russian Vessel for Shipping Spent Nuclear Fuel by Sea in Support of the DOE RRRFR Program

    International Nuclear Information System (INIS)

    Tyacke, Michael; Bolshinsky, Igor; Tomczak, Wlodzimierz; Naletov, Sergey; Pichugin, Oleg

    2001-01-01

    The Russian Research Reactor Fuel Return (RRRFR) Program, under the U.S. Department of Energy's Global Threat Reduction Initiative, began returning Russian-supplied high-enriched uranium (HEU) spent nuclear fuel (SNF), stored at Russian-designed research reactors throughout the world, to Russia in January 2006. During the first years of making HEU SNF shipments, it became clear that the modes of transportation needed to be expanded from highway and railroad to include sea and air to meet the extremely aggressive commitment of completing the first series of shipments by the end of 2010. The first shipment using sea transport was made in October 2008 and used a non-Russian flagged vessel. The Russian government reluctantly allowed a one-time use of the foreign-owned vessel into their highly secured seaport, with the understanding that any future shipments would be made using a vessel owned and operated by a Russian company. ASPOL-Baltic of St. Petersburg, Russia, owns and operates a small fleet of vessels and has a history of shipping nuclear materials. ASPOL-Baltic's vessels were licensed for shipping nuclear materials; however, they were not licensed to transport SNF materials. After a thorough review of ASPOL Baltic's capabilities and detailed negotiations, it was agreed that a contract would be let with ASPOL-Baltic to license and refit their MCL Trader vessel for hauling SNF in support of the RRRFR Program. This effort was funded through a contract between the RRRFR Program, Idaho National Laboratory, and Radioactive Waste Management Plant of Swierk, Poland. This paper discusses planning, Russian and international maritime regulations and requirements, Russian authorities reviews and approvals, licensing, design, and modifications made to the vessel in preparation for SNF shipments. A brief summary of actual shipments using this vessel, experiences, and lessons learned also are described.

  1. The Planning, Licensing, Modifications, and Use of a Russian Vessel for Shipping Spent Nuclear Fuel by Sea in Support of the DOE RRRFR Program

    Energy Technology Data Exchange (ETDEWEB)

    Michael Tyacke; Dr. Igor Bolshinsky; Wlodzimierz Tomczak; Sergey Naletov; Oleg Pichugin

    2001-10-01

    The Russian Research Reactor Fuel Return (RRRFR) Program, under the U.S. Department of Energy’s Global Threat Reduction Initiative, began returning Russian-supplied high-enriched uranium (HEU) spent nuclear fuel (SNF), stored at Russian-designed research reactors throughout the world, to Russia in January 2006. During the first years of making HEU SNF shipments, it became clear that the modes of transportation needed to be expanded from highway and railroad to include sea and air to meet the extremely aggressive commitment of completing the first series of shipments by the end of 2010. The first shipment using sea transport was made in October 2008 and used a non-Russian flagged vessel. The Russian government reluctantly allowed a one-time use of the foreign-owned vessel into their highly secured seaport, with the understanding that any future shipments would be made using a vessel owned and operated by a Russian company. ASPOL-Baltic of St. Petersburg, Russia, owns and operates a small fleet of vessels and has a history of shipping nuclear materials. ASPOL-Baltic’s vessels were licensed for shipping nuclear materials; however, they were not licensed to transport SNF materials. After a thorough review of ASPOL Baltic’s capabilities and detailed negotiations, it was agreed that a contract would be let with ASPOL-Baltic to license and refit their MCL Trader vessel for hauling SNF in support of the RRRFR Program. This effort was funded through a contract between the RRRFR Program, Idaho National Laboratory, and Radioactive Waste Management Plant of Swierk, Poland. This paper discusses planning, Russian and international maritime regulations and requirements, Russian authorities’ reviews and approvals, licensing, design, and modifications made to the vessel in preparation for SNF shipments. A brief summary of actual shipments using this vessel, experiences, and lessons learned also are described.

  2. Fast ship

    OpenAIRE

    Keuning, J.A.

    2014-01-01

    The invention concerns a ship whereby the hull and the mechanical propulsion device are designed such that the Froude number is larger than 0.5. In the aft ship the hull has a bottom with V-shaped bottom surfaces with a deadrise angle that is less than 40 degrees and the hull has substantially vertical sides. In the hull are a passenger compartment and a trim tank. The trim tank volume is such that the weight of a filled trim tank is more than 30 % of the weight of displacement of the hull wi...

  3. Investigations of active interrogation techniques to detect special nuclear material in maritime environments: Standoff interrogation of small- and medium-sized cargo ships

    International Nuclear Information System (INIS)

    Miller, Thomas M.; Patton, Bruce W.; Grogan, Brandon R.; Henkel, James J.; Murphy, Brian D.; Johnson, Jeffrey O.; Mihalczo, John T.

    2013-01-01

    In this work, several active interrogation (AI) sources are evaluated to determine their usefulness in detecting the presence of special nuclear material (SNM) in fishing trawlers, small cargo transport ships, and luxury yachts at large standoff distances from the AI source and detector. This evaluation is performed via computational analysis applying Monte Carlo methods with advanced variance reduction techniques. The goal is to determine the AI source strength required to detect the presence of SNM. The general conclusion of this study is that AI is not reliable when SNM is heavily shielded and not tightly coupled geometrically with the source and detector, to the point that AI should not be considered a via interrogation option in these scenarios. More specifically, when SNM is shielded by hydrogenous material large AI source strengths are required if detection is based on neutrons, which is not surprising. However, if the SNM is shielded by high-Z material the required AI source strengths are not significantly different if detection is based on neutrons or photons, which is somewhat surprising. Furthermore, some of the required AI source strengths that were calculated are very large. These results coupled with the realities of two ships moving independently at sea and other assumptions made during this analysis make the use of standoff AI in the maritime environment impractical

  4. Investigations of active interrogation techniques to detect special nuclear material in maritime environments: Standoff interrogation of small- and medium-sized cargo ships

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Thomas M., E-mail: millertm@ornl.gov; Patton, Bruce W.; Grogan, Brandon R.; Henkel, James J.; Murphy, Brian D.; Johnson, Jeffrey O.; Mihalczo, John T.

    2013-12-01

    In this work, several active interrogation (AI) sources are evaluated to determine their usefulness in detecting the presence of special nuclear material (SNM) in fishing trawlers, small cargo transport ships, and luxury yachts at large standoff distances from the AI source and detector. This evaluation is performed via computational analysis applying Monte Carlo methods with advanced variance reduction techniques. The goal is to determine the AI source strength required to detect the presence of SNM. The general conclusion of this study is that AI is not reliable when SNM is heavily shielded and not tightly coupled geometrically with the source and detector, to the point that AI should not be considered a via interrogation option in these scenarios. More specifically, when SNM is shielded by hydrogenous material large AI source strengths are required if detection is based on neutrons, which is not surprising. However, if the SNM is shielded by high-Z material the required AI source strengths are not significantly different if detection is based on neutrons or photons, which is somewhat surprising. Furthermore, some of the required AI source strengths that were calculated are very large. These results coupled with the realities of two ships moving independently at sea and other assumptions made during this analysis make the use of standoff AI in the maritime environment impractical.

  5. Fault size classification of rotating machinery using support vector machine

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Y. S.; Lee, D. H.; Park, S. K. [Korea Hydro and Nuclear Power Co. Ltd., Daejeon (Korea, Republic of)

    2012-03-15

    Studies on fault diagnosis of rotating machinery have been carried out to obtain a machinery condition in two ways. First is a classical approach based on signal processing and analysis using vibration and acoustic signals. Second is to use artificial intelligence techniques to classify machinery conditions into normal or one of the pre-determined fault conditions. Support Vector Machine (SVM) is well known as intelligent classifier with robust generalization ability. In this study, a two-step approach is proposed to predict fault types and fault sizes of rotating machinery in nuclear power plants using multi-class SVM technique. The model firstly classifies normal and 12 fault types and then identifies their sizes in case of predicting any faults. The time and frequency domain features are extracted from the measured vibration signals and used as input to SVM. A test rig is used to simulate normal and the well-know 12 artificial fault conditions with three to six fault sizes of rotating machinery. The application results to the test data show that the present method can estimate fault types as well as fault sizes with high accuracy for bearing an shaft-related faults and misalignment. Further research, however, is required to identify fault size in case of unbalance, rubbing, looseness, and coupling-related faults.

  6. Fault size classification of rotating machinery using support vector machine

    International Nuclear Information System (INIS)

    Kim, Y. S.; Lee, D. H.; Park, S. K.

    2012-01-01

    Studies on fault diagnosis of rotating machinery have been carried out to obtain a machinery condition in two ways. First is a classical approach based on signal processing and analysis using vibration and acoustic signals. Second is to use artificial intelligence techniques to classify machinery conditions into normal or one of the pre-determined fault conditions. Support Vector Machine (SVM) is well known as intelligent classifier with robust generalization ability. In this study, a two-step approach is proposed to predict fault types and fault sizes of rotating machinery in nuclear power plants using multi-class SVM technique. The model firstly classifies normal and 12 fault types and then identifies their sizes in case of predicting any faults. The time and frequency domain features are extracted from the measured vibration signals and used as input to SVM. A test rig is used to simulate normal and the well-know 12 artificial fault conditions with three to six fault sizes of rotating machinery. The application results to the test data show that the present method can estimate fault types as well as fault sizes with high accuracy for bearing an shaft-related faults and misalignment. Further research, however, is required to identify fault size in case of unbalance, rubbing, looseness, and coupling-related faults

  7. Act N0 68-1045 of 29 November 1968 amending Act N0 65-956 of 12 November 1965 on the third party liability of operators of nuclear ships

    International Nuclear Information System (INIS)

    1968-01-01

    This Act amends the 1965 Act, in particular by specifying that the maximum amount of liability of the operator of a foreign nuclear ship is that fixed by the legislation of the State concerned, unless otherwise agreed with that State, but may in no case be lower than that set out in the 1965 Act, namely 500 million French francs. (NEA) [fr

  8. Ship's barbers

    OpenAIRE

    Unknown

    2003-01-01

    Showing two sailors having their hair cut (? one is possibly being shaved) on board ship. Three other sailors can be seen standing on the right-hand side of the photograph. The photograph is from an album inscribed 'H.M.S. Lancaster; Mediterranean Photographic Album: Diary of Events and Important Places Visited during the Commission 1910-1912' on the cover. This album was the property of Sydney Harold Liddle.

  9. Updating the model TREMOD - Mobile Machinery (TREMOD-MM); Aktualisierung des Modells TREMOD - Mobile Machinery (TREMOD-MM)

    Energy Technology Data Exchange (ETDEWEB)

    Helms, Hinrich; Lambrecht, Udo; Knoerr, Wolfram [ifeu - Institut fuer Energie- und Umweltforschung Heidelberg gGmbH, Heidelberg (Germany)

    2010-05-15

    In the context of the project ''Development of a model for the computation of the air pollutant emissions and the fuel consumption of combustion engines in mobile devices and machines'', the Institute for Energy and Environmental Research GmbH (Heidelberg, Federal Republic of Germany) has created the model TREMOD-MM (TREMOD Mobile Machinery). Thus a detailed computation of the emissions from mobile devices and machines in the agriculture, construction industry, forestry and gardening as well as the sport shipping and passenger shipping can be accomplished. Strongly differentiated data are considered to the age structure, engine performance, use and emission behaviour. Thus it is possible to compute the emissions for different scenarios in high degree of detail.

  10. Prospects for the utilization of small nuclear plants for civil ships, floating heat and power stations and power seawater desalination complexes

    International Nuclear Information System (INIS)

    Polunichev, V.I.

    2000-01-01

    Small power nuclear reactor plants developed by OKB Mechanical Engineering are widely used as propulsion plants in various civil ships. Russia is the sole country in the world that possesses a powerful icebreaker and transport fleet which offers effective solution for vital socio-economic tasks of Russia's northern regions by maintaining a year-round navigation along the Arctic sea route. In the future, intensification of freighting volumes is expected in Arctic seas and at estuaries of northern rivers. Therefore, further replenishment of nuclear-powered fleet is needed by new generation ice-breakers equipped with advanced reactor plants. Adopted progressive design and technology solutions, reliable equipment and safety systems being continuously perfected on the basis of multi year operation experience feedback, addressing updated safety codes and achievement of science and technology, allow the advanced propulsion reactor plants of this type to be recommended as energy sources for floating heat and power co-generation stations and power-seawater desalination complexes. (author)

  11. Enhanced-safety underground nuclear power plants based on the use of proven ship-building equipment and technology

    International Nuclear Information System (INIS)

    Pashin, V.M.; Petrov, E.L.; Khazov, B.S.

    1995-01-01

    Investigations performed in the last few years by the State Science Center of the Russian Federation - Academician A. N. Krylov Central Scientific-Research Institute, together with specialized enterprises of the Ministry of Atomic Energy of the Russian Federation, Sudprom, and other agencies of Russia, have shown the promise of marine nuclear power plants for producing underground nuclear power plants with a higher degree of protection from external and internal actions of different intensity. The concept was developed on the basis of an analysis of the energy supply in different regions of Russia and the near-abroad using fossil fuels (lignite, oil, natural gas). The change in the international environment, which makes it possible to convert the military technology, frees the industrial potential and skilled workers in Russia for development of products for the national economy. Stricter international standards and rules for increased safety and protection of nuclear power plants made it necessary to develop a new generation of reactors for ground-based power plants, which under the modern economic conditions cannot be implemented within the time periods acceptable for economics for most of the countries surrounding Russia. In the development of a new generation of ground-based nuclear power plants, the intense improvement of the aviation and space technology must be taken into account. This is connected with the increase in the catastrophes and the threat they present to the safety of unprotected power plants. This article is an abstract of the entire report

  12. Strategies for Improving Enterprise Standardization Management of Tropical Crop Machinery

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    @@ There are two categories of tropical crop machinery. One comprises operation machinery that is used for planting, managing and harvesting tropical crops, while the other comprises process machinery for processing tropical crops. Tropical crop machinery is distinguished from other agricultural machinery by the special crops that such machinery cultivates and processes.

  13. Progress in control equipment for fuel-handling machinery

    International Nuclear Information System (INIS)

    Nutting, B.A.

    1986-01-01

    The paper outlines the development of the equipment used to control the fuel-handling machinery associated with nuclear reactors, from the early electromechanical equipment, through solid-state switching logic to programmable controllers and microprocessors. The control techniques have developed along with the technology, and modern systems offer versatility, reliability and ease of design, operation and maintenance. Future trends and developments are discussed together with possible limiting factors. (author)

  14. Corruption analysis and life span forecast research on sylphon bellows of nuclear-powered steam system of ship

    International Nuclear Information System (INIS)

    Song Chao; Chen Lisheng; Song Meicun; Wang Wei

    2012-01-01

    The fracture of the corrugated pipe has a dad effect to the operation of reactor which can cause the small-break LOCA. The corrosion is the key reason of the fracture. On the base of the analysis on corruption reason of the sylphon bellows and combine the characteristic of the limited sample point of it, the Grey theory was used in the assessment of corrosion life span of corrugated pipe in nuclear steam system. Through applying the GM (1, 1) model in inferring the discipline of corrosion quantity and combining traditional statistical method, the corrosion life of steam pipe was evaluated. It indicates that the model is precise, simple and the result is reliable. (authors)

  15. State of opening the cover and carrying out the checkup of the reactor vessel of the nuclear-powered ship 'Mutsu' by Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    1989-01-01

    In the checkup by opening the cover of the reactor vessel of the nuclear-powered ship 'Mutsu', Japan Atomic Energy Research Institute carried out the checkup and maintenance for the reactor proper, control system and primary coolant facilities including the secondary side of steam generators and the pressure balancing valve of the containment vessel. The works were classified into the opening of the reactor, checkup, maintenance and restoration. The opening was begun on August 4, 1988, and finished on December 5. The checkup and maintenance were begun on September 22, and are still continued now. The maximum radiation dose rate on the surfaces of fuel assemblies and control rods and at the positions 1 m distant from them was measured. The results of the checkup of various components are reported. In 290 absorbent rods of control rods, spot corrosion and discoloration were observed, of which the spot corrosion penetrated the walls of 4 rods. Also in 12 fuel rods, spot corrosion was observed near the welded end plugs, but leak was not observed. (K.I.)

  16. Ex-core detector response caused by control rod misalignment observed during operation of the reactor on the nuclear ship Mutsu

    International Nuclear Information System (INIS)

    Itagaki, Masafumi; Miyoshi, Yoshinori; Gakuhari, Kazuhiko; Okada, Noboru; Sakai, Tomohiro

    1993-01-01

    Unexpected deviations of ex-core neutron detector signals were observed during a voyage of the Japanese nuclear ship, Mutsu. From detailed three-dimensional analyses, this phenomenon was determined to be caused by an asymmetrical neutron source distribution in the core due to a small misalignment between the two control rods of a control rod group. A systematic ex-core detector response experiment was performed during the Mutsu's third experimental voyage to gain some understanding of the relationship between the control rod pattern and the detector response characteristics. Results obtained from analyses of the experiment indicate that the Crump-Lee technique, using calculated three-dimensional source distributions for various control rod patterns, provides good agreement between the calculated and measured detector responses. Xenon transient analyses were carried out to generate accurate three-dimensional source distributions for predicting the time-dependent detector response characteristics. Two types of ex-core detector responses are caused by changes in the control rod pattern in the Mutsu reactor: the detector response ratio tends to decrease with the withdrawal of a group of control rods as a pair, and a difference in the positions of the control rods in a group causes signal deviations among the four ex-core detectors. Control rod misalignment does not greatly affect the mean value of the four detector signals, and the deviation can be minimized if the two rods within a group are set at the same elevation at the time of detector calibration

  17. Transnucleaire's experience in ship adaptation

    International Nuclear Information System (INIS)

    Brachet, Y.; Vallette-Fontaine, M.

    2000-01-01

    Due to the application of the new IMDG regulations for the transport of radioactive material by sea, the conditions of transport of MTR spent fuel have drastically changed five years ago. In this paper, TRANSNUCLEAIRE analyses the necessary modifications to apply to existing ships in order to comply with the IMDG/INF regulations as well as with the Japanese KAISA 520 regulation. In the MTR spent fuel transport market characterized by a competitive approach, TRANSNUCLEAIRE has carried out many transports by sea in full compliance with the regulations at a price which is as close as possible to that of other industrial goods and without the need to fully dedicate the BOUGUENAIS ship to nuclear transports. Innovative ship design solutions have been implemented and accepted by different Authorities uncluding the Advisory Committee of the Japanese MOT. Due to efficient finite element calculations, benchmarked by laboratory large scale tests, high performances crushing materials have been developed in order to absorb the energy of collision between ships. These developments have led ta propose an efficient ship design complying with all the existing worldwide nuclear regulations. (author)

  18. Merchant shipping (Safety Convention) Act 1977

    International Nuclear Information System (INIS)

    1977-01-01

    When this Act comes into force, it will enable the United Kingdom to ratify and to give effect to the 1974 International Convention for the Safety of Life at Sea (the SOLAS Convention) which replaces the SOLAS Convention of 1960. Under the Act, the Secretary of State may make such rules as he considers appropriate regarding ships provided with nuclear power plants in accordance with Chapter VIII of the Annex to the 1974 Convention and to Recommendations attached to it, dealing with nuclear ships, and insofar as those provisions have not been implemented by the Merchant Shipping Acts 1894 to 1974. (NEA) [fr

  19. Green Shipping Practices of Shipping Firms

    Directory of Open Access Journals (Sweden)

    Young-Tae Chang

    2017-05-01

    Full Text Available The primary objective of this study is to provide an empirical research using structural equation modeling to identify the factors that motivate shipping firms to adopt green shipping practices (GSP. Furthermore, it also examines if adopting GSP can enhance the shipping firms’ environmental and productivity performance. The findings show that shipping firms are motivated to adopt GSP mostly by industrial norms set by institutionalized associations. They are also motivated by customers’ demand for environmental friendliness and their own strategy to make good image. Unlike our expectation, government regulations and international environmental laws are not significant in influencing shipping firms to adopt GSP. Moreover, adoption of green shipping practices can improve the environmental and productivity performance of the shipping firms.

  20. Green shipping management

    CERN Document Server

    Lun, Y H Venus; Wong, Christina W Y; Cheng, T C E

    2016-01-01

    This book presents theory-driven discussion on the link between implementing green shipping practices (GSP) and shipping firm performance. It examines the shipping industry’s challenge of supporting economic growth while enhancing environmental performance. Consisting of nine chapters, the book covers topics such as the conceptualization of green shipping practices (GSPs), measurement scales for evaluating GSP implementation, greening capability, greening and performance relativity (GPR), green management practice, green shipping network, greening capacity, and greening propensity. In view of the increasing quest for environment protection in the shipping sector, this book provides a good reference for firms to understand and evaluate their capability in carrying out green operations on their shipping activities.

  1. The shipping man adventures in ship finance

    CERN Document Server

    McCleery, Matthew

    2013-01-01

    When restless New York City hedge fund manager Robert Fairchild watches the Baltic Dry Cargo Index plunge 97%, registering an all-time high and a 25-year low within the span of just six months, he decides to buy a ship. Immediately fantasizing about naming a vessel after his wife, carrying a string of worry beads and being able to introduce himself as a "shipowner" at his upcoming college reunion, Fairchild immediately embarks on an odyssey into the most exclusive, glamorous and high stakes business in the world. From pirates off the coast of Somalia and on Wall Street to Greek and Norwegian shipping magnates, the education of Robert Fairchild is an expensive one. In the end, he loses his hedge fund, but he gains a life - as a Shipping Man. Part fast paced financial thriller, part ship finance text book, The Shipping Man is 310 pages of required reading for anyone with an interest in capital formation for shipping.

  2. Survey of nuclear insurance - Parts 1 and 2

    International Nuclear Information System (INIS)

    Francis, H.W.

    1979-01-01

    The use of nuclear energy developed comparatively suddenly and introduced hazards with which insurers were quite unfamiliar as compared to conventional hazards such as fire or explosion. In addition to the possibility of severe contamination to property and serious injury to persons on a large scale, radiation damage may become apparent long after actual exposure to radiation. All these factors made nuclear insurance mandatory. In order to marshall the large insurance capacity needed, 23 nuclear insurance pools similar to the British Insurance Committee, were set up and are operating in some 22 countries. The insurance covers written by nuclear pools are related to material damage, liability, losses, machinery breakdown contingent liabilities of suppliers of goods and services and finally transport risks and nuclear-propelled ships. (NEA) [fr

  3. Rotating machinery surveillance system reduces plant downtime and radiation exposure

    International Nuclear Information System (INIS)

    Bohanick, J.S.; Robinson, J.C.; Allen, J.W.

    1988-01-01

    A rotating machinery surveillance system (RMSS) was permanently installed at Grand Gulf nuclear station (GGNS) as part of a program sponsored by the US Department of Energy whose goal was to reduce radiation exposure to power plant personnel resulting from the inspection, maintenance, and repair of rotating machinery. The RMSS was installed at GGNS in 1983 to continuously monitor 173 analog vibration signals from proximity probes mounted on 26 machine trains and ∼450 process data points via a computer data link. Vibration frequency spectra, i.e., the vibration amplitude versus frequency of vibration, and various characterizations of these spectra are the fundamental data collected by the RMSS for performing machinery diagnostics. The RMSS collects vibration frequency spectra on a daily basis for all the monitored rotating equipment and automatically stores the collected spectra for review by the vibration engineer. Vibration spectra automatically stored by the RMSS fall into categories that include the last normal, alarm, minimum and maximum, past three-day data set, baseline, current, and user-saved spectra. During first and second fuel-cycle operation at GGNS, several significant vibration problems were detected by the RMSS. Two of these are presented in this paper: recirculation pumps and turbine-generator bearing degradation. The total reduction in personnel radiation exposure at GGNS from 1985 to 1987 due to the presence of the RMSS was estimated to be in the range from 49 to 54 person-rem

  4. It's safety first on N-fuel carrier ship

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    The 3 000t deadweight ship to carry irradiated nuclear fuel ordered recently from Appledore Shipbuilders will be one of the most sophisticated ships built at the firm's modern and totally-enclosed north Devon yard. The ship will be used to carry irradiated nuclear fuel from Japan to be reprocessed at British Nuclear Fuels site at Sellafield and at the Cogema plant in northern France. It has been designed to conform to the most exacting requirements of Pacific Nuclear Transport and will incorporate every safeguard for the shipment of irradiated nuclear fuels

  5. Study of accident environment during sea transport of nuclear material: Analysis of an engine room fire on a purpose built ship. Annex 5

    International Nuclear Information System (INIS)

    Yamamoto, K.; Shibata, H.; Ouchi, Y.; Kitamura, T.; Ito, T.; Hohnstreiter, G.F.; Pierce, J.D.; Koski, J.A.; Dukart, R.J.

    2001-01-01

    The program goal was to show that the IAEA safe transport regulations adequately cover the thermal effects of an engine-room fire on plutonium transportation packages stowed aboard a purpose built ship. The packages are stored in transportation containers located in a cargo hold of the ship. This study addressed the heat transfer from an engine-room fire that could heat and evaporate water out of the water-filled bulkhead and the resulting temperature conditions around the packages and inside the packages near their elastomeric seals. This study was designed to estimate the thermal response of a plutonium package in the hold of a purpose built ship during a shipboard fire, and furthermore, to confirm the sufficiency and adequacy of the current IAEA transport regulation

  6. Guide to ship sanitation

    National Research Council Canada - National Science Library

    2011-01-01

    "The third edition of the Guide to Ship Sanitation presents the public health significance of ships in terms of disease and highlights the importance of applying appropriate control measures"--Back cover...

  7. Production of Liquid Synthetic Fuels from Carbon, Water and Nuclear Power on Ships and at Shore Bases for Military and Potential Commercial Applications

    International Nuclear Information System (INIS)

    Locke Bogart, S.; Schultz, Ken; Brown, Lloyd; Russ, Ben

    2006-01-01

    It is demonstrable that synthetic fuels (jet/diesel/gasoline ≅ (CH 2 ) n ) can be produced from carbon, water, and nuclear energy. What remains to be shown is that all system processes are scalable, integrable, and economical. Sources of carbon include but are not limited to CO 2 from the atmosphere or seawater, CO 2 from fossil-fired power plants, and elemental carbon from coal or biomass. For mobile defense (Navy) applications, the ubiquitous atmosphere is our chosen carbon source. For larger-scale sites such as Naval Advance Bases, the atmosphere may still be the choice should other sources not be readily available. However, at many locations suitable for defense and, potentially, commercial syn-fuel production, far higher concentrations of carbon may be available. The rationale for this study was manifold: fuel system security from terrorism and possible oil embargoes; rising demand and, eventually, peaking supply of conventional petroleum; and escalating costs and prices of fuels. For these reasons, the initial parts of the study were directed at Syn-fuel production for mobile Naval platforms and shore sites such as Rokkasho, Japan (as an exemplar). Nuclear reactors would provide the energy for H 2 from water-splitting, Membrane Gas Absorption (MGA) would extract CO 2 from the atmosphere, the Reverse Water-Gas Reaction (RWGR) would convert the CO 2 to CO, and the resultant H 2 and CO feeds would be converted to (CH 2 )n by the Fischer-Tropsch reaction. Many of these processes exist at commercial scale. Some, particularly MGA and RWGR, have been demonstrated at the bench-scale, requiring up-scaling. Likewise, the demonstration of an integrated system at some scale is yet to be done. For ship-based production, it has been shown that the system should be viable and, under reasonable assumptions, both scalable and economical for defense fuels. For the assumptions in the study, fuel cost estimates range from ∼ $2.55 to $4.75 per gallon with a nominal cost of

  8. Recycling of merchant ships

    Directory of Open Access Journals (Sweden)

    Magdalena Klopott

    2013-12-01

    Full Text Available The article briefly outlines the issues concerning ship recycling. It highlights ships' high value as sources of steel scrap and non-ferrous metals, without omitting the fact that they also contain a range of hazardous substances. Moreover, the article also focuses on basic ship demolition methods and their environmental impact, as well as emphasizes the importance of “design for ship recycling” philosophy.

  9. Dutch Ships and Sailors

    NARCIS (Netherlands)

    de Boer, Victor; Hoekstra, F.G.; Leinenga, Jurjen; van Rossum, Matthias

    2014-01-01

    Dutch Ships and Sailors provides an infrastructure for maritime historical datasets, linking correlating data through semantic web technology. It brings together datasets related to recruitment and shipping in the East-India trade (mainly 18th century) and in the shipping of the northern provinces

  10. Thermo-hydraulic characteristics of ship propulsion reactor in the conditions of ship motions and safety assessment

    International Nuclear Information System (INIS)

    Kobayashi, Michiyuki; Murata, Hiroyuki; Sawada, Kenichi; Inasaka, Fujio; Aya, Izuo; Shiozaki, Koki

    1999-01-01

    By inputting the experimental data, information and others on thermo-hydraulic characteristics of integrated ship propulsion reactor accumulated hitherto by the Ship Research Institute and some recent cooperation results into the nuclear ship engineering simulation system, it was conducted not only to contribute an improvement study on next ship reactor by executing general analysis and evaluation on motion characteristics under ship body motion conditions, safety at accidents, and others of the integrated ship reactor but also to investigate and prepare some measures to apply fundamental experiment results based on obtained here information to safety countermeasure of the nuclear ships. In 1997 fiscal year, on safety of the integrated ship propulsion reactor loading nuclear ship, by adding experimental data on unstable flow analysis and information on all around of the analysis to general data base fundamental program, development to intellectual data base program was intended; on effect of pulsation flow on thermo-hydraulic characteristics of ship propulsion reactor; after pulsation flow visualization experiment, experimental equipment was reconstructed into heat transfer type to conduct numerical analysis of pulsation flow by confirming validity of numerical analysis code under comparison with the visualization experiment results; and on thermo-hydraulic behavior in storage container at accident of active safety type ship propulsion reactor; a flashing vibration test using new apparatus finished on its higher pressurization at last fiscal year to examine effects of each parameter such as radius and length of exhausting nozzle and pool water temperature. (G.K.)

  11. Automatic temperature control method of shipping can

    International Nuclear Information System (INIS)

    Nishikawa, Kaoru.

    1992-01-01

    The present invention provides a method of rapidly and accurately controlling the temperature of a shipping can, which is used upon shipping inspection for a nuclear fuel assembly. That is, a measured temperature value of the shipping can is converted to a gas pressure setting value in a jacket of the shipping can by conducting a predetermined logic calculation by using a fuzzy logic. A gas pressure control section compares the pressure setting value of a fuzzy estimation section and the measured value of the gas pressure in the jacket of the shipping can, and conducts air supply or exhaustion of the jacket gas so as to adjust the measured value with the setting value. These fuzzy estimation section and gas pressure control section control the gas pressure in the jacket of the shipping can to control the water level in the jacket. As a result, the temperature of the shipping can is controlled. With such procedures, since the water level in the jacket can be controlled directly and finely, temperature of the shipping can is automatically controlled rapidly and accurately compared with a conventional case. (I.S.)

  12. Machinery condition monitoring principles and practices

    CERN Document Server

    Mohanty, Amiya Ranjan

    2015-01-01

    Find the Fault in the MachinesDrawing on the author's more than two decades of experience with machinery condition monitoring and consulting for industries in India and abroad, Machinery Condition Monitoring: Principles and Practices introduces the practicing engineer to the techniques used to effectively detect and diagnose faults in machines. Providing the working principle behind the instruments, the important elements of machines as well as the technique to understand their conditions, this text presents every available method of machine fault detection occurring in machines in general, an

  13. Domestication of self-splicing introns during eukaryogenesis : the rise of the complex spliceosomal machinery

    NARCIS (Netherlands)

    Vosseberg, Julian; Snel, Berend

    2017-01-01

    ᅟ: The spliceosome is a eukaryote-specific complex that is essential for the removal of introns from pre-mRNA. It consists of five small nuclear RNAs (snRNAs) and over a hundred proteins, making it one of the most complex molecular machineries. Most of this complexity has emerged during

  14. Study of the Accident Environment During Sea Transport of Nuclear Material: Analysis of an Engine-room Fire on a Purpose-built Ship (invited paper)

    International Nuclear Information System (INIS)

    Yamamoto, K.; Kitamura, T.; Shibata, K.; Ouchi, Y.; Ito, T.; Hohnstreiter, G.F.; Pierce, J.D.; Koski, J.A.; Dukart, R.K.

    2000-01-01

    The programme goal was to show that the IAEA safe transport regulations adequately cover the thermal effects of an engine-room fire on plutonium transport packages stowed aboard a purpose-built ship. The packages are stored in transport containers located in a cargo hold of the ship. For this study, it was assumed that the packages in No 5 hold, adjacent to an engine-room, could be subject to heating due to a fire in the engine-room. The No 5 hold and the engine-room are separated by a water-filled bulkhead. This study addressed the heat transfer from an engine-room fire that could heat and evaporate water out of the water-filled bulkhead and the resulting temperature conditions around the packages and inside the packages near their elastometric seals. (author)

  15. Condition Monitoring of Machinery in Non-Stationary Operations : Proceedings of the Second International Conference "Condition Monitoring of Machinery in Non-Stationnary Operations"

    CERN Document Server

    Bartelmus, Walter; Chaari, Fakher; Zimroz, Radoslaw; Haddar, Mohamed

    2012-01-01

    Condition monitoring of machines in non-stationary operations (CMMNO) can be seen as the major challenge for research in the field of machinery diagnostics. Condition monitoring of machines in non-stationary operations is the title of the presented book and the title of the Conference held in Hammamet - Tunisia March 26 – 28, 2012. It is the second conference under this title, first took place in Wroclaw - Poland , March 2011. The subject CMMNO comes directly from industry needs and observation of real objects. Most monitored and diagnosed objects used in industry works in non-stationary operations condition. The non-stationary operations come from fulfillment of machinery tasks, for which they are designed for. All machinery used in different kind of mines, transport systems, vehicles like: cars, buses etc, helicopters, ships and battleships and so on work in non-stationary operations. The papers included in the book are shaped by the organizing board of the conference and authors of the papers. The papers...

  16. CCPIT Machinery Exhibition Succeeded in Kuala Lumpur

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    @@ From August 18 to 20, 2005, China Council for the Promotion of International Trade(CCPIT) held China Machinery and Electronics Trade Exhibition, CME 2005 in Kuala Lumpur, the capital of Malaysia on behalf of China, a good job has been done.

  17. CCPIT Machinery Exhibition Succeeded in Kuala Lumpur

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

      From August 18 to 20, 2005, China Council for the Promotion of International Trade(CCPIT) held China Machinery and Electronics Trade Exhibition, CME 2005 in Kuala Lumpur, the capital of Malaysia on behalf of China, a good job has been done.……

  18. Buckling of Ship Structures

    CERN Document Server

    Shama, Mohamed

    2013-01-01

    Buckling of Ship Structures presents a comprehensive analysis of the buckling problem of ship structural members. A full analysis of the various types of loadings and stresses imposed on ship plating and primary and secondary structural members is given. The main causes and consequences of the buckling mode of failure of ship structure and the methods commonly used to control buckling failure are clarified. This book contains the main equations required to determine the critical buckling stresses for both ship plating and the primary and secondary stiffening structural members. The critical buckling stresses are given for ship plating subjected to the induced various types of loadings and having the most common boundary conditions encountered in ship structures.  The text bridges the gap existing in most books covering the subject of buckling of ship structures in the classical analytical format, by putting the emphasis on the practical methods required to ensure safety against buckling of ship structur...

  19. Model of a Nuclear Security Naval Agency for radiation control of the Industrial Complex of of Submarine Construction and Maintenance Ship with Nuclear Propulsion; Modelo de uma Agência Naval de Segurança Nuclear para o controle radiológico do complexo industrial de construção e manutenção do submarino com propulsão nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lins Junior, Amilton de Sousa

    2017-07-01

    Due to the construction, by Brazilian Navy, of a Submarine Construction and Maintenance Ship with Nuclear Propulsion, where, among other activities, the commissioning and exchange of the fuel elements of the reactor in the future Nuclear Submarine, and of a Naval Base where the Nuclear Submarine and the Conventional Submarines, it is necessary the establishment of a Nuclear Security Naval Agency to monitor activities involving ionizing radiation sources and nuclear materials aimed at the radiological protection of exposed occupationally individuals (IOE), the general public and the environment. It should be noted that nuclear and radioactive material will be present only in a part of the yard called Radiological Complex. Therefore, the development of a structure for the control of the Radiological Complex is fundamental, considering that the future licensing process will be unprecedented in Brazil and will face several difficulties. This work presents a model of a structure for the radiological control of the industrial complex for the construction and maintenance of the submarine with nuclear propulsion, as well as the fundamental concepts of the activities, such as inspection, regulations and authorizations, to be carried out by the various component sectors of the Nuclear Security Naval Agency. (author)

  20. Thermo-hydraulic characteristics of ship propulsion reactor in the conditions of ship motions and safety assessment

    International Nuclear Information System (INIS)

    Kobayashi, Michiyuki; Aya, Izuo; Inasaka, Fujio; Murata, Hiroyuki; Odano, Naoteru; Shiozaki, Koki

    1998-01-01

    A research project from 1995-1999 had a plan to make experimental studies on (1) safety of nuclear ship loaded with an integral ship propulsion reactor (2) effects of pulsating flow on the thermo-hydraulic characteristics of ship propulsion reactor and (3) thermo-hydraulic behaviors of the reactor container at the time of accident in a passively safe ship propulsion reactor. Development of a data base for ship propulsion reactor was attempted using previous experimental data on the thermo-hydraulic characteristics of the reactor in the institute in addition to the present results aiming to make general analytical evaluation for the safety of the engineering-simulation system for nuclear ship. A general data base was obtained by integrating the data list and the analytical program for static characteristics. A test equipment which allows to visualize the pulsating flow was produced and visualization experiments have started. (M.N.)

  1. TMI-2 Core Shipping Preparations

    International Nuclear Information System (INIS)

    Ball, L.J.; Barkanic, R.J.; Conaway, W.T. II; Schmoker, D. S.; Post, Roy G.

    1988-01-01

    Shipping the damaged core from the Unit 2 reactor of Three Mile Island Nuclear Power Station near Harrisburg, PA, to the Idaho National Engineering Laboratory near Idaho Falls, ID, required development and implementation of a completely new spent fuel transportation system. This paper describes of the equipment developed, the planning and activities used to implement the hard-ware-systems into the facilities, and the planning involved in making the rail shipments. It also includes a summary of recommendations resulting from this experience. (author)

  2. Crushing Strength of Ship Structures

    DEFF Research Database (Denmark)

    Cerup-Simonsen, Bo; Abramowicz, W.; Høstgaard-Brene, C.N.S.

    1999-01-01

    The crushing response of ship structures is of primary importance to the designers and practicing engineers concerned with accidental loading and accident reconstruction of marine vehicles. Ship to-ship collisions, ship-harbor infrastructure interaction or ship-offshore structure interaction are ...

  3. Open innovation and supply chain management in food machinery ...

    African Journals Online (AJOL)

    Open innovation and supply chain management in food machinery supply chain: a ... This paradigm describes a new approach to internal R&D management, which ... a picture of the adoption of open innovation in the food machinery industry.

  4. Shipping Information Pipeline

    DEFF Research Database (Denmark)

    Jensen, Thomas; Vatrapu, Ravi

    2015-01-01

    and national borders within international shipping which is a rather complex domain. The intellectual objective is to generate and evaluate the efficacy and effectiveness of design principles for inter-organizational information infrastructures in the international shipping domain that can have positive...

  5. Liner Shipping Fleet Repositioning

    DEFF Research Database (Denmark)

    Tierney, Kevin; Jensen, Rune Møller

    2011-01-01

    Liner shipping fleet repositioning consists of moving vessels between services in a liner ship- ping network in order to better orient the overall network to the world economy, and to ensure the proper maintenance of vessels. Thus, fleet repositioning involves sailing and loading activities subject...

  6. Effective and Safe Ships

    DEFF Research Database (Denmark)

    Pedersen, Preben Terndrup; Amdahl, Jørgen; Rutgersson, Olle

    1996-01-01

    A Joint Nordic Research project "Effecive and Safe Ships" is presented. The project is aiming to develop methods and tools for quantitative evaluation fo ship safety. This report is the report of the preliminary phase where the plan for the main project is developed. The objectives of the project...

  7. Shipping Information Pipeline

    DEFF Research Database (Denmark)

    Jensen, Thomas

    to creating a more efficient shipping industry, and a number of critical issues are identified. These include that shipments depend on shipping information, that shipments often are delayed due to issues with documentation, that EDI messages account for only a minor part of the needed information......This thesis applies theoretical perspectives from the Information Systems (IS) research field to propose how Information Technology (IT) can improve containerized shipping. This question is addressed by developing a set of design principles for an information infrastructure for sharing shipping...... information named the Shipping Information Pipeline (SIP). Review of the literature revealed that IS research prescribed a set of meta-design principles, including digitalization and digital collaboration by implementation of Inter-Organizational Systems based on Electronic Data Interchange (EDI) messages...

  8. The Autophagic Machinery in Enterovirus Infection.

    Science.gov (United States)

    Lai, Jeffrey K F; Sam, I-Ching; Chan, Yoke Fun

    2016-01-27

    The Enterovirus genus of the Picornaviridae family comprises many important human pathogens, including polioviruses, rhinovirus, enterovirus A71, and enterovirus D68. They cause a wide variety of diseases, ranging from mild to severe life-threatening diseases. Currently, no effective vaccine is available against enteroviruses except for poliovirus. Enteroviruses subvert the autophagic machinery to benefit their assembly, maturation, and exit from host. Some enteroviruses spread between cells via a process described as autophagosome-mediated exit without lysis (AWOL). The early and late phases of autophagy are regulated through various lipids and their metabolizing enzymes. Some of these lipids and enzymes are specifically regulated by enteroviruses. In the present review, we summarize the current understanding of the regulation of autophagic machinery by enteroviruses, and provide updates on recent developments in this field.

  9. 29 CFR 1910.215 - Abrasive wheel machinery.

    Science.gov (United States)

    2010-07-01

    ... be securely fastened to the spindle and the bearing surface shall run true. When more than one wheel... 29 Labor 5 2010-07-01 2010-07-01 false Abrasive wheel machinery. 1910.215 Section 1910.215 Labor... OCCUPATIONAL SAFETY AND HEALTH STANDARDS Machinery and Machine Guarding § 1910.215 Abrasive wheel machinery. (a...

  10. Machinery prognostics and prognosis oriented maintenance management

    CERN Document Server

    Yan, Jihong

    2014-01-01

    This book gives a complete presentatin of the basic essentials of machinery prognostics and prognosis oriented maintenance management, and takes a look at the cutting-edge discipline of intelligent failure prognosis technologies for condition-based maintenance.  Latest research results and application methods are introduced for signal processing, reliability moelling, deterioration evaluation, residual life prediction and maintenance-optimization as well as applications of these methods.

  11. Vibration analysis for trending ageing in rotating machinery

    International Nuclear Information System (INIS)

    Sinha, S.K.; Rama Rao, A.

    2006-01-01

    The need for condition monitoring system for important equipment and machinery is a growing requirement in every industry and more so in the nuclear power plants because of stringent safety requirements. This is largely because of the inherent benefit of being able to promote predictive maintenance practice rather than uneconomical preventive maintenance practice in the plant. Forerunner among the condition monitoring parameter is vibration signatures measured on a rotating machine. It is known that every moving element in a rotating machine generates vibration signal that is uniquely its own. Detection of such signals and monitoring the changing conditions in a machine through vibration analysis is a technique involving the knowledge of engineering art and the mathematical theory. This blend of sound engineering judgement and vibration data interpretation skill is in fact the basis of vibration diagnostic techniques. (author)

  12. Skoda Concern's cooperation with State Machinery Design Research Institute

    International Nuclear Information System (INIS)

    Valchar, J.; Kuhn, L.

    1988-01-01

    The main areas are presented of cooperation between the Skoda Plzen Concern and the State Machinery Design Research Institute in Prague-Bechovice. This is mainly the development of steam turbines, from 50 MW turbines to the present 1000 MW saturated steam turbines designed for nuclear power plants. Main attention is centred on conditions of the boiling crisis in the steam turbine circuit, and its consequences. This study is served by the experimental equipment of the institute and its computer. The cooperation of the two institutions in the field of testing and diagnostic equipment is centred on measuring natural oscillations of turbine blades, the diagnostics of vibrations of steam turbines, the measurement of the humidity of saturated steam, optical measurements of the parameters of saturated steam, ultrasound diagnostics and the measurement of turbine blade deformation caused by hydraulic effects. (Z.M.). 8 figs

  13. Machinery Vibration Monitoring Program at the Savannah River Site

    International Nuclear Information System (INIS)

    Potvin, M.M.

    1990-01-01

    The Reactor Maintenance's Machinery Vibration Monitoring Program (MVMP) plays an essential role in ensuring the safe operation of the three Production Reactors at the Westinghouse Savannah River Company (WRSC) Savannah River Site (SRS). This program has increased machinery availability and reduced maintenance cost by the early detection and determination of machinery problems. This paper presents the Reactor Maintenance's Machinery Vibration Monitoring Program, which has been documented based on Electric Power Research Institute's (EPRI) NP-5311, Utility Machinery Monitoring Guide, and some examples of the successes that it has enjoyed

  14. Hydrodynamics of Ship Propellers

    DEFF Research Database (Denmark)

    Breslin, John P.; Andersen, Poul

    This book deals with flows over propellers operating behind ships, and the hydrodynamic forces and moments which the propeller generates on the shaft and on the ship hull.The first part of the text is devoted to fundamentals of the flow about hydrofoil sections (with and without cavitation...... of an intermittently cavitating propeller in a wake and the pressures and forces it exerts on the shaft and on the ship hull is examined. A final chapter discusses the optimization of efficiency of compound propulsors. The authors have taken care to clearly describe physical concepts and mathematical steps. Appendices...

  15. Designing Adaptable Ships: Modularity and Flexibility in Future Ship Designs

    Science.gov (United States)

    2016-01-01

    with motors, belts, shafts , seals, valves, hose spindles , and switches. If ship installation is not installed, the system will be status quo. Ship...Impact: the current centrifugal purifiers (Alfa-Laval) have experienced frequent failures with motor, belts, shafts , seals, valves, hose spindles ... Designing Adaptable Ships Modularity and Flexibility in Future Ship Designs John F. Schank, Scott Savitz, Ken Munson, Brian Perkinson, James

  16. Optimization in liner shipping

    DEFF Research Database (Denmark)

    Brouer, Berit Dangaard; Karsten, Christian Vad; Pisinger, David

    2017-01-01

    Seaborne trade is the lynchpin in almost every international supply chain, and about 90% of non-bulk cargo worldwide is transported by container. In this survey we give an overview of data-driven optimization problems in liner shipping. Research in liner shipping is motivated by a need for handling...... still more complex decision problems, based on big data sets and going across several organizational entities. Moreover, liner shipping optimization problems are pushing the limits of optimization methods, creating a new breeding ground for advanced modelling and solution methods. Starting from liner...... shipping network design, we consider the problem of container routing and speed optimization. Next, we consider empty container repositioning and stowage planning as well as disruption management. In addition, the problem of bunker purchasing is considered in depth. In each section we give a clear problem...

  17. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    Fribourg, Ch.

    2002-01-01

    This paper takes the state of the art on ship propulsion reactors technology. The french research programs with the corresponding technological stakes, the reactors specifications and advantages are detailed. (A.L.B.)

  18. Ship construction and welding

    CERN Document Server

    Mandal, Nisith R

    2017-01-01

    This book addresses various aspects of ship construction, from ship types and construction materials, to welding technologies and accuracy control. The contents of the book are logically organized and divided into twenty-one chapters. The book covers structural arrangement with longitudinal and transverse framing systems based on the service load, and explains basic structural elements like hatch side girders, hatch end beams, stringers, etc. along with structural subassemblies like floors, bulkheads, inner bottom, decks and shells. It presents in detail double bottom construction, wing tanks & duct keels, fore & aft end structures, etc., together with necessary illustrations. The midship sections of various ship types are introduced, together with structural continuity and alignment in ship structures. With regard to construction materials, the book discusses steel, aluminum alloys and fiber reinforced composites. Various methods of steel material preparation are discussed, and plate cutting and form...

  19. Performance Monitoring of Ships

    DEFF Research Database (Denmark)

    Hansen, Søren Vinther

    is used as input to the system and by comparing model and ship behaviour, an index describing the ship’s performance is generated. The work in this thesis is based on data logged through the automation system on board a PostPanmax container ship where data have been logged through a year. A routine...... in the models have been identified. The models used in this work are based on empirical relations or based on regression analyses of model tests and full-scale trials. In order to achieve valid results the conditions where performance is estimated have to be inside the boundaries of the model. Filters have been......The purpose of the research project is to establish a reliable index in the performance evaluation of ships. During operation the ship will experience added resistance due to fouling of hull and propeller. The added resistance will lead to increased fuel consumption and thus increased emissions...

  20. Distributed propulsion for ships

    OpenAIRE

    Nylund, Vilde

    2017-01-01

    It is anticipated that using distributed electric propulsion (DEP) on conventional ships will increase the total propulsive efficiency. This is mainly due to two reasons; firstly, because the total propeller disk area can be increased. Secondly, because each propeller can be optimised for the local wake where it is operating. In this work, the benefits of using DEP has been investigated for a 14 000 TEU container ship. Based on a literary study of the present state of propeller modelling ...

  1. SHIPPING REQUESTS ON EDH

    CERN Multimedia

    Logistics Group

    2001-01-01

    Users are informed that as from 1 September 2001 all Shipping Requests must be made on EDH using the appropriate electronic form. The submission of user requests directly into EDH will help rationalise the activities of the Shipping Service (Import & Export), with requests being automatically forwarded to hierarchical supervisors thereby improving the processing speed and facilitating the follow-up. Thank you for your collaboration.

  2. Plastic Pollution from Ships

    OpenAIRE

    Čulin, Jelena; Bielić, Toni

    2016-01-01

    The environmental impact of shipping on marine environment includes discharge of garbage. Plastic litter is of particular concern due to abundance, resistance to degradation and detrimental effect on marine biota. According to recently published studies, a further research is required to assess human health risk. Monitoring data indicate that despite banning plastic disposal at sea, shipping is still a source of plastic pollution. Some of the measures to combat the problem are discussed.

  3. On the Global Ship Hull Bending Energy in Ship Collisions

    DEFF Research Database (Denmark)

    Pedersen, Preben Terndrup; Li, Y.

    2004-01-01

    During ship collisions part of the kinetic energy of the involved vessels prior to contact is absorbed as energy dissipated by crushing of the hull structures, by friction and by elastic energy. The purpose of this report is to present an estimate of the elastic energy that can be stored in elastic...... hull vibrations during a ship collision. When a ship side is strengthened in order to improve the crashworthiness it has been argued in the scientific literature that a non trivial part of the energy released for structural deformation during the collision can be absorbed as elastic energy in global...... ship hull vibrations, such that with strong ship sides less energy has to be spent in crushing of the striking ship bow and/or the struck ship side. In normal ship-ship collision analyses both the striking and struck ship are usually considered as rigid bodies where structural crushing is confined...

  4. Fluid machinery application, selection, and design

    CERN Document Server

    Wright, Terry

    2013-01-01

    Published nearly a decade ago, Fluid Machinery: Performance, Analysis, and Design quickly became popular with students, professors, and professionals because of its comprehensive and comprehensible introduction to the fluid mechanics of turbomachinery. Renamed to reflect its wider scope and reorganized content, this second edition provides a more logical flow of information that will enhance understanding. In particular, it presents a consistent notation within and across chapters, updating material when appropriate. Although the authors do account for the astounding growth in the field of com

  5. Analysis of electric machinery and drive systems

    CERN Document Server

    Krause, Paul C; Sudhoff, Scott D; Pekarek, Steven

    2013-01-01

    Introducing a new edition of the popular reference on machine analysis Now in a fully revised and expanded edition, this widely used reference on machine analysis boasts many changes designed to address the varied needs of engineers in the electric machinery, electric drives, and electric power industries. The authors draw on their own extensive research efforts, bringing all topics up to date and outlining a variety of new approaches they have developed over the past decade. Focusing on reference frame theory that has been at the core of this work since the first edition, th

  6. Electrification of agricultural machinery; Elektrifizierung von Landmaschinen

    Energy Technology Data Exchange (ETDEWEB)

    Goetz, Manuel; Grad, Karl; Weinmann, Olrik [ZF Friedrichshafen AG, Friedrichshafen (Germany)

    2012-10-15

    As early as 2009, ZF exhibited a generator system for agricultural machinery at Agritechnica under the name Terra+ which consisted of an electric motor in the transmission housing. As part of the ElecTra project, the company is now presenting its first tractor prototype with this generator system at Agritechnica 2011. The project involves combining the electrification of the tractor's auxiliary systems with electric drives for an attachment. The electrification of the implement was carried out in cooperation with Amazone, manufacturer of implements for the agricultural industry. (orig.)

  7. Study on safety of a nuclear ship having an integral marine water reactor. Intelligent information database program concerned with thermal-hydraulic characteristics

    International Nuclear Information System (INIS)

    Inasaka, Fujio; Nariai, Hideki; Kobayashi, Michiyuki; Murata, Hiroyuki; Aya, Izuo

    2001-01-01

    As a high economical marine reactor with sufficient safety functions, an integrated type marine water reactor has been considered most promising. At the National Maritime Research Institute, a series of the experimental studies on the thermal-hydraulic characteristics of an integrated/passive-safety type marine water reactor such as the flow boiling of a helical-coil type steam generator, natural circulation of primary water under a ship rolling motion and flashing-condensation oscillation phenomena in pool water has been conducted. This current study aims at making use of the safety analysis or evaluation of a future marine water reactor by developing an intelligent information database program concerned with the thermal-hydraulic characteristics of an integral/passive-safety reactor on the basis of the above-mentioned valuable experimental knowledge. Since the program was created as a Windows application using the Visual Basic, it is available to the public and can be easily installed in the operating system. Main functions of the program are as follows: (1) steady state flow boiling analysis and determination of stability limit for any helical-coil type once-through steam generator design. (2) analysis and comparison with the flow boiling data, (3) reference and graphic display of the experimental data, (4) indication of the knowledge information such as analysis method and results of the study. The program will be useful for the design of not only the future integrated type marine water reactor but also the small sized water reactor. (author)

  8. Outer Dynamics of Ship Collisions

    DEFF Research Database (Denmark)

    Pedersen, Preben Terndrup

    1996-01-01

    The purpose is to present analysis procedures for the motion of ships during ship-ship collisions and for ship collisions with offshore structures. The aim is to estimate that part of the lost kinetic energy which will have to be absorbed by rupture and plastic damage of the colliding structures....

  9. Outer Dynamics of Ship Collisions

    DEFF Research Database (Denmark)

    Pedersen, Preben Terndrup

    1996-01-01

    The purpose of these notes is to present analysis procedures for the motion of ships during ship-ship collisions and for ship collisons with offshore structures. The aim is to estimate that part of the lost kinetic energy which will have to be absorbed by rupture and plastic damage of the colliding...

  10. Concerning the order of the Ministry of Transport for the amendment to part of the Rules for the Vehicle Transportation of Nuclear Fuel, the Rules for Ship Transportation and Storage of Dangerous Objects, and the Rules for the Enforcement of the Aviation Act

    International Nuclear Information System (INIS)

    1989-01-01

    The Ministry of Transport is planning to make amendments to the Rules for the Vehicle Transportation of Nuclear Fuel, the Rules for Ship Transportation and Storage of Dangerous objects, and the Rules for the Enforcement of the Aviation Act, on the basis of results of a study carried out by the Working Group for the Protection of Nuclear Material, the Atomic Energy Commission of Japan. The planned amendments to the Rules for the Vehicle Transportation of Nuclear Fuel cover the locking and sealing of containers, the development of transportation plans, the arrangement and operations of responsible persons and guards for its transportation, and improvement in the communications and liaison system. The amendments to the Rules for Ship Transportation and Storage of Dangerous Objects are related to the range of nuclear fuel substances to be protected, the measures to be taken for their protection during transportation by ship, the approval by the Minister of Transport, and the notification to the Regional Maritime Safety Headquarters. The planned amendments to the Rules for the Enforcement of the Aviation Act cover the range of nuclear fuel substances to be protected, etc. (N.K.)

  11. The RNAi Inheritance Machinery of Caenorhabditis elegans.

    Science.gov (United States)

    Spracklin, George; Fields, Brandon; Wan, Gang; Becker, Diveena; Wallig, Ashley; Shukla, Aditi; Kennedy, Scott

    2017-07-01

    Gene silencing mediated by dsRNA (RNAi) can persist for multiple generations in Caenorhabditis elegans (termed RNAi inheritance). Here we describe the results of a forward genetic screen in C. elegans that has identified six factors required for RNAi inheritance: GLH-1/VASA, PUP-1/CDE-1, MORC-1, SET-32, and two novel nematode-specific factors that we term here (heritable RNAi defective) HRDE-2 and HRDE-4 The new RNAi inheritance factors exhibit mortal germline (Mrt) phenotypes, which we show is likely caused by epigenetic deregulation in germ cells. We also show that HRDE-2 contributes to RNAi inheritance by facilitating the binding of small RNAs to the inheritance Argonaute (Ago) HRDE-1 Together, our results identify additional components of the RNAi inheritance machinery whose conservation provides insights into the molecular mechanism of RNAi inheritance, further our understanding of how the RNAi inheritance machinery promotes germline immortality, and show that HRDE-2 couples the inheritance Ago HRDE-1 with the small RNAs it needs to direct RNAi inheritance and germline immortality. Copyright © 2017 by the Genetics Society of America.

  12. Availability analysis of selected mining machinery

    Directory of Open Access Journals (Sweden)

    Brodny Jarosław

    2017-06-01

    Full Text Available Underground extraction of coal is characterized by high variability of mining and geological conditions in which it is conducted. Despite ever more effective methods and tools, used to identify the factors influencing this process, mining machinery, used in mining underground, work in difficult and not always foreseeable conditions, which means that these machines should be very universal and reliable. Additionally, a big competition, occurring on the coal market, causes that it is necessary to take action in order to reduce the cost of its production, e.g. by increasing the efficiency of utilization machines. To meet this objective it should be pro-ceed with analysis presented in this paper. The analysis concerns to availability of utilization selected mining machinery, conducted using the model of OEE, which is a tool for quantitative estimate strategy TPM. In this article we considered the machines being part of the mechanized longwall complex and the basis of analysis was the data recording by the industrial automation system. Using this data set we evaluated the availability of studied machines and the structure of registered breaks in their work. The results should be an important source of information for maintenance staff and management of mining plants, needed to improve the economic efficiency of underground mining.

  13. Cell secretion machinery: Studies using the AFM

    International Nuclear Information System (INIS)

    Jena, Bhanu P.

    2006-01-01

    A new field in biology, 'nano-cell biology', has emerged from the successful use of force microscopy in understanding the structure and dynamics of cells and biomolecules, at nm resolution and in real time. Atomic force microscopy, in combination with conventional tools and approaches (electron microscopy, electrophysiology, X-ray diffraction, photon correlation spectroscopy, mass spectroscopy, biochemistry, and molecular biology), has revealed for the first time, the universal molecular machinery and mechanism of secretion in cells. Secretion occurs in all living cells and involves the delivery of intracellular products to the cell exterior. Secretory products are packaged and stored in membranous sacs or vesicles within the cell. When the cell needs to secrete these products, the secretory vesicles containing them, dock and fuse at plasma membrane-associated supramolecular structures called Porosome, to release their contents. Specialized cells for neurotransmission, enzyme secretion, or hormone release utilize a highly regulated secretory process. During secretion, swelling of secretory vesicles results in a build-up of intravesicular pressure, allowing expulsion of vesicular contents. The extent of vesicle swelling dictates the amount of vesicular contents expelled. The discovery of the porosome as the universal secretory machinery, its isolation, its structure and dynamics at nm resolution and in real time, its biochemical composition and functional reconstitution into artificial lipid membrane, have been determined. The molecular mechanism of secretory vesicle swelling, and the fusion of opposing bilayers, i.e., the fusion of secretory vesicle membrane at the base of the porosome membrane, has also been resolved

  14. Rotating Machinery Predictive Maintenance Through Expert System

    Directory of Open Access Journals (Sweden)

    M. Sarath Kumar

    2000-01-01

    Full Text Available Modern rotating machines such as turbomachines, either produce or absorb huge amount of power. Some of the common applications are: steam turbine-generator and gas turbine-compressor-generator trains produce power and machines, such as pumps, centrifugal compressors, motors, generators, machine tool spindles, etc., are being used in industrial applications. Condition-based maintenance of rotating machinery is a common practice where the machine's condition is monitored constantly, so that timely maintenance can be done. Since modern machines are complex and the amount of data to be interpreted is huge, we need precise and fast methods in order to arrive at the best recommendations to prevent catastrophic failure and to prolong the life of the equipment. In the present work using vibration characteristics of a rotor-bearing system, the condition of a rotating machinery (electrical rotor is predicted using an off-line expert system. The analysis of the problem is carried out in an Object Oriented Programming (OOP framework using the finite element method. The expert system which is also developed in an OOP paradigm gives the type of the malfunctions, suggestions and recommendations. The system is implemented in C++.

  15. Methodology and techniques of early detection anomalies 85Kr and 3H in near bottom layer of sea water by water infiltration in spent nuclear fuel in dumpsites of the ship and submarine reactors

    International Nuclear Information System (INIS)

    Soyfer, V.N.; Goryachev, V.A.; Andreev, D.V.; Barabanov, I.R.; Yanovich, E.A.

    2004-01-01

    Assessment of the future radioactive environmental contamination threat by releases from the dumped submarine and ship reactors with spent nuclear fuel (SNF) is a project goal. The methodology of search and detection of traces of noble gases ( 85 Kr, 222 Rn) and 3 H (which leaking the first from the SNF) on them plume on a bottom in dumpsites of ship nuclear reactors is advanced. Investigation of releases from the dumped ship reactors with SNF of icebreaker enin in Kara Sea is launched (September 2003). Research has multi-plane character: experiments with SNF, creation of techniques and expeditions. Preliminary observation of current field and hydrological characteristics in zone of marked dumpsites on the shelf has been fulfilled. For an estimation of a gas fission products release (including Kr-85) from the irradiated fuel during the corrosion in conditions a near-bottom layer of the sea in Arctic the special installation has been created in the RRC 'Kurchatov Institute' hot laboratory. Then the following experiment (modeling the conditions a near-bottom layer of the sea in Arctic) was made: First, samples of irradiated VVER-1000 type reactor fuel (UO 2 ) are loaded into capsules filled with pure sea water or sea water with the silt sampled in Kara Sea. The fuel samples have been selected due to similarity of its burnup level (62 MWd/kg) and other parameters to the one of icebreaker 'Lenin' reactor, that had been buried (1965) in Kara sea. The average sample activity was about 1 GBq for 137 Cs. Second, the capsules and the vacuum system are pumped out and checked on tightness by the helium leak tester. Then capsules are filled with the artificial gas mixture without traces of 85 Kr. Temperature of capsules are maintained in a range 0;1 deg C. Each 1-2 month gas samples are taken from the capsules into the previously pumped out flask, then capsules are refilled by the gas mixture. The measurements of 85 Kr concentration in the samples are carried out on low

  16. On the global ship hull bending energy in ship collisions

    DEFF Research Database (Denmark)

    Pedersen, Preben Terndrup; Li, Yujie

    2009-01-01

    During ship collisions part of the kinetic energy of the involved vessels immediately prior to contact is absorbed as energy dissipated by crushing of the hull structures, by friction and by elastic energy. The purpose of this report is to present an estimate of the elastic energy that can...... be stored in elastic hull vibrations during a ship collision. When a ship side is strengthened in order to improve the crashworthiness it has been argued in the scientific literature that a non-trivial part of the energy released for structural deformation during the collision can be absorbed as elastic...... energy in global ship hull vibrations, such that with strong ship sides less energy has to be spent in crushing of the striking ship bow and/or the struck ship side. In normal ship–ship collision analyses both the striking and struck ship are usually considered as rigid bodies where structural crushing...

  17. On Development of Agricultural Machinery Operating Service in Chongqing

    Institute of Scientific and Technical Information of China (English)

    Chongjing; TAN; Shi; YANG

    2015-01-01

    Development of agricultural machinery operating service in Chongqing takes on rapid increase in number of service organizations,diversified service methods,improvement in service level,and constant service income. However,there are some problems,including unreasonable composition and small scale of service organization,imbalanced development of four service methods,low service level,and low operating income of agricultural machinery households. To accelerate development of agricultural machinery operating service in Chongqing,it is recommended to take following measures: adjusting subsidy for purchase and operation of agricultural machinery; improving fiscal and taxation and financial system; speeding up infrastructure construction,establishing agricultural machinery information network,and improving organizational form and methods of agricultural machinery operating service.

  18. Ship operations report, 1973

    International Nuclear Information System (INIS)

    1973-01-01

    The NOAA Fleet Operations Report 1973 was developed to provide a summary of project accomplishments during calendar year 1973. The report was prepared from season, cruise and special reports submitted by ships of the fleet. Centralized management of the NOAA Fleet was finalized by changing the operational control of the National Marine Fisheries Service (NMFS) Ships DAVID STARR JORDAN (FRS 44), TOWNSEND CROMWELL (FRS 43) and MURRE II (FRV 63) from NMFS to the National Ocean Survey on July 1, 1973. Throughout the year, ships routinely collected and transmitted weather data. Similarly, as NOAA participants in the Integrated Global Ocean Station System (IGOSS) service program, XBT observations were taken and either radioed or submitted in log form via mail. In addition, particulate and radionuclide samples were taken in cooperation with the Atomic Energy Commission, sediment samples were obtained for the Smithsonian Institution and observations were made of marine mammals

  19. Ship operations report, 1975

    International Nuclear Information System (INIS)

    1976-01-01

    The NOAA Ship Operations Report 1975 was developed to provide a summary of projects undertaken during calendar year 1975. The report was prepared from season, cruise and special reports submitted by ships of the fleet. This report is promulgated for inhouse dissemination in the National Oceanic and Atmospheric Administration, for collaborating and interested agencies, and for use by members of the scientific community. Throughout the year, ships routinely collected and transmitted weather data. Similarly, as NOAA participants in the Integrated Global Ocean Station System (IGOSS) service program, XBT observations were taken and either radioed or submitted in log form via mail. In addition, particulate and radionuclide samples were taken in cooperation with the Atomic Energy Commission, sediment samples were obtained for the Smithsonian Institution and observations were made of marine mammals

  20. Internationalisation Within Liner Shipping

    DEFF Research Database (Denmark)

    Prockl, Günter; Kinra, Aseem; Kotzab, Herbert

    2018-01-01

    , the degree of internationalisation, measured on the basis of sea-oriented operations, differs from that measured according to land-oriented front-end marketing and sales activities. The purpose of this study is to further examine the internationalisation patterns of shipping lines. An examination...... of the front-end activities and the structures of leading container-shipping companies is conducted. The sales office networks of the sector’s 20 largest companies worldwide (by twenty-foot equivalent unit capacity) are analysed as key indicators. The numbers of sales offices are measured by analysing...... the websites of the sample (20 companies), as well as annual reports and other publicly available data sources. The findings show that not all shipping companies are international, by virtue of the industry. While it is difficult to observe differences in the overall patterns of the sales networks at a macro...

  1. SNF shipping cask shielding analysis

    International Nuclear Information System (INIS)

    Johnson, J.O.; Pace, J.V. III.

    1996-01-01

    The Waste Management and Remedial Action Division has planned a modification sequence for storage facility 7827 in the Solid Waste Storage Area (SWSA). The modification cycle is: (1) modify an empty caisson, (2) transfer the spent nuclear fuel (SNF) of an occupied caisson to a hot cell in building 3525 for inspection and possible repackaging, and (3) return the package to the modified caisson in the SWSA. Although the SNF to be moved is in the solid form, it has different levels of activity. Thus, the following 5 shipping casks will be available for the task: the Loop Transport Carrier, the In- Pile Loop LITR HB-2 Carrier, the 6.5-inch HRLEL Carrier, the HFIR Hot Scrap Carrier, and the 10-inch ORR Experiment Removal Shield Cask. This report describes the shielding tasks for the 5 casks: determination of shielding characteristics, any streaming avenues, estimation of thermal limits, and shielding calculational uncertainty for use in the transportation plan

  2. Shipping emissions in ports

    OpenAIRE

    Merk, Olaf

    2014-01-01

    Shipping emissions in ports are substantial, accounting for 18 million tonnes of CO2 emissions, 0.4 million tonnes of NOx, 0.2 million of SOx and 0.03 million tonnes of PM10 in 2011. Around 85% of emissions come from containerships and tankers. Containerships have short port stays, but high emissions during these stays. Most of CO2 emissions in ports from shipping are in Asia and Europe (58%), but this share is low compared to their share of port calls (70%). European ports have much less emi...

  3. Technical development of fluid machinery area

    International Nuclear Information System (INIS)

    Chung, Kyung Nam; Kim, Jin Young; Kim, Yang Ik

    2008-01-01

    In this paper, recent research activity of Hyundai Heavy Industries in the fluid machinery area is introduced. Technical development has been carried out in pumps, turbines, construction equipment, side thrusters, engine lubrication flow, etc. Here the technology of pumps and cooling of construction equipment will be dealt with. We have actively used computational fluid dynamics in the performance analysis of pump models and the design of new models of various industrial pumps or marine pumps. And a cooling analysis system composed of 3D flow analysis and 1D cooling analysis has been established, and applied to the design of cooling systems of new models of excavators and wheel loaders. The above mentioned technology is presented in details, and some future works are mentioned

  4. Utility machinery vibration monitoring guide: Final report

    International Nuclear Information System (INIS)

    Moore, T.T.; Thomas, C.C.

    1987-08-01

    Section I of this guide presents a methodology for developing machinery vibration monitoring programs specifically designed for application within the utility industry. The methodology is designed to enhance a monitoring program and can be used at the outset of program development or as a reference after programs have been started. Section I evaluates all aspects of the monitoring program, including Objectives and Goals, Information Type, Timing and Format, Data Analysis, Data Acquisition, Measurement and Transducer Selection, Personnel and Organization, Program Instrumentation, Program Costs, Program Justification, and Implementation of a Monitoring Program. The methodology is then applied to two host utility plants in Section II, which contains the monitoring programs developed by Gulf States Utilities and Philadelphia Electric Company using this guide. Section III contains the histories of several different types of existing utility monitoring programs. Some of the lessons learned, including the recommendations of these ''mature'' programs for persons starting new programs, are included

  5. Multiple Cylinder Free-Piston Stirling Machinery

    Science.gov (United States)

    Berchowitz, David M.; Kwon, Yong-Rak

    In order to improve the specific power of piston-cylinder type machinery, there is a point in capacity or power where an advantage accrues with increasing number of piston-cylinder assemblies. In the case of Stirling machinery where primary energy is transferred across the casing wall of the machine, this consideration is even more important. This is due primarily to the difference in scaling of basic power and the required heat transfer. Heat transfer is found to be progressively limited as the size of the machine increases. Multiple cylinder machines tend to preserve the surface area to volume ratio at more favorable levels. In addition, the spring effect of the working gas in the so-called alpha configuration is often sufficient to provide a high frequency resonance point that improves the specific power. There are a number of possible multiple cylinder configurations. The simplest is an opposed pair of piston-displacer machines (beta configuration). A three-cylinder machine requires stepped pistons to obtain proper volume phase relationships. Four to six cylinder configurations are also possible. A small demonstrator inline four cylinder alpha machine has been built to demonstrate both cooling operation and power generation. Data from this machine verifies theoretical expectations and is used to extrapolate the performance of future machines. Vibration levels are discussed and it is argued that some multiple cylinder machines have no linear component to the casing vibration but may have a nutating couple. Example applications are discussed ranging from general purpose coolers, computer cooling, exhaust heat power extraction and some high power engines.

  6. Mechanics of Ship Grounding

    DEFF Research Database (Denmark)

    Pedersen, Preben Terndrup

    1996-01-01

    In these notes first a simplified mathematical model is presented for analysis of ship hull loading due to grounding on relatively hard and plane sand, clay or rock sea bottoms. In a second section a more rational calculation model is described for the sea bed soil reaction forces on the sea bott...

  7. SHIPPING OF RADIOACTIVE ITEMS

    CERN Multimedia

    TIS/RP Group

    2001-01-01

    The TIS-RP group informs users that shipping of small radioactive items is normally guaranteed within 24 hours from the time the material is handed in at the TIS-RP service. This time is imposed by the necessary procedures (identification of the radionuclides, determination of dose rate and massive objects require a longer procedure and will therefore take longer.

  8. Ship Roll Motion Control

    DEFF Research Database (Denmark)

    Perez, Tristan; Blanke, Mogens

    2010-01-01

    . This tutorial paper presents an account of the development of various ship roll motion control systems and the challenges associated with their design. The paper discusses how to assess performance, the applicability of dierent models, and control methods that have been applied in the past....

  9. Ship Roll Damping Control

    DEFF Research Database (Denmark)

    Perez, Tristan; Blanke, Mogens

    2012-01-01

    limitations and large variations of the spectral characteristics of wave-induced roll motion. This tutorial paper presents an account of the development of various ship roll motion control systems together with the challenges associated with their design. It discusses the assessment of performance...

  10. Options of ship discharge

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-05-15

    Environmental performance is a key design consideration for manufacturers of bulk handling machines, not least ship unloaders, with features being introduced to minimise dust and noise pollution. The article reports on developments in grab unloaders, slewing grabcranes and mobile grabcranes by manufacturers such as Konecrane, EMS-Tech, Liebherr-Werk Nenzing and Gottwald. 2 photos.

  11. Hydroelastic Vibrations of Ships

    DEFF Research Database (Denmark)

    Jensen, Jørgen Juncher; Folsø, Rasmus

    2002-01-01

    A formula for the necessary hull girder bending stiffness required to avoid serious springing vibrations is derived. The expression takes into account the zero crossing period of the waves, the ship speed and main dimensions. For whipping vibrations the probability of exceedance for the combined...

  12. The Design of High Reliability Magnetic Bearing Systems for Helium Cooled Reactor Machinery

    International Nuclear Information System (INIS)

    Swann, M.; Davies, N.; Jayawant, R.; Leung, R.; Shultz, R.; Gao, R.; Guo, Z.

    2014-01-01

    The requirements for magnetic bearing equipped machinery used in high temperature, helium cooled, graphite moderated reactor applications present a set of design considerations that are unlike most other applications of magnetic bearing technology in large industrial rotating equipment, for example as used in the oil and gas or other power generation applications. In particular, the bearings are typically immersed directly in the process gas in order to take advantage of the design simplicity that comes about from the elimination of ancillary lubrication and cooling systems for bearings and seals. Such duty means that the bearings will usually see high temperatures and pressures in service and will also typically be subject to graphite particulate and attendant radioactive contamination over time. In addition, unlike most industrial applications, seismic loading events become of paramount importance for the magnetic bearings system, both for actuators and controls. The auxiliary bearing design requirements, in particular, become especially demanding when one considers that the whole mechanical structure of the magnetic bearing system is located inside an inaccessible pressure vessel that should be rarely, if ever, disassembled over the service life of the power plant. Lastly, many machinery designs for gas cooled nuclear power plants utilize vertical orientation. This circumstance presents its own unique requirements for the machinery dynamics and bearing loads. Based on the authors’ experience with machine design and supply on several helium cooled reactor projects including Ft. St. Vrain (US), GT-MHR (Russia), PBMR (South Africa), GTHTR (Japan), and most recently HTR-PM (China), this paper addresses many of the design considerations for such machinery and how the application of magnetic bearings directly affects machinery reliability and availability, operability, and maintainability. Remote inspection and diagnostics are a key focus of this paper. (author)

  13. Machinery failure analysis and troubleshooting practical machinery management for process plants

    CERN Document Server

    Bloch, Heinz P

    2012-01-01

    Solve the machinery failure problems costing you time and money with this classic, comprehensive guide to analysis and troubleshooting  Provides detailed, complete and accurate information on anticipating risk of component failure and avoiding equipment downtime Includes numerous photographs of failed parts to ensure you are familiar with the visual evidence you need to recognize Covers proven approaches to failure definition and offers failure identification and analysis methods that can be applied to virtually all problem situations Demonstr

  14. Classification of Ship Routing and Scheduling Problems in Liner Shipping

    DEFF Research Database (Denmark)

    Kjeldsen, Karina Hjortshøj

    2011-01-01

    This article provides a classification scheme for ship routing and scheduling problems in liner shipping in line with the current and future operational conditions of the liner shipping industry. Based on the classification, the literature is divided into groups whose main characteristics...

  15. Wallops Ship Surveillance System

    Science.gov (United States)

    Smith, Donna C.

    2011-01-01

    Approved as a Wallops control center backup system, the Wallops Ship Surveillance Software is a day-of-launch risk analysis tool for spaceport activities. The system calculates impact probabilities and displays ship locations relative to boundary lines. It enables rapid analysis of possible flight paths to preclude the need to cancel launches and allow execution of launches in a timely manner. Its design is based on low-cost, large-customer- base elements including personal computers, the Windows operating system, C/C++ object-oriented software, and network interfaces. In conformance with the NASA software safety standard, the system is designed to ensure that it does not falsely report a safe-for-launch condition. To improve the current ship surveillance method, the system is designed to prevent delay of launch under a safe-for-launch condition. A single workstation is designated the controller of the official ship information and the official risk analysis. Copies of this information are shared with other networked workstations. The program design is divided into five subsystems areas: 1. Communication Link -- threads that control the networking of workstations; 2. Contact List -- a thread that controls a list of protected item (ocean vessel) information; 3. Hazard List -- threads that control a list of hazardous item (debris) information and associated risk calculation information; 4. Display -- threads that control operator inputs and screen display outputs; and 5. Archive -- a thread that controls archive file read and write access. Currently, most of the hazard list thread and parts of other threads are being reused as part of a new ship surveillance system, under the SureTrak project.

  16. A Survey of Fish Production and Processing Machinery in Rivers ...

    African Journals Online (AJOL)

    Survey of fish production and processing machinery in Port Harcourt City Local Government Area of Rivers State, Nigeria was carried out to evaluate the followings: different machines used for fish production and processing, the most acceptable machine, effect of cost of machinery on the fish farmer, whether gender has ...

  17. Added masses of ship structures

    CERN Document Server

    Korotkin, Alexandr I

    2008-01-01

    This essentially self-contained reference book contains data on added masses of ships and various ship and marine engineering structures. Theoretical and experimental methods for determining added masses of these objects are described.

  18. Ship Observations - VOS and Navy

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Combination of Voluntary Observing Ship (VOS) and US Navy Ship weather observations. Obs generally taken 2-4 times daily at 00, 06, 12, and 18z.

  19. Trends of shipping markets development

    Directory of Open Access Journals (Sweden)

    Tomasz Nowosielski

    2012-06-01

    Full Text Available Shipping markets are dependent on international trade transactions that generate transport needs. These needs can dynamically change depending on global natural resources and commodity markets situation. The changes affecting shipping markets can also be caused by changes to the existing cargo flows and by establishing new ones in different geographies. It is anticipated that in the future shipping markets will change, visible by a decline in shipping in North America and Europe and an increase in Asia.

  20. High cost for drilling ships

    International Nuclear Information System (INIS)

    Hooghiemstra, J.

    2007-01-01

    Prices for the rent of a drilling ship are very high. Per day the rent is 1% of the price for building such a ship, and those prices have risen as well. Still, it is attractive for oil companies to rent a drilling ship [nl

  1. Vibration monitoring of EDF rotating machinery using artificial neural networks

    International Nuclear Information System (INIS)

    Alguindigue, I.E.; Loskiewicz-Buczak, A.; Uhrig, R.E.; Hamon, L.; Lefevre, F.

    1991-01-01

    Vibration monitoring of components in nuclear power plants has been used for a number of years. This technique involves the analysis of vibration data coming from vital components of the plant to detect features which reflect the operational state of machinery. The analysis leads to the identification of potential failures and their causes, and makes it possible to perform efficient preventive maintenance. Earlydetection is important because it can decrease the probability of catastrophic failures, reduce forced outgage, maximize utilization of available assets, increase the life of the plant, and reduce maintenance costs. This paper documents our work on the design of a vibration monitoring methodology based on neural network technology. This technology provides an attractive complement to traditional vibration analysis because of the potential of neural networks to operate in real-time mode and to handle data which may be distorted or noisy. Our efforts have been concentrated on the analysis and classification of vibration signatures collected by Electricite de France (EDF). Two neural networks algorithms were used in our project: the Recirculation algorithm and the Backpropagation algorithm. Although this project is in the early stages of development it indicates that neural networks may provide a viable methodology for monitoring and diagnostics of vibrating components. Our results are very encouraging

  2. Modelling and developing a decision-making process of hazard zone identification in ship power plants

    International Nuclear Information System (INIS)

    Podsiadlo, Antoni; Tarelko, Wieslaw

    2006-01-01

    The most dangerous places in ships are their power plants. Particularly, they are very unsafe for operators carried out various necessary operation and maintenance activities. For this reason, ship machinery should be designed to ensure the maximum safety for its operators. It is a very difficult task. Therefore, it could not be solved by means of conventional design methods, which are used for design of uncomplicated technical equipment. One of the possible ways of solving this problem is to provide appropriate tools, which allow us to take the operator's safety into account during a design process, especially at its early stages. A computer-aided system supporting design of safe ship power plants could be such a tool. This paper deals with developing process of a prototype of the computer-aided system for hazard zone identification in ship power plants

  3. Modelling and developing a decision-making process of hazard zone identification in ship power plants

    Energy Technology Data Exchange (ETDEWEB)

    Podsiadlo, Antoni [Department of Engineering Sciences, Gdynia Maritime University, ul. Morska 83, 81-225 Gdynia (Poland)]. E-mail: topo@am.gdynia.pl; Tarelko, Wieslaw [Department of Engineering Sciences, Gdynia Maritime University, ul. Morska 83, 81-225 Gdynia (Poland)]. E-mail: tar@am.gdynia.pl

    2006-04-15

    The most dangerous places in ships are their power plants. Particularly, they are very unsafe for operators carried out various necessary operation and maintenance activities. For this reason, ship machinery should be designed to ensure the maximum safety for its operators. It is a very difficult task. Therefore, it could not be solved by means of conventional design methods, which are used for design of uncomplicated technical equipment. One of the possible ways of solving this problem is to provide appropriate tools, which allow us to take the operator's safety into account during a design process, especially at its early stages. A computer-aided system supporting design of safe ship power plants could be such a tool. This paper deals with developing process of a prototype of the computer-aided system for hazard zone identification in ship power plants.

  4. Towards Real Time Simulation of Ship-Ship Interaction

    DEFF Research Database (Denmark)

    Lindberg, Ole; Bingham, Harry B.; Engsig-Karup, Allan Peter

    2012-01-01

    We present recent and preliminary work directed towards the development of a simplified, physics-based model for improved simulation of ship-ship interaction that can be used for both analysis and real-time computing (i.e. with real-time constraints due to visualization). The goal is to implement...... accurate (realistic) and much faster ship-wave and ship-ship simulations than are currently possible. The coupling of simulation with visualization should improve the visual experience such that it can be perceived as more realistic in training. Today the state-of-art in real-time ship-ship interaction...... is for efficiency reasons and time-constraints in visualization based on model experiments in towing tanks and precomputed force tables. We anticipate that the fast, and highly parallel, algorithm described by Engsig-Karup et al. [2011] for execution on affordable modern high-throughput Graphics Processing Units...

  5. Occupational Accidents with Agricultural Machinery in Austria.

    Science.gov (United States)

    Kogler, Robert; Quendler, Elisabeth; Boxberger, Josef

    2016-01-01

    The number of recognized accidents with fatalities during agricultural and forestry work, despite better technology and coordinated prevention and trainings, is still very high in Austria. The accident scenarios in which people are injured are very different on farms. The common causes of accidents in agriculture and forestry are the loss of control of machine, means of transport or handling equipment, hand-held tool, and object or animal, followed by slipping, stumbling and falling, breakage, bursting, splitting, slipping, fall, and collapse of material agent. In the literature, a number of studies of general (machine- and animal-related accidents) and specific (machine-related accidents) agricultural and forestry accident situations can be found that refer to different databases. From the database Data of the Austrian Workers Compensation Board (AUVA) about occupational accidents with different agricultural machinery over the period 2008-2010 in Austria, main characteristics of the accident, the victim, and the employer as well as variables on causes and circumstances by frequency and contexts of parameters were statistically analyzed by employing the chi-square test and odds ratio. The aim of the study was to determine the information content and quality of the European Statistics on Accidents at Work (ESAW) variables to evaluate safety gaps and risks as well as the accidental man-machine interaction.

  6. EMP coupling to ships

    International Nuclear Information System (INIS)

    Deadrick, F.J.; Cabayan, H.S.; Kunz, K.F.; Bevensee, R.M.; Martin, L.C.; Egbert, R.W.

    1980-01-01

    Scale-model tests were conducted to establish the adequacy and limitations of model measurements as tools for predicting electromagnetic pulse (EMP) coupling voltages and currents to the critical antennas, cables, and metallic structures on ships. The scale-model predictions are compared with the results of the full-scale EMP simulation test of the Canadian ASW ship, HMCS Huron. (The EMP coupling predictions in this report were made without prior knowledge of the results of the data from the HMCS Huron tests.) This report establishes that the scale-model tests in conjunction with the data base from EMP coupling modules provides the necessary information for source model development and permits effective, low-cost study of particular system configurations. 184 figures, 9 tables

  7. SHIPPING OF RADIOACTIVE ITEMS

    CERN Multimedia

    TIS/RP Group

    2001-01-01

    The TIS-RP group informs users that shipping of small radioactive items is normally guaranteed within 24 hours from the time the material is handed in at the TIS-RP service. This time is imposed by the necessary procedures (identification of the radionuclides, determination of dose rate, preparation of the package and related paperwork). Large and massive objects require a longer procedure and will therefore take longer.

  8. Ship and Shoot

    Science.gov (United States)

    Woods, Ron

    2012-01-01

    Ron Woods shared incredibly valuable insights gained during his 28 years at the Kennedy Space Center (KSC) packaging Flight Crew Equipment for shuttle and ISS missions. In particular, Woods shared anecdotes and photos from various processing events. The moral of these stories and the main focus of this discussion were the additional processing efforts and effects related to a "ship-and-shoot" philosophy toward flight hardware.

  9. Nuclear transport

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    During january and february 2003, a unique event concerning nuclear transport was reported and rated 1 on the INES scale. This event concerns the absence of a maintenance operation on a shipping cask. This shipping cask was used for several years for nuclear transport inside La-hague site before being re-assigned to transport on public thoroughfare. The re-assignment of the cask should have been preceded and conditioned by a maintenance operation whose purpose is to check the efficiency of its radiation shield. During this period 2 on-site inspections concerning the transport of nuclear materials were performed. (A.C.)

  10. Automation facilities for agricultural machinery control

    Directory of Open Access Journals (Sweden)

    A. Yu. Izmaylov

    2017-01-01

    Full Text Available The possibility of use of the automation equipment for agricultural machinery control is investigated. The authors proposed solutions on creation of the centralized unified automated information system for mobile aggregates management. In accordance with the modern requirements this system should be open, integrated into the general schema of agricultural enterprise control. Standard hardware, software and communicative features should be realized in tasks of monitoring and control. Therefore the schema should be get with use the unified modules and Russian standards. The complex multivariate unified automated control system for different objects of agricultural purpose based on block and modular creation should correspond to the following principles: high reliability, simplicity of service, low expenses in case of operation, the short payback period connected to increase in productivity, the reduced losses when harvesting, postharvest processing and storage, the improved energetic indices. Technological processes control in agricultural production is exercised generally with feedback. The example without feedback is program control by temperature in storage in case of the cooling mode. Feedback at technological processes control in agricultural production allows to optimally solve a problem of rational distribution of functions in man-distributed systems and forming the intelligent ergonomic interfaces, consistent with professional perceptions of decision-makers. The negative feedback created by the control unit allows to support automatically a quality index of technological process at the set level. The quantitative analysis of a production situation base itself upon deeply formalized basis of computer facilities that promotes making of the optimal solution. Information automated control system introduction increases labor productivity by 40 percent, reduces energetic costs by 25 percent. Improvement of quality of the executed technological

  11. Analysis of a ship-to-ship collision

    International Nuclear Information System (INIS)

    Porter, V.L.; Ammerman, D.J.

    1996-01-01

    Sandia National Laboratories is involved in a safety assessment for the shipment of radioactive material by sea. One part of this study is investigation of the consequences of ship-to-ship collisions. This paper describes two sets of finite element analyses performed to assess the structural response of a small freighter and the loading imparted to radioactive material (RAM) packages during several postulated collision scenarios with another ship. The first series of analyses was performed to evaluate the amount of penetration of the freighter hull by a striking ship of various masses and initial velocities. Although these analyses included a representation of a single RAM package, the package was not impacted during the collision so forces on the package could not be computed. Therefore, a second series of analyses incorporating a representation of a row of seven packages was performed to ensure direct package impact by the striking ship. Average forces on a package were evaluated for several initial velocities and masses of the striking ship. In addition to. providing insight to ship and package response during a few postulated ship collisions scenarios, these analyses will be used to benchmark simpler ship collision models used in probabilistic risk assessment analyses

  12. The kinematics of machinery outlines of a theory of machines

    CERN Document Server

    Reuleaux, Franz

    2012-01-01

    A classic on the kinematics of machinery, this volume was written by the Father of Kinematics. Reuleaux writes with authority and precision, developing the subject from its fundamentals. 450 figures. 1876 edition.

  13. Hospital Ship Replacement

    Science.gov (United States)

    2011-08-01

    serious contender. Although it is a proven hull design for stability, integrating the ability to quickly transfer patients aboard is challenging . The...Waste management afloat is a constant challenge for the Navy. It is even more so when designing a hospital ship. In addition to the typical waste...0.97 Optbrs: Corrmon rail fuellrijacllon,crude oil. Rated power generating sets 61:ili:ln()q;to~ 50Htl760rpm &.gne type -1801.\\ Vlc )l ~W.’/cyl SI;O k

  14. Targeting Cell Polarity Machinery to Exhaust Breast Cancer Stem Cells

    Science.gov (United States)

    2017-10-01

    AWARD NUMBER: W81XWH-15-1-0644 TITLE: Targeting Cell Polarity Machinery to Exhaust Breast Cancer Stem Cells PRINCIPAL INVESTIGATOR: Chun-Ju...Targeting Cell Polarity Machinery to Exhaust Breast Cancer Stem Cells 5a. CONTRACT NUMBER 5b. GRANT NUMBER W81XWH-15-1-0644 5c. PROGRAM ELEMENT...Unlimited 13. SUPPLEMENTARY NOTES 14. ABSTRACT Cancer stem cells (CSCs), a cell population with acquired perpetuating self-renewal properties which

  15. Intelligence and the machinery of government: conceptualizing the intelligence community

    OpenAIRE

    Davies, PHJ

    2010-01-01

    This article argues that the failure to address intelligence agencies as public organizations part and parcel with the overt machinery of government constitutes a significant lacuna both in the specialist study of intelligence and the broader discipline of public administration studies. The role and status of intelligence institutions as aspects of the machinery of central government is examined, along with the prospects of certain key paradigms in the field for understanding those institutio...

  16. Effects of ship motions on laminar flow in tubes

    Energy Technology Data Exchange (ETDEWEB)

    Yan, B.H., E-mail: yanbh1986@163.co [Department of Nuclear Science and Engineering, Naval University of Engineering, 717 Jiefang Street, Wuhan 430033 (China); Yu, L. [Department of Nuclear Science and Engineering, Naval University of Engineering, 717 Jiefang Street, Wuhan 430033 (China); Yang, Y.H. [School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 800 Dong Chuan Road, Shanghai 200240 (China)

    2010-01-15

    The thermal-hydraulics of barge-mounted floating nuclear desalination plants is the incentive for this study. Laminar flow in tubes in heaving motion is modeled. The friction factor and heat transfer coefficient are obtained. All the equations of laminar flow in steady state are applicable for heeling motion. The effect of ship motions on the laminar developing region is also analyzed. The ship motions can weaken the boundary layer in the laminar developing region and strengthen the laminar frictional resistance. The effect of ship motions on the instability of laminar flow is also investigated. The ship motions do not affect the instability point, but they can shorten the distance between the instability point and the transition point, and cause the transition from laminar flow to turbulent flow to occur earlier.

  17. Radiation leakage in nuclear ship 'MUTSU'

    International Nuclear Information System (INIS)

    Ando, Yoshio; Miyasaka, Shun-ichi; Takeuchi, Kiyoshi.

    1975-01-01

    Associated with the radiation leakage in MUTSU occurred in September 1974, this report reviews the shielding design for MUTSU, radiation measurement and inspection activities by a survey group, and 2 dimensional analysis on the behavior of fast neutrons to shielding based on Ssub(N) codes. In the first part, the purpose and the structure of the primary and the secondary shields of MUTSU are briefly illustrated. In the second part, the progress of the series of affairs is explained, starting from zero power criticality experiment, through discovery of radiation leakage in output-increasing test, sending of a survey group for various measurement and inspection, and finally to the conclusion drawn by the survey group. In the third part, various numerical analyses performed to investigate into the leakage are illustrated with their results. The transport codes used were ANISN, TWOTRAN, SPAN, and PALLAS-2DCY. As a result of those inspection and calculation, it was found that the radiation leakage was due to fast neutrons coming through the gap between the reactor vessel and the primary shield. (Aoki, K.)

  18. Ship Creek bioassessment investigations

    Energy Technology Data Exchange (ETDEWEB)

    Cushing, C.E.; Mueller, R.P.; Murphy, M.T.

    1995-06-01

    Pacific Northwest Laboratory (PNL) was asked by Elmendorf Air Force Base (EAFB) personnel to conduct a series of collections of macroinvertebrates and sediments from Ship Creek to (1) establish baseline data on these populations for reference in evaluating possible impacts from Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) activities at two operable units, (2) compare current population indices with those found by previous investigations in Ship Creek, and (3) determine baseline levels of concentrations of any contaminants in the sediments associated with the macroinvertebrates. A specific suite of indices established by the US Environmental Protection Agency (EPA) was requested for the macroinvertebrate analyses; these follow the Rapid Bioassessment Protocol developed by Plafkin et al. (1989) and will be described. Sediment sample analyses included a Microtox bioassay and chemical analysis for contaminants of concern. These analyses included, volatile organic compounds, total gasoline and diesel hydrocarbons (EPA method 8015, CA modified), total organic carbon, and an inductive-coupled plasma/mass spectrometry (ICP/MS) metals scan. Appendix A reports on the sediment analyses. The Work Plan is attached as Appendix B.

  19. ERDC Ship/Tow Simulator

    Data.gov (United States)

    Federal Laboratory Consortium — Performing Advanced Hydrodynamic ModelingEngineers and ship pilots can now overcome the challenges of evaluating navigation channel designs, modifications and safety...

  20. Using anti-corrosive paints on ships

    Energy Technology Data Exchange (ETDEWEB)

    Smith, J

    1969-02-07

    Anit-corrosive paints on the outside of ship's hulls fall into 3 groups: the area below the water, the boot- topping area at the waterline, and the weatherwork including the hull and superstructure. Typical formulations of primer and paint are given for use in each section. Anti-corrosion paints must always be considered in conjunction with the kind and amount of surface preparation that can be given. The requirement for faster descaling techniques and higher standards of surface preparation has led to the introduction of automated centrifugal abrasive blasting machines for all new plates and sections. If it is not possible to remove old coatings by abrasive blasting, then the traditional method of chipping followed by wire brushing must be used. The removal of mill scale by abrasive blasting can produce a clean metal surface which is liable to rapid corrosion unless it is painted immediately. A pre-fabrication or shop primer is used which is normally applied by airless spray equipment synchronized with the sand blasting machinery.

  1. Spent fuel shipping costs for transportation logistics analyses

    International Nuclear Information System (INIS)

    Cole, B.M.; Cross, R.E.; Cashwell, J.W.

    1983-05-01

    Logistics analyses supplied to the nuclear waste management programs of the U.S. Department of Energy through the Transportation Technology Center (TTC) at Sandia National Laboratories are used to predict nuclear waste material logistics, transportation packaging demands, shipping and receiving rates and transportation-related costs for alternative strategies. This study is an in-depth analysis of the problems and contingencies associated with the costs of shipping irradiated reactor fuel. These costs are extremely variable however, and have changed frequently (sometimes monthly) during the past few years due to changes in capital, fuel, and labor costs. All costs and charges reported in this study are based on January 1982 data using existing transport cask systems and should be used as relative indices only. Actual shipping costs would be negotiable for each origin-destination combination

  2. On Impact Mechanics in Ship Collisions

    DEFF Research Database (Denmark)

    Pedersen, Preben Terndrup; Zhang, Shengming

    1998-01-01

    The purpose of this paper is to present analytical, closed-form expressions for the energy released for crushing and the impact impulse during ship collisions. Ship-ship collisions, ship collisions with rigid walls and ship collisions with flexible offshore structures are considered. The derived ...

  3. Luggage and shipped goods

    International Nuclear Information System (INIS)

    Vogel, H.; Haller, D.

    2007-01-01

    Summary: Purpose: Control of luggage and shipped goods are frequently carried out. The possibilities of X-ray technology shall be demonstrated. Materials and methods: There are different imaging techniques. The main concepts are transmission imaging, backscatter imaging, computed tomography, and dual energy imaging and the combination of different methods The images come from manufacturers and personal collections. Results: The search concerns mainly, weapons, explosives, and drugs; furthermore animals, and stolen goods, Special problems offer the control of letters and the detection of Improvised Explosive Devices (IED). Conclusion: One has to expect that controls will increase and that imaging with X-rays will have their part. Pattern recognition software will be used for analysis enforced by economy and by demand for higher efficiency - man and computer will produce more security than man alone

  4. Global Shipping Game

    Science.gov (United States)

    2011-01-28

    information please contact the Chairman, War Gaming Department, Naval War College, 686 Cushing Road, Newport, RI 02841 or via electronic mail at... Game ……………………………………………...9 c. Overarching Research Question……………………………………………..…10 d. Subsidiary Questions…………………………………………………………...10 e ...An e -SLOC is the “cyber network that supports the global maritime trade network.” Industry Global Shipping Game Report 27 experts felt that

  5. Basic planning of a newly built exclusive ship for spent fuel transport

    International Nuclear Information System (INIS)

    Obara, I.; Sasao, T.; Akiyama, H.; Kybota, T.

    1998-01-01

    A commercial reprocessing plant is under construction at the Fuel Cycle Facilities in Rokkasho-mura, Aomori Prefecture. To prepare for the transport of spent nuclear fuels (SF) from all Japanese nuclear power stations to this reprocessing plant, the need for an exclusive transport ship was recognized. Nuclear Fuel Transport Co. Ltd. (NFT), in cooperation with electric power utilities planned the construction of such a ship over a period of several years. During this period NFT developed new types of cask to transport high burn-up spent fuels to the reprocessing plant. Six kinds of casks were developed and 40 units are now under fabrication. The ship was designed to carry a maximum of 20 units. Based on the Irradiated Nuclear Fuel (INF) Code adopted by the International Maritime Organization (IMO), the Japanese Ministry of Transport (MoT) issued new domestic regulations in September, 1995 which covered design criteria for ships carrying Irradiated Nuclear Fuels. The new SF transport ship is the first one to which this new regulation was applied. Although the ship will only ply the coastal routes of Japan, she has been designed to conform with all the international requirements for the Class-3 of the INF Code. In May 1995, Nuclear Fuel Shipping Co. Ltd (NFS), a wholly-owned subsidiary of NFT, concluded a contract with Mitsui Engineering and Shipbuilding Co., Ltd. for the construction of the exclusive transport ship. The keel was laid in November 1995. The ship was launched in april 1996 and named 'Rokuei-Maru'. At the end of September, she was completed and delivered to the ship owner, NFS. (authors)

  6. Advanced Demonstration of Motion Correction for Ship-to-Ship Passive Inspections

    Energy Technology Data Exchange (ETDEWEB)

    Ziock, Klaus-Peter [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Boehnen, Chris Bensing [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ernst, Joseph [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2013-09-30

    Passive radiation detection is a key tool for detecting illicit nuclear materials. In maritime applications it is most effective against small vessels where attenuation is of less concern. Passive imaging provides: discrimination between localized (threat) and distributed (non-threat) sources, removal of background fluctuations due to nearby shorelines and structures, source localization to an individual craft in crowded waters, and background subtracted spectra. Unfortunately, imaging methods cannot be easily applied in ship-to-ship inspections because relative motion of the vessels blurs the results over many pixels, significantly reducing sensitivity. This is particularly true for the smaller water craft where passive inspections are most valuable. In this project we performed tests and improved the performance of an instrument (developed earlier under, “Motion Correction for Ship-to-Ship Passive Inspections”) that uses automated tracking of a target vessel in visible-light images to generate a 3D radiation map of the target vessel from data obtained using a gamma-ray imager.

  7. Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory Foamglas Shipping Container

    International Nuclear Information System (INIS)

    Klima, B.B.; Shappert, L.B.; Seagren, R.D.; Box, W.D.

    1978-05-01

    An analytical evaluation of the Oak Ridge National Laboratory (ORNL) Foamglas Shipping Container was made to demonstrate its compliance with the regulations governing offsite radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the container complies with the applicable regulations

  8. Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory Foamglas Shipping Container

    International Nuclear Information System (INIS)

    Klima, B.B.; Shappert, L.B.; Seagren, R.D.; Box, W.D.

    1979-01-01

    An analytical evaluation of the ORNL Foamglas Shipping Container was made to demonstrate its compliance with the regulations governing offsite radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the container complies with the applicable regulations

  9. Single liner shipping service design

    DEFF Research Database (Denmark)

    Plum, Christian Edinger Munk; Pisinger, David; Salazar-González, Juan-José

    2014-01-01

    The design of container shipping networks is an important logistics problem, involving assets and operational costs measured in billions of dollars. To guide the optimal deployment of the ships, a single vessel round trip is considered by minimizing operational costs and flowing the best paying...

  10. Ship exhaust gas plume cooling

    NARCIS (Netherlands)

    Schleijpen, H.M.A.; Neele, P.P.

    2004-01-01

    The exhaust gas plume is an important and sometimes dominating contributor to the infrared signature of ships. Suppression of the infrared ship signatures has been studied by TNO for the Royal Netherlands Navy over considerable time. This study deals with the suppression effects, which can be

  11. Navy Hospital ships in history

    Directory of Open Access Journals (Sweden)

    Sougat Ray

    2017-01-01

    Full Text Available Hospital ships are operated by the Naval forces in or near war zones to provide medical assistance to the wounded personnel of all nationalities and not be used for any military purpose. Hospital ships possibly existed in ancient times and the Athenian Navy had a ship named Therapia. However, it was only during the 17th century that it became a common practice for the naval squadrons to be accompanied by large ships with the facilities of carrying the wounded after each engagement. In 1860, the steamships HMS Melbourne and HMS Mauritius were equipped with genuine medical facilities. They were manned by the Medical Staff Corps and provided services to the British expedition to China. During the World War I and World War II, passenger ships were converted for use as hospital ships and were started to be used on a massive scale. RMS Aquitania and HMHS Britannic were two famous examples of hospital ships used extensively. Modern US hospital ships USNS Mercy and USNS Comfort are operated by Military Sealift Command of the US Navy. Their primary mission is to provide emergency on-site care for US combatant forces deployed in war or other operations.

  12. Identification of Dynamically Positioned Ships

    Directory of Open Access Journals (Sweden)

    Thor I. Fossen

    1996-04-01

    Full Text Available Todays model-based dynamic positioning (DP systems require that the ship and thruster dynamics are known with some accuracy in order to use linear quadratic optical control theory. However, it is difficult to identify the mathematical model of a dynamically posititmed (DP ship since the ship is not persistently excited under DP. In addition the ship parameter estimation problem is nonlinear and multivariable with only position and thruster state measurements available for parameter estimation. The process and measurement noise must also be modeled in order to avoid parameter drift due to environmental disturbances and sensor failure. This article discusses an off-line parallel extended Kalman filter (EKF algorithm utilizing two measurement series in parallel to estimate the parameters in the DP ship model. Full-scale experiments with a supply vessel are used to demonstrate the convergence and robustness of the proposed parameter estimator.

  13. Quality assurance program description for shipping packages of radioactive material

    International Nuclear Information System (INIS)

    1978-01-01

    This quality assurance plan describes the quality assurance program at the Pacific Northwest Laboratory (PNL), for shipping packages of radioactive material. The purpose of this report is to describe how PNL will comply with the Code of Federal Regulations, Title 10, Part 71, Appendix E. In compliance with the instructions from the Nuclear Regulatory Commission (NRC), the 18 criteria from Appendix E are covered

  14. Losses in German nuclear power plants

    International Nuclear Information System (INIS)

    Abinger, R.

    1982-01-01

    The author illustrates the special features of engineering insurance for nuclear power plants. The shares of the Allianz Versicherungs-AG in the insurance of construction and erection work and in machinery insurance are dealt with. Risk estimation is usually based on statistical analysis of losses. Loss analysis in the conventional sector of nuclear power plants shows typical characteristics of traditional erection and machinery losses. In the nuclear field, however, costs are greatly increased by added safety measures. For this reason, additional cover is allocated and incorporated in premium assessment. Examples from erection and machinery reveal the greater costs involved in handling losses. (orig.) [de

  15. FOREWORD: 26th IAHR Symposium on Hydraulic Machinery and Systems

    Science.gov (United States)

    Wu, Yulin; Wang, Zhengwei; Liu, Shuhong; Yuan, Shouqi; Luo, Xingqi; Wang, Fujun

    2012-11-01

    The 26th IAHR Symposium on Hydraulic Machinery and Systems, will be held in Beijing, China, 19-23 August 2012. It is jointly organized by Tsinghua University, State Key Laboratory of Hydro Science and Hydraulic Engineering, China, Jiangsu University, Xi'an University of Technology, China Agricultural University, National Engineering Research Center of Hydropower Equipment and Dongfang Electric Machinery Co., Ltd. It is the second time that China hosts such a symposium. By the end of 2011, the China electrical power system had a total of 1 050 GW installed power, out of which 220 GW was in hydropower plants. The energy produced in hydropower facilities was 662.6 TWh from a total of 4,720 TWh electrical energy production in 2011. Moreover, in 2020, new hydropower capacities are going to be developed, with a total of 180 GW installed power and an estimated 708 TWh/year energy production. And in 2011, the installed power of pumped storage stations was about 25GW. In 2020, the data will be 70GW. At the same time, the number of pumps used in China is increasing rapidly. China produces about 29,000,000 pumps with more than 220 series per year. By the end of 2011, the Chinese pumping system has a total of 950 GW installed power. The energy consumed in pumping facilities was 530 TWh in 2011. The pump energy consumption accounted for about 12% of the national electrical energy production. Therefore, there is a large market in the field of hydraulic machinery including water turbines, pump turbines and a variety of pumps in China. There are also many research projects in this field. For example, we have conducted National Key Research Projects on 1000 MW hydraulic turbine, and on the pump turbines with high head, as well as on the large capacity pumps for water supply. Tsinghua University of Beijing is proud to host the 26th IAHR Symposium on Hydraulic Machinery and Systems. Tsinghua University was established in 1911, after the founding of the People's Republic of China. It

  16. Cybersecurity Framework for Ship Industrial Control System

    OpenAIRE

    Maule, R. William; Hake, Joseph

    2016-01-01

    Ship mechanical and electrical control systems, and the communications grid through which these devices operate, are a high priority concern for Navy leadership. Ship systems use microprocessor-based controls to interface with physical objects, and Programmable Logic Controllers (PLCs) to automate ship electromechanical processes. Ship operations are completely dependent on these devices. The commercial security products upon which ships depend do not work on ICS, leaving ships vulnerable. Th...

  17. Multiscale singular value manifold for rotating machinery fault diagnosis

    Energy Technology Data Exchange (ETDEWEB)

    Feng, Yi; Lu, BaoChun; Zhang, Deng Feng [School of Mechanical Engineering, Nanjing University of Science and Technology,Nanjing (United States)

    2017-01-15

    Time-frequency distribution of vibration signal can be considered as an image that contains more information than signal in time domain. Manifold learning is a novel theory for image recognition that can be also applied to rotating machinery fault pattern recognition based on time-frequency distributions. However, the vibration signal of rotating machinery in fault condition contains cyclical transient impulses with different phrases which are detrimental to image recognition for time-frequency distribution. To eliminate the effects of phase differences and extract the inherent features of time-frequency distributions, a multiscale singular value manifold method is proposed. The obtained low-dimensional multiscale singular value manifold features can reveal the differences of different fault patterns and they are applicable to classification and diagnosis. Experimental verification proves that the performance of the proposed method is superior in rotating machinery fault diagnosis.

  18. Radiological consequences of ship collisions that might occur in U.S. Ports during the shipment of foreign research reactor spent nuclear fuel to the United States in break-bulk freighters

    International Nuclear Information System (INIS)

    Sprung, J.L.; Bespalko, S.J.; Massey, C.D.; Yoshimura, R.; Johnson, J.D.; Reardon, P.C.; Ebert, M.W.; Gallagher D.W.

    1996-08-01

    Accident source terms, source term probabilities, consequences, and risks are developed for ship collisions that might occur in U.S. ports during the shipment of spent fuel from foreign research reactors to the United States in break-bulk freighters

  19. Containment of spills from ships

    International Nuclear Information System (INIS)

    Engerer, M.J.

    1992-01-01

    Oil escaping from a ship is contained within a limited area surrounding the ship by means of a flexible ring structure. The ring structure is stored in a collapsed state in a compartment extending around the ship. In response to an oil spill, the ring structure is dropped from the compartment and immediately surrounds the ship. A circular inflatable flotation section of the ring structure is charged with gas under pressure. The gas is supplied from a bottle cascade aboard the ship, through lines preconnected to the flotation section and paid out from free-wheeling reels. The flotation section supports a thin circumferential wall of predetermined height that submerges and assumes a vertical cylinder-like shape surrounding the escaping oil. The oil floats within the confines of the ring structure, and the ring structure is progressively expanded to a predetermined size selected to accommodate the total volume of oil carried by the ship. When the ring structure achieves its expanded state, pressure in the flotation section is raised to render the structure relatively rigid and resistant to collapse in response to wave action. Oil can be removed from the interior of the ring structure by recovery ships using suction lines or other conventional recovery methods. 12 figs

  20. Ships and the Sailors Inside Them

    National Research Council Canada - National Science Library

    Sims, Philip

    2004-01-01

    .... Iron shipbuilding allowed safer and healthier ships but their internal compartmentation created communication problems which were gradually solved with mechanical systems Ships developed their own...

  1. Structural insights into the bacterial carbon - phosphorus lyase machinery

    DEFF Research Database (Denmark)

    Seweryn, Paulina; Van, Lan Bich; Kjeldgaard, Morten

    2015-01-01

    Phosphorus is required for all life and microorganisms can extract it from their environment through several metabolic pathways. When phosphate is in limited supply, some bacteria are able to use phosphonate compounds, which require specialized enzymatic machinery to break the stable carbon......–phosphorus (C–P) bond. Despite its importance, the details of how this machinery catabolizes phosphonates remain unknown. Here we determine the crystal structure of the 240-kilodalton Escherichia coli C–P lyase core complex (PhnG–PhnH–PhnI–PhnJ; PhnGHIJ), and show that it is a two-fold symmetric hetero...

  2. Densification of chipper harvested SRC using on-farm machinery

    Energy Technology Data Exchange (ETDEWEB)

    Paulson, M.

    2003-07-01

    This report gives details of a project to density wood chips using on-farm machinery in order to avoid problems encountered in bulk handling and storage of low density short rotation cultivation (SRC) wood chips - especially as some customers can only accept baled material. Trials using different lengths of chips produced by a standard SRC harvester are described, and the failure to produce acceptable bales is reported. The potential cost of modifying equipment is deemed to make the baling of SRC chips using standard farm machinery currently not viable.

  3. Bio-indications of sunken ships and ship wrecks

    Digital Repository Service at National Institute of Oceanography (India)

    Parulekar, A

    An evaluation of bottom fauna of ship-wreck sites in estuarine and coastal waters of Goa, India, revealed an exceptionally high biotic enrichment. In terms of number of species, faunal dispersion, faunal diversity, biomass and productivity, in space...

  4. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  5. Investigation into the feasibility of alternative plutonium shipping forms

    International Nuclear Information System (INIS)

    Mishima, J.; Lindsey, C.G.

    1983-06-01

    Pacific Northwest Laboratory (PNL), operated for the Department of Energy by the Battelle Memorial Institute, is conducting a study for the Nuclear Regulatory Commission on the feasibility of altering current plutonium shipping forms to reduce or eliminate the airborne dispersibility of PuO 2 which might occur during a shipping accident. Plutonium used for fuel fabrication is currently shipped as a PuO 2 powder with a significant fraction in the respirable size range. If the high-strength container is breached due to stresses imposed during a transportation accident, the PuO 2 powder could be subject to airborne dispersion. The available information indicated that a potential accident involving fire accompanied by crush/impact forces would lead to failure of current surface shipping containers (no assumptions were made on the possibility of such a severe accident). Criteria were defined for an alternate shipping form to mitigate the effects of such an accident. Candidate techniques and materials were evaluated as alternate shipping forms by a task team consisting of personnel from PNL and Rockwell Hanford Operations (RHO). At this time, the most promising candidate for an alternate plutonium shipping form appears to be pressing PuO 2 into unsintered (green) pellets. These green pellets satisfy the criteria for a less dispersible form without requiring significant process changes. Discussions of all candidates considered are contained in a series of appendices. Recommendations for further investigations of the applicability of green pellets as an alternate shipping form are given, including the need for a cost-benefit study

  6. Neutrino physics with SHIP

    CERN Document Server

    van Herwijnen, Eric

    2016-01-01

    SHIP is a new general purpose fixed target facility, whose Technical Proposal has been recently reviewed by the CERN SPS Committee. It recommended that the experiment proceed further to a Comprehensive Design phase. In its initial phase, the 400 GeV proton beam extracted from the SPS will be dumped on a heavy target with the aim of integrating 2×1020 POT (Protons On Target) in 5 years. A dedicated detector, based on a long vacuum tank followed by a spectrometer and particle identification detectors, will allow probing a variety of models with light long-lived exotic particles and masses below O(10) GeV/c 2 . The main focus will be the physics of the so-called Hidden Portals. The sensitivity to Heavy Neutrinos will allow to probe for the first time the mass range between the kaon and the charm meson mass, and a range of couplings for which Baryogenesis and active neutrino masses could also be explained. Another dedicated detector will allow the study of neutrino cross-sections and angular distributions. ντ ...

  7. Production Balance of Ship Erection

    Institute of Scientific and Technical Information of China (English)

    JIANG Ru-hong; TAN Jia-hua; LIU Cun-gen

    2008-01-01

    A network plan model of ship erection was established based on the network planning technologyand the work-package breakdown system. The load-oriented production control method was introduced to buildup a throughput diagram model thus it is possible to describe the ship erection process numerically. Based onthe digitaiized models some cases of production balance of ship erection were studied and three balance indexeswere put forward, they are the load balance rate, the input manpower balance rate and the maximum gantrycrane operating times. Such an analytic method based on the balance evaluation is the important foundationfor digitization and intelligentization of shipyard production management.

  8. Civil ships propulsion reactor plants development and operation experience, and prospects for their improvement

    International Nuclear Information System (INIS)

    Vasyukov, V.I.; Kiryushin, A.I.; Panov, Yu.K.; Polunichev, V.I.

    2000-01-01

    Russia is alone country in the World possessing nuclear-powered icebreaker fleet. Phases of creation in Russia of several propulsion nuclear reactor plant generations are considered. By present 8 nuclear ice-breakers and a nuclear-powered cargo ship (lighter carrier) have been constructed, for which three of propulsion NSSS generations were developed. Their brief description, main performance indicators and results of operation since 1959 are given. It is shown that gradual evolution of NSSS design features has ensured creation of reliable, safe and environmentally friendly propulsion reactor plants. Issues of the propulsion NSSS life extension and improvement for new generation of nuclear ice-breakers, cargo ships, floating heat and power plants, sea water desalination and power generating complexes are considered with account for the gained operating experience. Activities on creation of new generation nuclear-powered ships and floating NPPs are considered as prospective sphere of Russia's collaboration with other countries of the World community. (author)

  9. Ship Engine Room Casualty Analysis by Using Decision Tree Method

    Directory of Open Access Journals (Sweden)

    Ömür Yaşar SAATÇİOĞLU

    2017-03-01

    Full Text Available Ships may encounter undesirable conditions during operations. In consequence of a casualty, fire, explosion, flooding, grounding, injury even death may occur. Besides, these results can be avoidable with precautions and preventive operating processes. In maritime transportation, casualties depend on various factors. These were listed as misuse of the engine equipment and tools, defective machinery or equipment, inadequacy of operational procedure and measure of safety and force majeure effects. Casualty reports which were published in Australia, New Zealand, United Kingdom, Canada and United States until 2015 were examined and the probable causes and consequences of casualties were determined with their occurrence percentages. In this study, 89 marine investigation reports regarding engine room casualties were analyzed. Casualty factors were analyzed with their frequency percentages and also their main causes were constructed. This study aims to investigate engine room based casualties, frequency of each casualty type and main causes by using decision tree method.

  10. Ship Effect Measurements With Fiber Optic Neutron Detector

    International Nuclear Information System (INIS)

    King, Kenneth L.; Dean, Rashe A.; Akbar, Shahzad; Kouzes, Richard T.; Woodring, Mitchell L.

    2010-01-01

    The main objectives of this research project was to assemble, operate, test and characterize an innovatively designed scintillating fiber optic neutron radiation detector manufactured by Innovative American Technology with possible application to the Department of Homeland Security screening for potential radiological and nuclear threats at US borders (Kouzes 2004). One goal of this project was to make measurements of the neutron ship effect for several materials. The Virginia State University DOE FaST/NSF summer student-faculty team made measurements with the fiber optic radiation detector at PNNL above ground to characterize the ship effect from cosmic neutrons, and underground to characterize the muon contribution.

  11. Reconstruction calculation of pin power for ship reactor core

    International Nuclear Information System (INIS)

    Li Haofeng; Shang Xueli; Chen Wenzhen; Wang Qiao

    2010-01-01

    Aiming at the limitation of the software that pin power distribution for ship reactor core was unavailable, the calculation model and method of the axial and radial pin power distribution were proposed. Reconstruction calculations of pin power along axis and radius was carried out by bicubic and bilinear interpolation and cubic spline interpolation, respectively. The results were compared with those obtained by professional reactor physical soft with fine mesh difference. It is shown that our reconstruction calculation of pin power is simple and reliable as well as accurate, which provides an important theoretic base for the safety analysis and operating administration of the ship nuclear reactor. (authors)

  12. Automated Detection of Anomalous Shipping Manifests to Identify Illicit Trade

    Energy Technology Data Exchange (ETDEWEB)

    Sanfilippo, Antonio P.; Chikkagoudar, Satish

    2013-11-12

    We describe an approach to analyzing trade data which uses clustering to detect similarities across shipping manifest records, classification to evaluate clustering results and categorize new unseen shipping data records, and visual analytics to provide to support situation awareness in dynamic decision making to monitor and warn against the movement of radiological threat materials through search, analysis and forecasting capabilities. The evaluation of clustering results through classification and systematic inspection of the clusters show the clusters have strong semantic cohesion and offer novel ways to detect transactions related to nuclear smuggling.

  13. Occupational accidents aboard merchant ships

    DEFF Research Database (Denmark)

    Hansen, H.L.; Nielsen, D.; Frydenberg, Morten

    2002-01-01

    Objectives: To investigate the frequency, circumstances, and causes of occupational accidents aboard merchant ships in international trade, and to identify risk factors for the occurrence of occupational accidents as well as dangerous working situations where possible preventive measures may...... be initiated. Methods: The study is a historical follow up on occupational accidents among crew aboard Danish merchant ships in the period 1993–7. Data were extracted from the Danish Maritime Authority and insurance data. Exact data on time at risk were available. Results: A total of 1993 accidents were...... aboard. Relative risks for notified accidents and accidents causing permanent disability of 5% or more were calculated in a multivariate analysis including ship type, occupation, age, time on board, change of ship since last employment period, and nationality. Foreigners had a considerably lower recorded...

  14. Travelers' Health: Cruise Ship Travel

    Science.gov (United States)

    ... and territories). Zika virus was first reported in Brazil in 2015 and subsequently spread across the Caribbean ... 11. Mouchtouri VA, Rudge JW. Legionnaires’ disease in hotels and passenger ships: a systematic review of evidence, ...

  15. Ship Repair Workflow Cost Model

    National Research Council Canada - National Science Library

    McDevitt, Mike

    2003-01-01

    The effects of intermittent work patterns and funding on the costs of ship repair and maintenance were modeled for the San Diego region in 2002 for Supervisor of Shipbuilding and Repair (SUPSHIP) San Diego...

  16. TMI-2 spent fuel shipping

    International Nuclear Information System (INIS)

    Quinn, G.J.; Burton, H.M.

    1985-01-01

    TMI-2 failed fuel will be shipped to the Idaho National Engineering Laboratory for use in the DOE Core Examination Program. The fuel debris will be loaded into three types of canisters during defueling and dry loaded into a spent fuel shipping cask. The cask design accommodates seven canisters per cask and has two separate containment vessels with ''leaktight'' seals. Shipments are expectd to begin in early 1986

  17. Implications of material selection on the design of packaging machinery.

    Science.gov (United States)

    Merritt, J P

    2009-01-01

    Material selection has significant implications on the design and cost of horizontal-form-fill-seal packaging machinery. To avoid excessive costs, machine redesigns and project delays, material selection must be reconciled early in the project and revisited throughout the construction of the machine.

  18. The Machinery for Enforcement of Domestic Arbitral Awards in Nigeria

    African Journals Online (AJOL)

    Nnamdi Azikiwe University Journal of International Law and Jurisprudence ... Arbitration is a private means of resolving dispute which is resorted to, chiefly because the parties choose to avoid as much as possible employing the state machinery for dispute resolution, namely the court and its dreaded time consuming ...

  19. The capacity of sugar beet farms’ machinery and equipment

    Directory of Open Access Journals (Sweden)

    Małgorzata BZOWSKA – BAKALARZ

    2012-12-01

    Full Text Available The survey investigates into equipment of sugar beet farms of the Lublin region, Poland, with machinery – with reference to plantation size and yields. To assess the production potential of the farms, the authors determined the age structure of the machinery owned by the farmers and established the scale of investment in new equipment. The machinery most important for sugar beet production are pre-sowing and post-harvest tillage units, sprayers, seed drills, combine harvesters and self-unloading trailers. In most cases, the surveyed farmers own most of these machines, but they are often obsolete: 37% of them is in operation for more than 15 years. As for the machines dedicated solely to sugar beet growing (harvesters and seeders, their age structure is most unfavourable – 70% of them have been used for over 15 years. A trend towards increasing plantation sizes provides incentives for introducing innovation to cultivation methods. However, the scale of investment in new machinery is small, especially in the case of small and medium-sized farms that dominate in the region. The authors surveyed also the scale of using professional services in the field of tillage processes to determine changes in farming practices.

  20. Web-based Interactive Simulator for Rotating Machinery.

    Science.gov (United States)

    Sirohi, Vijayalaxmi

    1999-01-01

    Baroma (Balance of Rotating Machinery), the Web-based educational engineering interactive software for teaching/learning combines didactical and software ergonomical approaches. The software in tutorial form simulates a problem using Visual Interactive Simulation in graphic display, and animation is brought about through graphical user interface…

  1. On impact mechanics in ship collisions

    DEFF Research Database (Denmark)

    Pedersen, Preben Terndrup; Zhang, Shengming

    1998-01-01

    The purpose of this paper is to present analytical, closed-form expressions for the energy released for crushing and the impact impulse during ship collisions. Ship–ship collisions, ship collisions with rigid walls and ship collisions with flexible offshore structures are considered. The derived ...

  2. Spectroscopy of transfermium isotopes at SHIP

    Energy Technology Data Exchange (ETDEWEB)

    Antalic, Stanislav; Saro, Stefan; Venhart, Martin [Comenius University, Bratislava (Slovakia); Hessberger, Fritz Peter; Ackermann, Dieter; Heinz, Sophia; Kindler, Birgit; Kojouharov, Ivan; Lommel, Bettina; Mann, Rido; Streicher, Branislav [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, Darmstadt (Germany); Hofmann, Sigurd [GSI Helmholtzzentrum fuer Schwerionenforschung GmbH, Darmstadt (Germany); Goethe-Universitaet, Frankfurt am Main (Germany); Sulignano, Barbara [CEA-Saclay, DAPNIA/SPhN, Gif-sur-Yvette (France)

    2009-07-01

    Recent developments of experimental techniques suited for {alpha}-, {gamma}- and CE spectroscopy now allow to study nuclear structure in the region of trans-fermium nuclei. This opened the door to investigate nuclear structure under extreme conditions of heaviest nuclei (Z>100,A>250). Most interesting examples are studies of K-isomers. Experiments aimed to investigate such phenomena provide important information on the nuclear structure of the heaviest elements and are stringent tests for the quality of nuclear models. In this contribution the results from studies of multi-quasi-particle isomeric states in {sup 253}No and {sup 255}Lr performed at SHIP are presented in detail. Both nuclei are first odd-mass isotopes in the trans-fermium region for which high K-isomers were observed. By decay of the high K-isomer in {sup 253}No a rotational band was populated, which was not seen in previous in-beam studies. Additionally, also the recent results on the single particle level systematics for the N=149, 151 and 153 isotones are presented.

  3. Spent fuel shipping cask development status

    International Nuclear Information System (INIS)

    Henry, K.H.; Lattin, W.C.

    1989-01-01

    The Nuclear Waste Policy Act of 1982 (NWPA) authorized the US Department of Energy (DOE) to establish a national system for the disposal of spent nuclear fuel and high-level radioactive waste from commercial power generation, and established the Office of Civilian Radioactive Waste Management (OCRWM) within the DOE-Headquarters (DOE-HQ) to carry out these duties. A 1985 presidential decision added the disposal of high-level radioactive waste generated by defense programs to the national disposal system. A primary element of the disposal program is the development and operation of a transportation system to move the waste from its present locations to the facilities that will be included in the waste management system. The primary type of disposal facility to be established is a geologic repository; a Monitored Retrievable Storage (MRS) facility may also be included as an intermediate step in the nuclear waste disposal process. This paper focuses on the progress and status of one facet of the transportation program--the development of a family of shipping casks for transporting spent fuel from nuclear power reactor sites to the repository of MRS facility

  4. Repetitive stimulation of autophagy-lysosome machinery by intermittent fasting preconditions the myocardium to ischemia-reperfusion injury.

    Science.gov (United States)

    Godar, Rebecca J; Ma, Xiucui; Liu, Haiyan; Murphy, John T; Weinheimer, Carla J; Kovacs, Attila; Crosby, Seth D; Saftig, Paul; Diwan, Abhinav

    2015-01-01

    Autophagy, a lysosomal degradative pathway, is potently stimulated in the myocardium by fasting and is essential for maintaining cardiac function during prolonged starvation. We tested the hypothesis that intermittent fasting protects against myocardial ischemia-reperfusion injury via transcriptional stimulation of the autophagy-lysosome machinery. Adult C57BL/6 mice subjected to 24-h periods of fasting, every other day, for 6 wk were protected from in-vivo ischemia-reperfusion injury on a fed day, with marked reduction in infarct size in both sexes as compared with nonfasted controls. This protection was lost in mice heterozygous null for Lamp2 (coding for lysosomal-associated membrane protein 2), which demonstrate impaired autophagy in response to fasting with accumulation of autophagosomes and SQSTM1, an autophagy substrate, in the heart. In lamp2 null mice, intermittent fasting provoked progressive left ventricular dilation, systolic dysfunction and hypertrophy; worsening cardiomyocyte autophagosome accumulation and lack of protection to ischemia-reperfusion injury, suggesting that intact autophagy-lysosome machinery is essential for myocardial homeostasis during intermittent fasting and consequent ischemic cardioprotection. Fasting and refeeding cycles resulted in transcriptional induction followed by downregulation of autophagy-lysosome genes in the myocardium. This was coupled with fasting-induced nuclear translocation of TFEB (transcription factor EB), a master regulator of autophagy-lysosome machinery; followed by rapid decline in nuclear TFEB levels with refeeding. Endogenous TFEB was essential for attenuation of hypoxia-reoxygenation-induced cell death by repetitive starvation, in neonatal rat cardiomyocytes, in-vitro. Taken together, these data suggest that TFEB-mediated transcriptional priming of the autophagy-lysosome machinery mediates the beneficial effects of fasting-induced autophagy in myocardial ischemia-reperfusion injury.

  5. Repetitive stimulation of autophagy-lysosome machinery by intermittent fasting preconditions the myocardium to ischemia-reperfusion injury

    Science.gov (United States)

    Godar, Rebecca J; Ma, Xiucui; Liu, Haiyan; Murphy, John T; Weinheimer, Carla J; Kovacs, Attila; Crosby, Seth D; Saftig, Paul; Diwan, Abhinav

    2015-01-01

    Autophagy, a lysosomal degradative pathway, is potently stimulated in the myocardium by fasting and is essential for maintaining cardiac function during prolonged starvation. We tested the hypothesis that intermittent fasting protects against myocardial ischemia-reperfusion injury via transcriptional stimulation of the autophagy-lysosome machinery. Adult C57BL/6 mice subjected to 24-h periods of fasting, every other day, for 6 wk were protected from in-vivo ischemia-reperfusion injury on a fed day, with marked reduction in infarct size in both sexes as compared with nonfasted controls. This protection was lost in mice heterozygous null for Lamp2 (coding for lysosomal-associated membrane protein 2), which demonstrate impaired autophagy in response to fasting with accumulation of autophagosomes and SQSTM1, an autophagy substrate, in the heart. In lamp2 null mice, intermittent fasting provoked progressive left ventricular dilation, systolic dysfunction and hypertrophy; worsening cardiomyocyte autophagosome accumulation and lack of protection to ischemia-reperfusion injury, suggesting that intact autophagy-lysosome machinery is essential for myocardial homeostasis during intermittent fasting and consequent ischemic cardioprotection. Fasting and refeeding cycles resulted in transcriptional induction followed by downregulation of autophagy-lysosome genes in the myocardium. This was coupled with fasting-induced nuclear translocation of TFEB (transcription factor EB), a master regulator of autophagy-lysosome machinery; followed by rapid decline in nuclear TFEB levels with refeeding. Endogenous TFEB was essential for attenuation of hypoxia-reoxygenation-induced cell death by repetitive starvation, in neonatal rat cardiomyocytes, in-vitro. Taken together, these data suggest that TFEB-mediated transcriptional priming of the autophagy-lysosome machinery mediates the beneficial effects of fasting-induced autophagy in myocardial ischemia-reperfusion injury. PMID:26103523

  6. Emerging roles of the spliceosomal machinery in myelodysplastic syndromes and other hematological disorders.

    Science.gov (United States)

    Visconte, V; Makishima, H; Maciejewski, J P; Tiu, R V

    2012-12-01

    In humans, the majority of all protein-coding transcripts contain introns that are removed by mRNA splicing carried out by spliceosomes. Mutations in the spliceosome machinery have recently been identified using whole-exome/genome technologies in myelodysplastic syndromes (MDS) and in other hematological disorders. Alterations in splicing factor 3 subunit b1 (SF3b1) were the first spliceosomal mutations described, immediately followed by identification of other splicing factor mutations, including U2 small nuclear RNA auxillary factor 1 (U2AF1) and serine arginine-rich splicing factor 2 (SRSF2). SF3b1/U2AF1/SRSF2 mutations occur at varying frequencies in different disease subtypes, each contributing to differences in survival outcomes. However, the exact functional consequences of these spliceosomal mutations in the pathogenesis of MDS and other hematological malignancies remain largely unknown and subject to intense investigation. For SF3b1, a gain of function mutation may offer the promise of new targeted therapies for diseases that carry this molecular abnormality that can potentially lead to cure. This review aims to provide a comprehensive overview of the emerging role of the spliceosome machinery in the biology of MDS/hematological disorders with an emphasis on the functional consequences of mutations, their clinical significance, and perspectives on how they may influence our understanding and management of diseases affected by these mutations.

  7. Emerging roles of the spliceosomal machinery in myelodysplastic syndromes and other hematologic disorders

    Science.gov (United States)

    Visconte, V; Makishima, H; Maciejewski, JP; Tiu, RV

    2013-01-01

    In humans, the majority of all protein-coding transcripts contain introns that are removed by mRNA splicing carried out by spliceosomes. Mutations in the spliceosome machinery have recently been identified using whole exome/genome technologies in myelodysplastic syndromes (MDS) and in other hematologic disorders. Alterations in Splicing Factor 3 Subunit b1 (SF3b1) were the first spliceosomal mutations described, immediately followed by identification of other splicing factor mutations, including U2 Small Nuclear RNA Auxillary Factor 1 (U2AF1) and Serine Arginine Rich Splicing Factor 2 (SRSF2). SF3b1/U2AF1/SRSF2 mutations occur at varying frequencies in different disease subtypes, each contributing to differences in survival outcomes. However, the exact functional consequences of these spliceosomal mutations in the pathogenesis of MDS and other hematologic malignancies remain largely unknown and subject to intense investigation. For SF3b1, a gain of function mutation may offer the promise of new targeted therapies for diseases that carry this molecular abnormality that can potentially lead to cure. This review aims to provide a comprehensive overview of the emerging role of the spliceosome machinery in the biology of MDS/hematologic disorders with an emphasis on the functional consequences of mutations, their clinical significance, and perspectives on how they may influence our understanding and management of diseases affected by these mutations. PMID:22678168

  8. Mutations in SNRPB, encoding components of the core splicing machinery, cause cerebro-costo-mandibular syndrome.

    Science.gov (United States)

    Bacrot, Séverine; Doyard, Mathilde; Huber, Céline; Alibeu, Olivier; Feldhahn, Niklas; Lehalle, Daphné; Lacombe, Didier; Marlin, Sandrine; Nitschke, Patrick; Petit, Florence; Vazquez, Marie-Paule; Munnich, Arnold; Cormier-Daire, Valérie

    2015-02-01

    Cerebro-costo-mandibular syndrome (CCMS) is a developmental disorder characterized by the association of Pierre Robin sequence and posterior rib defects. Exome sequencing and Sanger sequencing in five unrelated CCMS patients revealed five heterozygous variants in the small nuclear ribonucleoprotein polypeptides B and B1 (SNRPB) gene. This gene includes three transcripts, namely transcripts 1 and 2, encoding components of the core spliceosomal machinery (SmB' and SmB) and transcript 3 undergoing nonsense-mediated mRNA decay. All variants were located in the premature termination codon (PTC)-introducing alternative exon of transcript 3. Quantitative RT-PCR analysis revealed a significant increase in transcript 3 levels in leukocytes of CCMS individuals compared to controls. We conclude that CCMS is due to heterozygous mutations in SNRPB, enhancing inclusion of a SNRPB PTC-introducing alternative exon, and show that this developmental disease is caused by defects in the splicing machinery. Our finding confirms the report of SNRPB mutations in CCMS patients by Lynch et al. (2014) and further extends the clinical and molecular observations. © 2014 WILEY PERIODICALS, INC.

  9. Total Analysis System for Ship Structural Strength

    OpenAIRE

    Takuya, Yoneya; Hiroyuki, Kobayashi; Abdul M., Rahim; Yoshimichi, Sasaki; Masaki, Irisawa; Technical Investigation and Information Department, Research Center; Technical Investigation and Information Department, Research Center; Singapore Office; Technical Investigation and Information Department, Research Center; Technical Investigation and Information Department, Research Center

    2001-01-01

    This paper outlines a total analysis system for ship hull structures, which integrates a wide variety of analysis functions to realise practical applications of rational methods for assessing ship structural strength. It is based on direct calculation of wave-induced loads as well as three-dimensional structural analysis of an entire-ship or hold structure. Three major analysis functions of the total system are ship motion and wave load analysis, ship structural analysis and statistical analy...

  10. Effects of ship's vibration and motion on plant parameters

    International Nuclear Information System (INIS)

    Kakuta, Tsunemi; Kitamura, Toshikatsu; Mizushima, Toshihiko; Yamazaki, Hiroshi; Nakahara, Takeshi; Kamiya, Eisei; Kudou, Takahiro; Naitoh, Akira; Tominaga, Mineo.

    1992-03-01

    Present report was written about the study of the effects of ship's vibration and motion on reactor plant performances measured and analyzed to confirm the total balance for control systems of reactor to propulsion. On July 10, 1990, or on the first day of the first voyage for the power up test, the sea trials of MUTSU, nuclear ship made first in Japan, started from the anchoring test. The trial tests had finished through the third voyage between October 30 and November 9 to the fourth voyage between 7 and 14 of December. The trial tests had been conducted over ten items or so containing in-house tests of the measurements of ship's vibration and motion in order to research the effects on reactor performance. We here call the in-house tests the plant correlation tests. In regard to the correlation with ship's vibration, we confirmed that the inherent vibrations of hull and reactor containment arisen from ship structure had precisely been measured and that the plant correlations due to the hull and local vibrations arising from propeller revolutions are very small. Concerning the correlation with ship's motion, it was shown that her rolling motion strongly had affected on the propulsion system such as shaft power and shaft revolutions. About the correlation with reactor systems it was found that her pitching motion had given effect on the water level in pressurizer, primary coolant average temperature, ε-signal of the auto-control of reactor power and primary coolant pressure etc, particularly, most-strongly on the water level in pressurizer; her rolling and pitching motions had given effect on nuclear characteristics such as reactivity and startup rate; in addition the fluctuation of 0.06 Hz, we think the response inherent in (MUTSU) reactor systems, had been observed on her reactor parameters like reactivity and startup rate, and her propulsion systems like shaft horse power. (author)

  11. LEVERAGING AGING MATERIALS DATA TO SUPPORT EXTENSION OF TRANSPORTATION SHIPPING PACKAGES SERVICE LIFE

    Energy Technology Data Exchange (ETDEWEB)

    Dunn, K. [Savannah River National Laboratory; Bellamy, S. [Savannah River National Laboratory; Daugherty, W. [Savannah River National Laboratory; Sindelar, R. [Savannah River National Laboratory; Skidmore, E. [Savannah River National Laboratory

    2013-08-18

    Nuclear material inventories are increasingly being transferred to interim storage locations where they may reside for extended periods of time. Use of a shipping package to store nuclear materials after the transfer has become more common for a variety of reasons. Shipping packages are robust and have a qualified pedigree for performance in normal operation and accident conditions but are only certified over an approved transportation window. The continued use of shipping packages to contain nuclear material during interim storage will result in reduced overall costs and reduced exposure to workers. However, the shipping package materials of construction must maintain integrity as specified by the safety basis of the storage facility throughout the storage period, which is typically well beyond the certified transportation window. In many ways, the certification processes required for interim storage of nuclear materials in shipping packages is similar to life extension programs required for dry cask storage systems for commercial nuclear fuels. The storage of spent nuclear fuel in dry cask storage systems is federally-regulated, and over 1500 individual dry casks have been in successful service up to 20 years in the US. The uncertainty in final disposition will likely require extended storage of this fuel well beyond initial license periods and perhaps multiple re-licenses may be needed. Thus, both the shipping packages and the dry cask storage systems require materials integrity assessments and assurance of continued satisfactory materials performance over times not considered in the original evaluation processes. Test programs for the shipping packages have been established to obtain aging data on materials of construction to demonstrate continued system integrity. The collective data may be coupled with similar data for the dry cask storage systems and used to support extending the service life of shipping packages in both transportation and storage.

  12. AN ENHANCED EQUATION FOR VIBRATION PREDICTION OF NEW TYPES OF SHIPS

    Directory of Open Access Journals (Sweden)

    Valer Cergol

    2015-09-01

    Full Text Available AA simplified approach developed to evaluate the vibration levels of complex structures such as passenger and similar ships with large shell and deck openings and extended superstructures is here presented. The final objective is to give an useful tool to ship designers, to establish since the first design stage the dynamic response of the ship with sufficient precision. This approach is based on the assumption that the ship hull can be represented as a non uniform section beam. The propeller excitations in terms of pressure pulses and shaft line moments and forces are introduced. To take into account this exciting source in the early design stage a statistical formula for dynamic excitation of propeller was developed. Furthermore the superimposition of local effects has been performed with the use of an analytical formula. The local effect due to the different space topologies such as cabins, public spaces, technical and machinery areas has been taken into account. The transversal beams, longitudinal girders, stiffeners and pillars as supported structural elements are considered in the vibration local response. The reliability of the results obtained using the formula has been improved with more precise results obtained by FEM analysis. The calculated vibration response has been verified and compared to vibration measurements performed on board of ships.

  13. Cavitation and gas-liquid flow in fluid machinery and devices. FED-Volume 190

    International Nuclear Information System (INIS)

    O'Hern, T.J.; Kim, J.H.; Morgan, W.B.; Furuya, O.

    1994-01-01

    Cavitation and gas-liquid two-phase flow have remained important areas in many industrial applications and constantly provided challenges for academic researchers and industrial practitioners alike. Cavitation and two-phase flow commonly occur in fluid machinery such as pumps, propellers, and fluid devices such as orifices, valves, and diffusers. Cavitation not only degrades the performance of these machines and devices but deteriorates the materials. Gas-liquid two-phase flow has also been known to degrade the performance of pumps and propellers and can often induce an instability. The industrial applications of cavitation and two-phase flow can be found in power plants, ship propellers, hydrofoils, and aerospace equipment, to name but a few. The papers presented in this volume reflect the variety and richness of cavitation and gas-liquid two-phase flow in various flow transporting components and the increasing role they play in modern and conventional technologies. Separate abstracts were prepared for 35 papers in this book

  14. The Research of Computer Aided Farm Machinery Designing Method Based on Ergonomics

    Science.gov (United States)

    Gao, Xiyin; Li, Xinling; Song, Qiang; Zheng, Ying

    Along with agricultural economy development, the farm machinery product type Increases gradually, the ergonomics question is also getting more and more prominent. The widespread application of computer aided machinery design makes it possible that farm machinery design is intuitive, flexible and convenient. At present, because the developed computer aided ergonomics software has not suitable human body database, which is needed in view of farm machinery design in China, the farm machinery design have deviation in ergonomics analysis. This article puts forward that using the open database interface procedure in CATIA to establish human body database which aims at the farm machinery design, and reading the human body data to ergonomics module of CATIA can product practical application virtual body, using human posture analysis and human activity analysis module to analysis the ergonomics in farm machinery, thus computer aided farm machinery designing method based on engineering can be realized.

  15. Simulation of a marine nuclear reactor

    International Nuclear Information System (INIS)

    Kusunoki, Tsuyoshi; Kyouya, Masahiko; Kobayashi, Hideo; Ochiai, Masaaki

    1995-01-01

    A Nuclear-powered ship Engineering Simulation SYstem (NESSY) has been developed by the Japan Atomic Energy Research Institute as an advanced design tool for research and development of future marine reactors. A marine reactor must respond to changing loads and to the ship's motions because of the ship's maneuvering and its presence in a marine environment. The NESSY has combined programs for the reactor plant behavior calculations and the ship's motion calculations. Thus, it can simulate reactor power fluctuations caused by changing loads and the ship's motions. It can also simulate the behavior of water in the pressurizer and steam generators. This water sloshes in response to the ship's motions. The performance of NESSY has been verified by comparing the simulation calculations with the measured data obtained by experiments performed using the nuclear ship Mutsu. The effects of changing loads and the ship's motions on the reactor behavior can be accurately simulated by NESSY

  16. Effect of Buffer Bow Structure in Ship-Ship Collision

    DEFF Research Database (Denmark)

    Yamada, Yasuhira; Endo, Hisayoshi; Pedersen, Preben Terndrup

    2008-01-01

    tankers, the introduction of buffer bulbous bows has been proposed. Relatively soft buffer bows absorb part of the kinetic energy of the striking ship before penetrating the inner hull of the struck vessel. The purpose of the present paper is to verify the effectiveness of a prototype buffer bulbous bow......) and the forward velocity of the struck ship on the collapse mode of the bow of the striking vessel are investigated. Collapse modes, contact forces and energy absorption capabilities of the buffer bows are compared with those of conventional bows....

  17. EX1001 Ship Shakedown (EX1001, EM302) on NOAA Ship Okeanos Explorer in Hawaiian Islands

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The ship has been alongside for repairs and leave since November, 2009. The ship shakedown cruise is scheduled to provide an opportunity for the ship to get underway...

  18. Reliability Based Ship Structural Design

    DEFF Research Database (Denmark)

    Dogliani, M.; Østergaard, C.; Parmentier, G.

    1996-01-01

    This paper deals with the development of different methods that allow the reliability-based design of ship structures to be transferred from the area of research to the systematic application in current design. It summarises the achievements of a three-year collaborative research project dealing...... with developments of models of load effects and of structural collapse adopted in reliability formulations which aim at calibrating partial safety factors for ship structural design. New probabilistic models of still-water load effects are developed both for tankers and for containerships. New results are presented...... structure of several tankers and containerships. The results of the reliability analysis were the basis for the definition of a target safety level which was used to asses the partial safety factors suitable for in a new design rules format to be adopted in modern ship structural design. Finally...

  19. Design of Crashworthy Ship Strucures

    DEFF Research Database (Denmark)

    Toernqvist, Rikard

    2003-01-01

    The main purpose of the project has been to develop a rational procedure for designing new crashworthy side structures for those ship types where it could be expected that a substantial improvement of the crashworthiness and the related safety could be achieved by careful consideration of the str......The main purpose of the project has been to develop a rational procedure for designing new crashworthy side structures for those ship types where it could be expected that a substantial improvement of the crashworthiness and the related safety could be achieved by careful consideration...... in collision and grounding analysis is the prediction of the onset of fracture and crack propagation in the shell plating. In simulations of accidental loading on ships it is crucial that fracture is determined correctly, as it will influence the global deformation mode and the amount of damage to the hull...

  20. On Grounding of Fast Ships

    DEFF Research Database (Denmark)

    Simonsen, Bo Cerup; Pedersen, Preben Terndrup

    1997-01-01

    The paper deals with analysis of grounding of high-speed crafts. It is the purpose to present a comprehensive mathematical model for calculation of the overall dynamic ship response during grounding. This procedure is applied to derive the motions, the time varying sectional forces and the local...... loads during grounding on plane, sloping, sandy bottoms for six different designs of fast monohull ships made from steel, aluminium or GRP sandwich materials. The results show that the effect of the hull flexibility is to reduce the overall dynamic sectional loads on the hull girder. The considered...... numerical examples also indicate that, even with impact speeds of 40 knots against a 1:10 sloping bottom, the global strength of the hull girder is not exceeded by the grounding induced loads.For the local deformation of high-speed ship hulls at the point of contact with the ground, the paper presents...

  1. Scattering transform and LSPTSVM based fault diagnosis of rotating machinery

    Science.gov (United States)

    Ma, Shangjun; Cheng, Bo; Shang, Zhaowei; Liu, Geng

    2018-05-01

    This paper proposes an algorithm for fault diagnosis of rotating machinery to overcome the shortcomings of classical techniques which are noise sensitive in feature extraction and time consuming for training. Based on the scattering transform and the least squares recursive projection twin support vector machine (LSPTSVM), the method has the advantages of high efficiency and insensitivity for noise signal. Using the energy of the scattering coefficients in each sub-band, the features of the vibration signals are obtained. Then, an LSPTSVM classifier is used for fault diagnosis. The new method is compared with other common methods including the proximal support vector machine, the standard support vector machine and multi-scale theory by using fault data for two systems, a motor bearing and a gear box. The results show that the new method proposed in this study is more effective for fault diagnosis of rotating machinery.

  2. 49 CFR 393.130 - What are the rules for securing heavy vehicles, equipment and machinery?

    Science.gov (United States)

    2010-10-01

    ... heavy vehicles, equipment and machinery? (a) Applicability. The rules in this section apply to the transportation of heavy vehicles, equipment and machinery which operate on wheels or tracks, such as front end... heavy vehicles, equipment or machinery with crawler tracks or wheels. (1) In addition to the...

  3. 40 CFR 180.521 - Fumigants for grain-mill machinery; tolerances for residues.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 23 2010-07-01 2010-07-01 false Fumigants for grain-mill machinery... Tolerances § 180.521 Fumigants for grain-mill machinery; tolerances for residues. (a) General. Fumigants may be safely used in or on grain-mill machinery in accordance with the following prescribed conditions...

  4. Dedicated monitoring and machinery protection systems on reciprocating compressors

    Energy Technology Data Exchange (ETDEWEB)

    Grande, Alvaro; Wenisch, Markus [Hoerbiger Ventilwerke GmbH and Co KG, Wien (Austria); Jacobs, Denis [HOERBIGER do Brasil Industria de Equipamentos, Cajamar, SP (Brazil)

    2012-07-01

    Growing demands on reciprocating compressors (recips) in the process gas industry require particular solutions for machinery protection and performance monitoring systems. Compared to rotating equipment, monitoring systems for recips have to consider the special mechanical and physical characteristics, such as oscillating masses, variable vibration behaviour and varying operating conditions. Furthermore, they provide valuable information about the performance of cylinder related components allowing the operator the optimization of efficiency and availability, and therefore increase production. (author)

  5. Abrasive Wear of Alloyed Cast Steels Applied for Heavy Machinery

    Directory of Open Access Journals (Sweden)

    Studnicki A.

    2015-03-01

    Full Text Available In the paper the results and analysis of abrasive wear studies were shown for two grades of cast steels: low-alloyed cast steel applied for heavy machinery parts such as housing, covers etc. and chromium cast steels applied for kinetic nodes of pin-sleeve type. Studies were performed using the modified in Department of Foundry pin-on-disc method.

  6. Targeting Transcription Elongation Machinery for Breast Cancer Therapy

    Science.gov (United States)

    2017-05-01

    ABSTRACT: This project focuses on the important but under-studied role of the P-TEFb- dependent transcription elongation machinery in human breast...molecule CDK9 inhibitors can be used to halt breast cancer metastasis. 8 experimental groups to test various drug dosage and frequency regimes will...tumor cells, which are said to be ’ addicted ’ to this protein. Consistently, pharmacological inhibition of Hsp90 has demonstrated great promise in

  7. Electric machinery and drives in thermal power stations

    International Nuclear Information System (INIS)

    1974-01-01

    The following subjects were dealt with during the VDE meeting: 1) Requirements made by the electric network on the generators and their excitation equipment, and the influence thereof on their design; 2) requirements made by the power station process on the electric drives and the influence thereof on type and design; 3) requirements made on protective measures from the point of the electric power station machinery. (TK) [de

  8. Performance of machinery in potato production in one growing season

    Directory of Open Access Journals (Sweden)

    Kun Zhou

    2015-12-01

    Full Text Available Statistics on the machinery performance are essential for farm managers to make better decisions. In this paper, the performance of all machineries in five sequential operations, namely bed forming, stone separation, planting, spraying and harvesting in the potato production system, were investigated during one growing season. In order to analyse and decompose the recorded GPS data into various time and distance elements for estimation of the machinery performance, an automatic GPS analysis tool was developed. The field efficiency and field capacity were estimated for each operation. Specifically, the measured average field efficiency was 71.3% for bed forming, 68.5% for stone separation, 40.3% for planting, 69.7% for spraying, and 67.4% for harvesting. The measured average field capacities were 1.46 ha/h, 0.53 ha/h, 0.47 ha/h, 10.21 ha/h, 0.51 ha/h, for the bed forming, stone separation, planting, spraying, and harvesting operations, respectively. These results deviate from the corresponding estimations calculated based on norm data from the American Society of Agricultural and Biological Engineers (ASABE. The deviations indicate that norms provided by ASABE cannot be used directly for the prediction of performance of the machinery used in this work. Moreover, the measured data of bed forming and stone separation could be used as supplementary data for the ASABE which does not provide performance norms for these two operations. The gained results can help farm managers to make better management and operational decisions that result in potential improvement in productivity and profitability as well as in potential environmental benefits.

  9. Designing a machinery control system (MCS) security testbed

    OpenAIRE

    Desso, Nathan H.

    2014-01-01

    Approved for public release; distribution is unlimited Industrial control systems (ICS) face daily cyber security threats, can have a significant impact to the security of our nation, and present a difficult challenge to defend. Critical infrastructures, including military systems like the machinery control systems (MCS) found onboard modern U.S. warships, are affected because of their use of commercial automation solutions. The increase of automated control systems within the U.S. Navy sa...

  10. Performance of machinery in potato production in one growing season

    Energy Technology Data Exchange (ETDEWEB)

    Zhou, K.; Jensen, A.L.; Bochtis, D.D.; Sørensen, C.G.

    2015-07-01

    Statistics on the machinery performance are essential for farm managers to make better decisions. In this paper, the performance of all machineries in five sequential operations, namely bed forming, stone separation, planting, spraying and harvesting in the potato production system, were investigated during one growing season. In order to analyse and decompose the recorded GPS data into various time and distance elements for estimation of the machinery performance, an automatic GPS analysis tool was developed. The field efficiency and field capacity were estimated for each operation. Specifically, the measured average field efficiency was 71.3% for bed forming, 68.5% for stone separation, 40.3% for planting, 69.7% for spraying, and 67.4% for harvesting. The measured average field capacities were 1.46 ha/h, 0.53 ha/h, 0.47 ha/h, 10.21 ha/h, 0.51 ha/h, for the bed forming, stone separation, planting, spraying, and harvesting operations, respectively. These results deviate from the corresponding estimations calculated based on norm data from the American Society of Agricultural and Biological Engineers (ASABE). The deviations indicate that norms provided by ASABE cannot be used directly for the prediction of performance of the machinery used in this work. Moreover, the measured data of bed forming and stone separation could be used as supplementary data for the ASABE which does not provide performance norms for these two operations. The gained results can help farm managers to make better management and operational decisions that result in potential improvement in productivity and profitability as well as in potential environmental benefits. (Author)

  11. Fault diagnosis in rotating machinery by vibration analysis

    International Nuclear Information System (INIS)

    Behzad, M.; Asayesh, M.

    2002-01-01

    Dynamic behavior of unbalanced bent shaft has been investigated in this research. Finite element method is used for unbalance response calculation of a bent shaft. The result shows the effect of bent on the unbalance response. The angle between bent vector and unbalance force, position and type of supports, shaft diameter and disk position can affect the outcome. The results of this research can significantly help in fault diagnosis in rotating machinery

  12. Status of spent fuel shipping cask development

    International Nuclear Information System (INIS)

    Hall, I.K.; Hinschberger, S.T.

    1989-01-01

    This paper discusses how several new-generation shopping cask systems are being developed for safe and economical transport of commercial spent nuclear fuel and other radioactive wastes for the generating sites to a federal geologic repository or monitored retrievable storage (MRS) facility. Primary objectives of the from-reactor spent fuel cask development work are: to increase cask payloads by taking advantage of the increased at-reactor storage time under the current spent fuel management scenario, to facilitate more efficient cask handling operations with reduced occupational radiation exposure, and to promote standardization of the physical interfaces between casks and the shipping and receiving facilities. Increased cask payloads will significantly reduce the numbers of shipments, with corresponding reductions in transportation costs and risks to transportation workers, cask handling personnel, and the general public

  13. Recent results of experiments at SHIP

    International Nuclear Information System (INIS)

    Hofmann, S.

    1997-10-01

    The new elements 110, 111 and 112 were synthesized and unambiguously identified in experiments at SHIP. The decay data were compared with the predictions of theoretical models. Good agreement was obtained for the nuclei up to element Z=112. Theory predicts deformed nuclei with minimum (negative) shell-correction energy at Z=108 and N=162. Candidates for an experimental investigation of spherical superheavy nuclei (SHE) are selected on the basis of the predictions of the nuclear models and extrapolation of experimental results. The production cross-sections up to element Z=112 were measured, partly accurate excitation functions were obtained. The data allow to fix a narrow energy window for production of SHE by ln-emission channels. Possibilities to broaden the energy window by radiative capture reactions, use of neutron deficient projectile isotopes and use of actinide targets are discussed. (orig.)

  14. Verification of the machinery condition monitoring technology by fault simulation tests

    International Nuclear Information System (INIS)

    Maehara, Takafumi; Watanabe, Yukio; Osaki, Kenji; Higuma, Koji; Nakano, Tomohito

    2009-01-01

    This paper shows the test items and equipments introduced by Japan Nuclear Energy Safety Organization to establish the monitoring technique for machinery conditions. From the result of vertical pump simulation tests, it was confirmed that fault analysis was impossible by measuring the accelerations on both motor and pump column pipes, however, was possible by measuring of pump shaft vibrations. Because hydraulic whirls by bearing wear had significant influences over bearing misalignments and flow rates, the monitoring trends must be done under the same condition (on bearing alignments and flow rates). We have confirmed that malfunctions of vertical pumps can be diagnosed using measured shaft vibration by ultrasonic sensors from outer surface of pump casing on the floor. (author)

  15. Ships - inspiring objects in architecture

    Science.gov (United States)

    Marczak, Elzbieta

    2017-10-01

    Sea-going vessels have for centuries fascinated people, not only those who happen to work at sea, but first and foremost, those who have never set foot aboard a ship. The environment in which ships operate is reminiscent of freedom and countless adventures, but also of hard and interesting maritime working life. The famous words of Pompey: “Navigare necesseest, vivere non estnecesse” (sailing is necessary, living - is not necessary), which he pronounced on a stormy sea voyage, arouse curiosity and excitement, inviting one to test the truth of this saying personally. It is often the case, however, that sea-faring remains within the realm of dreams, while the fascination with ships demonstrates itself through a transposition of naval features onto land constructions. In such cases, ship-inspired motifs bring alive dreams and yearnings as well as reflect tastes. Tourism is one of the indicators of people’s standard of living and a measure of a society’s civilisation. Maritime tourism has been developing rapidly in recent decades. A sea cruise offers an insight into life at sea. Still, most people derive their knowledge of passenger vessels and their furnishings from the mass media. Passenger vessels, also known as “floating cities,” are described as majestic and grand, while their on-board facilities as luxurious, comfortable, exclusive and inaccessible to common people on land. Freight vessels, on the other hand, are described as enormous objects which dwarf the human being into insignificance. This article presents the results of research intended to answer the following questions: what makes ships a source of inspiration for land architecture? To what extent and by what means do architects draw on ships in their design work? In what places can we find structures inspired by ships? What ships inspire architects? This article presents examples of buildings, whose design was inspired by the architecture and structural details of sea vessels. An analysis of

  16. Wind Forces on Container Ships

    DEFF Research Database (Denmark)

    Andersen, Ingrid Marie Vincent

    2012-01-01

    An investigation of the wind forces acting on a 9,000+ TEU container ship has been carried out through a series of wind tunnel tests. It was investigated how the wind forces depend on the container configuration on the deck using a 1:450 scale model and a series of appropriate container...... are presented as nondimensional coefficients. It is concluded, that the measured forces and moment depend on the container configuration on deck, and the results may provide a general idea of how the magnitude of the wind forces is affected by a given container stacking configuration on a similar container ship....

  17. Quality management in shipping companies

    Directory of Open Access Journals (Sweden)

    Đergović Dragana M.

    2017-01-01

    Full Text Available As international business becomes more competitive, companies are finding that they need to work more effectively to stay in business. Quality assurance has become very important to the majority of production and service companies with international activity. Shipping companies were also required to implement a quality management system. The huge importance of safety in maritime transport operations resulted in the International Safety Management Code (ISM Code by the International Maritime Organization. The general management system principles embodied by the maritime ISM Code and generics ISO standards, have enabled their complementary application in establishing a quality management system in shipping companies, within a safety management system as its subset.

  18. Production method of hydrogen jet plasma process in hydro machinery

    International Nuclear Information System (INIS)

    Amini, F.

    2007-01-01

    The purpose of present paper is to the process of plasma formation in hydro machinery when a hydro turbine operates at various conditions and load rejection. By investigation the power, shock pressure , and impact effects of hydro machinery, it is revealed that energy and hydrogen are generated by the plasma process. The investigation on several turbines of various hydro power plants reveals that cold fusion process in hydro machinery generates hydrogen. The hypothesis concerning the participation of alkaline metals in river water and the atomic nuclei of the runner blade material in the formation of hydrogen are considered. It is possible to assume hydrogen, deuterium, helium, and tritium atoms (based on Dr. Mizuno and Dr. Kanarev theories) that are formed, diffuse into cavitation bubbles. The plasma is generated during the collapse of the bubble; thus, the quantity of burnt hydrogen determine the volume of generating hydrogen and the impact force caused by hydrogen explosion (noise).There are five main notions, which can determine hydrogen and plasma process: (1) turbine power effect, (2) high shock pressure, (3) crack on turbine parts, (4) impacts effects and (4) the lift of rotating parts. The frequency of the excitation lies in a range from 0.786 to 1.095 Hz.In future, it may be possible to design hydro turbines based on the plasma process that generates hydrogen; or there may exist turbines that rotate with a mixture of hydrogen explosion and water energies

  19. On the reversed Brayton cycle with high speed machinery

    Energy Technology Data Exchange (ETDEWEB)

    Backman, J.

    1996-12-31

    This work was carried out in the laboratory of Fluid Dynamics, at Lappeenranta University of Technology during the years 1991-1996. The research was a part of larger high speed technology development research. First, there was the idea of making high speed machinery applications with the Brayton cycle. There was a clear need to deepen the knowledge of the cycle itself and to make a new approach in the field of the research. Also, the removal of water from the humid air seemed very interesting. The goal of this work was to study methods of designing high speed machinery for the reversed Brayton cycle, from theoretical principles to practical applications. The reversed Brayton cycle can be employed as an air dryer, a heat pump or a refrigerating machine. In this research the use of humid air as a working fluid has an environmental advantage, as well. A new calculation method for the Brayton cycle is developed. In this method especially the expansion process in the turbine is important because of the condensation of the water vapour in the humid air. This physical phenomena can have significant effects on the level of performance of the application. Also, the influence of calculating the process with actual, achievable process equipment efficiencies is essential for the development of future machinery. The above theoretical calculations are confirmed with two different laboratory prototypes. (53 refs.)

  20. On the reversed Brayton cycle with high speed machinery

    Energy Technology Data Exchange (ETDEWEB)

    Backman, J

    1997-12-31

    This work was carried out in the laboratory of Fluid Dynamics, at Lappeenranta University of Technology during the years 1991-1996. The research was a part of larger high speed technology development research. First, there was the idea of making high speed machinery applications with the Brayton cycle. There was a clear need to deepen the knowledge of the cycle itself and to make a new approach in the field of the research. Also, the removal of water from the humid air seemed very interesting. The goal of this work was to study methods of designing high speed machinery for the reversed Brayton cycle, from theoretical principles to practical applications. The reversed Brayton cycle can be employed as an air dryer, a heat pump or a refrigerating machine. In this research the use of humid air as a working fluid has an environmental advantage, as well. A new calculation method for the Brayton cycle is developed. In this method especially the expansion process in the turbine is important because of the condensation of the water vapour in the humid air. This physical phenomena can have significant effects on the level of performance of the application. Also, the influence of calculating the process with actual, achievable process equipment efficiencies is essential for the development of future machinery. The above theoretical calculations are confirmed with two different laboratory prototypes. (53 refs.)