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.)

Nonproliferation norms in civilian nuclear fuel cycle

International Nuclear Information System (INIS)

Kawata, Tomio

2005-01-01

For sustainable use of nuclear energy in large scale, it seems inevitable to choose a closed cycle option. One of the important questions is, then, whether we can really achieve the compatibility between civilian nuclear fuel cycle and nonproliferation norms. In this aspect, Japan is very unique because she is now only one country with full-scope nuclear fuel cycle program as a non-nuclear weapon state in NPT regime. In June 2004 in the midst of heightened proliferation concerns in NPT regime, the IAEA Board of Governors concluded that, for Japanese nuclear energy program, non-diversion of declared nuclear material and the absence of undeclared nuclear material and activities were verified through the inspections and examinations under Comprehensive Safeguards and the Additional Protocol. Based on this conclusion, the IAEA announced the implementation of Integrated Safeguards in Japan in September 2004. This paper reviews how Japan has succeeded in becoming the first country with full-scope nuclear fuel cycle program to qualify for integrated Safeguards, and identifies five key elements that have made this achievement happen: (1) Obvious need of nuclear fuel cycle program, (2) Country's clear intention for renunciation of nuclear armament, (3) Transparency of national nuclear energy program, (4) Record of excellent compliance with nonproliferation obligations for many decades, and (5) Numerous proactive efforts. These five key elements will constitute a kind of an acceptance model for civilian nuclear fuel cycle in NNWS, and may become the basis for building 'Nonproliferation Culture'. (author)

Strengthening the nuclear nonproliferation regime: focus on the civilian nuclear fuel cycle

International Nuclear Information System (INIS)

Saltiel, David H.; Pregenzer, Arian Leigh

2005-01-01

Leaders around the world and across the ideological spectrum agree that the global nonproliferation regime is facing a serious test. The emergence of sophisticated terrorist networks, black markets in nuclear technology, and technological leaps associated with globalization have conspired to threaten one of the most successful examples of international cooperation in history. The rampant proliferation of nuclear weapons that was predicted at the start of the nuclear age has been largely held in check and the use of those weapons avoided. Nonetheless, with the thirty-fifth anniversary of the Treaty on the Nonproliferation of Nuclear Weapons (NPT), the threat of nuclear proliferation seems more serious than ever. Although experts readily concede that there exist many pathways to proliferation, the threat posed by the misuse of the civilian nuclear fuel cycle has received considerable recent attention. While the connection between nuclear energy and nonproliferation has been a topic of discussion since the dawn of the nuclear age, world events have brought the issue to the forefront once again. United States President George W. Bush and International Atomic Energy Agency (IAEA) Director General Mohammad ElBaradei are among those who have highlighted proliferation risks associated with civilian nuclear power programs and called for revitalizing the nuclear nonproliferation regime to address new threats. From the possibility of diversion or theft of nuclear material or technology, to the use of national civilian programs as a cover for weapons programs - what some have called latent proliferation - the fuel cycle appears to many to represent a glaring proliferation vulnerability. Just as recognition of these risks is not new, neither is recognition of the many positive benefits of nuclear energy. In fact, a renewed interest in exploiting these benefits has increased the urgency of addressing the risks. Global energy demand is expected to at least double by the middle of

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)

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

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.

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.)

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

Status of the civilian nuclear industry in Asia

International Nuclear Information System (INIS)

Heim, Alexandre; Laconde, Thibault

2011-01-01

The main nuclear actors in Asia are China, South Korea, India and Japan. The authors indicate the share of nuclear energy in their energy mix, the number of operating reactors, the total installed power, and the number of projects. Then, for each of these four countries, and for Pakistan and Taiwan, they propose a brief history of the nuclear program and briefly present its current status. They also evoke the official reactions after the Fukushima accident. Finally, they briefly discuss some issues for the development of civilian nuclear industry in Asia: uranium supplies, nuclear waste processing, development of a national nuclear sector

The French civilian nuclear: connections and stakes

International Nuclear Information System (INIS)

2010-01-01

This document (18 power point slides) gives an overview of the French civilian nuclear industry and research and development: importance of the nuclear power generation in France, excellence of the education in nuclear sciences, organization of the nuclear connection (CEA, Areva, EDF, IRSN), the role of the French International Nuclear Agency (AFNI), the requirements for a renewal of human resources (French and foreign engineers) in the field of nuclear energy, the degree course for a diploma, examples of engineer and university diplomas, the educational networks in various regions of France, presentation of the Institut National des Sciences et Techniques Nucleaires (Nuclear Sciences and Techniques National Institute) and its master degrees, organization of the French education system in nuclear sciences with strong relations with the research and development programs

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

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.

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.)

Ideology in science and technology: the case of civilian nuclear power

International Nuclear Information System (INIS)

Harrod, A.N.

1987-01-01

This dissertation traces the complicated interrelationships between ideology and interest within the civilian nuclear power controversy. The first chapter introduces the topic. The second chapter provides a social-political-economic overview of the context in which the conflicting ideologies arose. Factors looked at are the ascendancy of the physical sciences, the development of nuclear energy, the disenchantment with science and technology and the consequent rise of an anti-nuclear ideology. Chapter III uses the theories of Alvin Gouldner to understand the structure of ideology. The chapter defines ideology's similarities to and differences from scientific discourse. Chapter IV examines the ideological discourse of a selected sample of scientists who have spoken for and against civilian nuclear power. In parallel to chapter IV, chapter V examines a scientific controversy among the sample of experts. It shows how scientific disagreement can be produced and how ideology is most closely linked to science. Chapter VI examines the social interests of the scientists and experts to discover ways that interests have shaped the ideological and scientific positions for and against civilian nuclear energy. Based on the foregoing, chapter VII concludes that the introduction of science and experts into a controversy cannot be expected to end disagreement over policy because of the link between science and ideology

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)

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

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

Atom Mirny: The World’S First Civilian Nuclear Power Plant

International Nuclear Information System (INIS)

Kaiser, Peter; Madsen, Michael

2013-01-01

The world’s first civilian nuclear power plant was commissioned on June 27, 1954 in Obninsk, which was at that time in the Soviet Union, today, the Russian Federation. The Obninsk nuclear power plant generated electricity and supported experimental nuclear research. The Obninsk nuclear power plant operated without incident for 48 years. In September 2002, the last fuel subassembly was unloaded, when the Obninsk nuclear power plant set another first: it became the first nuclear power plant to be decommissioned in Russia

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.)

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.

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.

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.)

Code on the safety of civilian nuclear fuel cycle installations

International Nuclear Information System (INIS)

1996-01-01

The 'Code' was promulgated by the National Nuclear Safety Administration (NSSA) on June 17, 1993, which is applicable to civilian nuclear fuel fabrication, processing, storage and reprocessing installations, not including the safety requirements for the use of nuclear fuel in reactors. The contents of the 'Code' involve siting, design, construction, commissioning, operation and decommissioning of fuel cycle installation. The NNSA shall be responsible for the interpretation of this 'Code'

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

Potential nuclear material safeguards applied to the Department of Energy's Civilian Radioactive Waste Management System

International Nuclear Information System (INIS)

Danker, W.J.; Floyd, W.

1993-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) within the U.S. Department of Energy is charged with the responsibility of safe and efficient disposal of this Nation's civilian high-level radioactive waste and spent fuel. Part of this responsibility includes providing for the application of both domestic and international safeguards on nuclear material at facilities of the Civilian Waste Management System. While detailed safeguards requirements for these disposal facilities have yet to be established, once established, they could impact facility design. Accordingly, OCRWM has participated in efforts to develop safeguards approaches for geologic repositories and will continue to participate actively with the Nuclear Regulatory Commission (NRC), International Atomic Energy Agency (IAEA), as well as other Department of Energy (DOE) Offices in efforts to resolve safeguards issues related to spent fuel disposal, to minimize any potential design impacts and to support effective nuclear material safeguards. The following paper discusses current plants and issues related to the application of safeguards to the Civilian Radioactive Waste Management System (CRWMS)

Major alternatives for government policies, organizational structures, and actions in civilian nuclear reactor emergency management in the United States

International Nuclear Information System (INIS)

1980-01-01

The purpose of this report is to identify and assess major alternatives for governmental policies, organizational structures, and actions in civilian nuclear reactor emergency management in the United States. The National Academy of Public Administration agreed to identify and evaluate alternatives for governmental policies, organizational structures, and actions in civilian nuclear reactor emergency management. It agreed to review present policies and practices in civilian nuclear reactor emergency management, to review selected experiences and practices of governmental agencies other than the Nuclear Regulatory Commission, and industries other than the nuclear power industry, and to identify alternatives to the present nuclear emergency system

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.)

Historical civilian nuclear accident based Nuclear Reactor Condition Analyzer

Science.gov (United States)

McCoy, Kaylyn Marie

There are significant challenges to successfully monitoring multiple processes within a nuclear reactor facility. The evidence for this observation can be seen in the historical civilian nuclear incidents that have occurred with similar initiating conditions and sequences of events. Because there is a current lack within the nuclear industry, with regards to the monitoring of internal sensors across multiple processes for patterns of failure, this study has developed a program that is directed at accomplishing that charge through an innovation that monitors these systems simultaneously. The inclusion of digital sensor technology within the nuclear industry has appreciably increased computer systems' capabilities to manipulate sensor signals, thus making the satisfaction of these monitoring challenges possible. One such manipulation to signal data has been explored in this study. The Nuclear Reactor Condition Analyzer (NRCA) program that has been developed for this research, with the assistance of the Nuclear Regulatory Commission's Graduate Fellowship, utilizes one-norm distance and kernel weighting equations to normalize all nuclear reactor parameters under the program's analysis. This normalization allows the program to set more consistent parameter value thresholds for a more simplified approach to analyzing the condition of the nuclear reactor under its scrutiny. The product of this research provides a means for the nuclear industry to implement a safety and monitoring program that can oversee the system parameters of a nuclear power reactor facility, like that of a nuclear power plant.

Perspectives on civilian nuclear power in the US

International Nuclear Information System (INIS)

Edwards, J.G.

1985-01-01

During President Reagan's first term, the nation faced squarely most of the major issues facing nuclear power - issues which had accumulated for several decades. The nation established a very large and challenging agenda aimed at: removing Federal impediments to commercial nuclear power; aimed at fulfilling Federal statutory responsibilities in nuclear power rather than sluffing off those obligations; and aimed at restoring the Federal Government as a reliable partner with industry rather than a vacillating nuisance - a cheerleader one day and a nag the next. Very substantive progress has been made on that agenda in the face of what seemed to be insurmountable opposition. The US civilian nuclear program was launched by President Eisenhower in the 1950's. In the 1980's, another great American President has moved to restore the commitment to safe, economic and reliable nuclear power

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

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.).

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.)

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)

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.)

Integration of the military and civilian nuclear fuel cycles in Russia

International Nuclear Information System (INIS)

Bukharin, O.

1994-01-01

This paper describes the close integration of the civil and military nuclear fuel cycles in Russia. Individual processing facilities, as well as the flow of nuclear material, are described as they existed in the 1980s and as they exist today. The end of the Cold War and the breakup of the Soviet Union weakened the ties between the two nuclear fuel cycles, but did not separate them. Separation of the military and civilian nuclear fuel cycles would facilitate Russia's integration into the world's nuclear fuel cycle and its participation in international non-proliferation regimes

The making of French nuclear energy policy. Through the relationship between civilian and military use

International Nuclear Information System (INIS)

Kimura, Kenji

2013-01-01

The French history of nuclear development clearly shows the inseparability of its civilian use from military use. In France, Commissariat a l'Energie Atomique (CEA) and Electricite de France (EDF) have played an important role in research and development of nuclear technology since the postwar period. At first, the two organizations had kept great autonomy, but the government reinforced its control on them because France needed nuclear deterrence against the Soviet Union. France began using plutonium in 1952, and the Suez crisis in 1956 showed the need for nuclear force to ensure its independence. After this event, France managed the first nuclear test using plutonium in 1960. As for enriched uranium, they have long had great difficulty in securing it. The uranium enrichment technology became crucial also in civilian use in this period. EDF proposed the pressurized water reactor (PWR), which requires enriched uranium, as the future reactor type because of its economic advantage, but CEA wanted to continue developing the gas-cooled reactor (GCR) because of its independence in nuclear fuel supply. Finally, they chose PWR because a French enrichment facility was built in 1967. From such French history, we can say that the civilian and military use of nuclear technology are inseparable. (author)

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

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.)

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

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)

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

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

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.)

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)

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.)

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

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.)

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)

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.)

Dismantling of civilian nuclear powered fleet technical support vessels. engineering solutions - 59386

International Nuclear Information System (INIS)

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

2012-01-01

At the present time six nuclear technical support vessels are operated and maintained by Atomflot. Two of them (Volodarsky FTB (floating technical base) and Lepse FTB) were taken out of service for decommissioning and are stored afloat. One more vessel Lotta FTB should be decommissioned during next two years. The nuclear technological support ships carrying spent nuclear fuel (SNF), liquid and solid radioactive wastes (LRW and SRW) appear to be a possible radiation contamination of Murmansk region and Kola Bay because the Ship long-term storage afloat has the negative effect on hull's structures technical condition. As a result of this in the context of the Federal Program 'Nuclear and Radiation Safety' (2008-2015) NIPTB Onega OAO was engaged by state corporation Rosatom to develop the dismantling procedure for Volodarsky FTB and Lotta FTB. Before developing of nuclear technological support ships decommissioning projects the technical and economic assessment of decommissioning/dismantling was carried out. The following options were examined: - formation of module as one-piece Ship's hull for long-term storage at Saida Bay; - formation of separated modules for long-term storage at Saida Bay; - complete dismantling of hull's structures, systems and equipment with packing all generated SRW into certified long-term storage containers. This paper contains description of options, research procedure, comparative analysis of options of decommissioning and dismantling (D and D) of nuclear technological support ships and its difference with dismantling of nuclear submarine. On the basis of the technical and economic assessment of FTB D and D options the least expensive on the first D and D stage and the least duration option is the option 1 (Formation of module as one-piece Ship's hull for long-term storage at Saida Bay). By the implementation of the given option there will be the need of large areas for modules storage at Saida Bay. It was not considered while working out

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

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume II. Proliferation resistance

International Nuclear Information System (INIS)

1980-06-01

The purpose of this volume is limited to an assessment of the relative effects that particular choices of nuclear-power systems, for whatever reasons, may have on the possible spread of nuclear-weapons capabilities. This volume addresses the concern that non-nuclear-weapons states may be able to initiate efforts to acquire or to improve nuclear-weapons capabilities through civilian nuclear-power programs; it also addresses the concern that subnational groups may obtain and abuse the nuclear materials or facilities of such programs, whether in nuclear-weapons states (NWS's) or nonnuclear-weapons states (NNW's). Accordingly, this volume emphasizes one important factor in such decisions, the resistance of nuclear-power systems to the proliferation of nuclear-weapons capabilities

Personnel requirements, education, and training for civilian nuclear activities, 1984-2000

International Nuclear Information System (INIS)

Stevenson, W.

1984-10-01

This report provides projections of the employment of scientists, engineers, technicians, and other occupations for the civilian nuclear industry through the year 2000. Low, medium, and high projections are provided. In all cases, a substantial number of job openings are anticipated to fill needs created by employment growth, retirement, death, and occupational mobility. The expected adequacy of supply to fill these positions is assessed after taking into account projections of college enrollments and degrees along with competing labor demand from nuclear defense, defense waste management, weapons development, non-nuclear defense activities, and other highly technical industries. The likelihood for shortages is high in certain fields. Positions for engineers (particularly nuclear engineers), health physicists, health physics technicians, and electronics technicians will be the most difficult to fill

Cyber Norms for Civilian Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Spirito, Christopher

2016-11-01

The international community agrees that the safe operation of civilian nuclear infrastructure is in every population’s best interest. One challenge each government must address is defining and agreeing to a set of acceptable norms of behavior in cyberspace as they relate to these facilities. The introduction of digital systems and networking technologies into these environments has led to the possibility that control and supporting computer systems are now accessible and exploitable, especially where interconnections to global information and communications technology (ICT) networks exist. The need for norms of behavior in cyberspace includes what is expected of system architects and cyber defenders as well as adversaries who should abide by rules of engagement even while conducting acts that violate national and international laws. The goal of this paper is to offer three behavioral cyber norms to improve the overall security of the ICT and Operational Technology (OT) networks and systems that underlie the operations of nuclear facilities. These norms of behavior will be specifically defined with the goals of reducing the threats associated to the theft of nuclear materials, accidental release of radiation and sabotage of nuclear processes. These norms would also include instances where an unwitting attacker or intelligence collection entity inadvertently makes their way into a nuclear facility network or system and can recognize they are in a protected zone and an approach to ensuring that these zones are not exploitable by bad actors to place their sensitive cyber effect delivery systems.

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)

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

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.)

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

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

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)

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

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

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)

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)

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.)

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

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

Atoms for Peace (and War): US Forms of Influence on Italy's Civilian Nuclear Programs (1946-1964)

International Nuclear Information System (INIS)

Bini, Elisabetta

2017-01-01

This chapter analyzes the ways in which the United States influenced Italian civilian nuclear energy policies between the end of World War II and the mid-1960s. It argues that until the mid-1950s, when the United States developed its Atoms for Peace program, the US administration remained quite suspicious about Italy’s project to develop a civilian nuclear energy program. The State Department and the Atomic Energy Commission (AEC) kept firmly under control Italy’s efforts to extract uranium in the North of the country. Their greatest concern was that the Italian government might decide to declare its uranium resources property of the state, like it had done with its hydrocarbon resources. Despite a series of requests from Italian scientists and industrial firms, the Marshall Plan did not provide any funds for the purchase of nuclear equipment. In the context of the Atoms for Peace program and of the signing in 1955 of a bilateral agreement, the United States gained increased influence over Italy's atomic energy policies. Based on new archival sources from the United States and Italy, this chapter argues that after John F. Kennedy became President, and in the context of the so-called 'center-left governments', the US administration supported the expansion of Italy's nuclear program and a greater role of the state in promoting civilian nuclear energy programs. Once ENEL was founded, however, the company chose to rely on oil, rather than nuclear power, to fuel most of its electric plants. Following a series of agreements between Standard Oil (N.J.) and ENI, Italy received large quantities of cheap oil from the Middle East. ENEL's strategy was supported by American oil companies operating in Italy, and endorsed by the State Department as more cost-effective than a full-scale nuclear program. However, important sectors of the US administration remained critical of the rapid decline of Italy's civilian nuclear program, which accompanied

Review of the proposed Strategic National Plan for Civilian Nuclear Reactor Development: Volume 1

International Nuclear Information System (INIS)

1986-10-01

On August 9, 1985, the Secretary of Energy requested that the Chairman of the Energy Research Advisory Board establish an ad-hoc Panel to review a draft ''Strategic National Plan for Civilian Nuclear Reactor Development.'' The resulting report, approved by the Board, contains suggestions for improving the draft plan and also contains major recommendations for alleviating the several institutional barriers that appear to preclude the construction of any new nuclear power plants in this country

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.

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

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

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.)

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)

Historical overview of domestic spent nuclear fuel shipments in the United States

International Nuclear Information System (INIS)

Pope, R.B.; Wankerl, M.W.; Hamberger, C.R.; Schmid, S.P.

1993-01-01

The information in this paper summarized historical data on spent nuclear fuel shipments in the United States (U.S.) from the period from 1964 to 1991. Information on shipments has been developed to establish a basis for developing a transportation system in the U.S. for initiating shipments of spent nuclear fuel beginning in 1988. The paper shows that approximately 2700 power spent nuclear fuel rail and truck casks have been shipped within the U.S. during the past 28 years. In total, approximately 2000 metric tonnes of uranium (MTU) have been shipped to date, which compares with projected shipping rates of from 3000 to greater than 6000 MTU per year when the U.S. Civilian Radiation Waste Management System is in full operation. (author)

Historical overview of domestic spent nuclear fuel shipments in the United States

International Nuclear Information System (INIS)

Pope, R.B.; Wankerl, M.W.; Hamberger, C.R.; Schmid, S.P.

1992-01-01

The information in this paper summarizes historical data on spent nuclear fuel shipments in the United States (US) from the period from 1964 to 1991. Information on shipments has been developed to establish a basis for developing a transportation system in the US for initiating shipments of spent nuclear fuel beginning in 1998. The paper shows that approximately 2700 power reactor spent nuclear fuel rail and truck casks have been shipped within the US during the past 28 years. In total, approximately 2000 metric tonnes of uranium (MTU) have been shipped to date, which compares with projected shipping rates of from 3000 to greater than 6000 MM per year when the US Civilian Radioactive Waste Management System is in full operation

Civilian Nuclear Power. Appendices to a report to the President - 1962

International Nuclear Information System (INIS)

1962-01-01

Four recent estimates of the fossil fuel resources in the United States are used in the Report on Civilian Nuclear Power. They are not entirely independent estimates and, in particular, three of the estimates of coal resources have as their basis the data in 'Coal Reserves of the United States - A Progress Report, January 1, 1960,' Geological Survey Bulletin 1136. The total energy content of the various fossil fuel resources remaining in the United States as given by these estimates has been summarized.

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.)

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.)

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

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.)

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.)

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VII. International perspectives

Energy Technology Data Exchange (ETDEWEB)

1980-06-01

The purpose of this volume is to assess the proliferation vulnerabilities of the present deployment of civilian nuclear-power systems within the current nonproliferation regime and, in light of their prospective deployment, to consider technical and institutional measures and alternatives which may contribute to an improved regime in which nuclear power could play a significant part. An assessment of these measures must include consideration of their nonproliferation effectiveness as well as their bearing upon energy security, and their operational, economic, and political implications. The nature of these considerations can provide some measure of their likely acceptability to various nations.

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VII. International perspectives

International Nuclear Information System (INIS)

1980-06-01

The purpose of this volume is to assess the proliferation vulnerabilities of the present deployment of civilian nuclear-power systems within the current nonproliferation regime and, in light of their prospective deployment, to consider technical and institutional measures and alternatives which may contribute to an improved regime in which nuclear power could play a significant part. An assessment of these measures must include consideration of their nonproliferation effectiveness as well as their bearing upon energy security, and their operational, economic, and political implications. The nature of these considerations can provide some measure of their likely acceptability to various nations

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)

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)

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)

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

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

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.)

GA-4 and GA-9 legal weight truck shipping cask development

International Nuclear Information System (INIS)

Grenier, R.; Meyer, R.; Jensen, M.

1989-01-01

General Atomics (GA), under contract to the Idaho Operations Office of the U.S. Department of Energy, is developing two new legal weight truck spent fuel shipping casks that will carry four PWR or nine BWR spent fuel assemblies. They are being developed for the Office of Civilian Radioactive Waste Management (OCRWM) to meet its mission to dispose of nuclear wastes at a permanent disposal site. This paper discusses the primary goal, to maximize the number of fuel elements of each fuel type that a LWT cask can carry, while ensuring that the design meets all NRC licensing requirements

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.

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.

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)

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)

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

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.)

Working Group 7.1 on environmental transport, US-USSR Joint Coordinating Committee on Civilian Nuclear Reactor Safety

International Nuclear Information System (INIS)

Anspaugh, L.R.; Hendrickson, S.M.

1991-01-01

This report contains brief summaries of the status of projects of the Environmental Transport Group of the US-USSR Joint Coordinating Committee of Civilian Nuclear Reactor Safety. Projects reported on include: Management and Administration; Atmospheric Transport; Resuspension; External Dose; Terrestrial Food Chains; Aquatic Food Chains; Hydrological Transport; and Intercalibration

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)

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 ...

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)

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)

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

Protection of civilian nuclear installations in time of armed conflict

International Nuclear Information System (INIS)

Lamm, V.

2003-01-01

The inclusion of article 56 in Protocol 1 of the Geneva convention of 12 August 1949 represents a significant achievement in the development of international humanitarian law. Article 56 of protocol 1 reads as follow: firstly, works or installations containing dangerous forces, namely dams, dykes and nuclear electrical generating stations, shall not not be made the object of attack, even where these objects are military objectives, if such attack may cause the release of dangerous forces and consequent severe losses among the civilian population. Other military objectives located at or in the vicinity of these works or installations shall not be made the object of attack if such attack may cause the release of dangerous forces from the works or installations and consequent severe losses among the civilian population. Secondly, the special protection against attack provided by paragraph 1 shall cease: for a dam or a dyke only if it is used for other than its normal function and in regular, significant and direct support of military operations and if such attack is the only feasible way to terminate such support; for a nuclear electrical generating station only if it provides electric power in regular, significant and direct support of military operations and if such attack is the only feasible way to terminate such support;for other military objectives located at or in the vicinity of these works or installations only if they are used in regular, significant and direct support of military operations and if such attack is the only feasible way to terminate such support. Thirdly, in all cases, the civilian population and individual civilians shall remain entitled to all the protection accorded them by international law, including the protection of the precautionary measures provided for in article 57. If the protection ceases and any of the works, installations or military objectives mentioned in paragraph 1 is attacked, all practical precautions shall be taken to

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

Radiological protection of service and civilian personnel

International Nuclear Information System (INIS)

1990-01-01

Since the United Kingdom's defence nuclear industry was founded in the late 1940s, Service and civilian personnel have been exposed to ionising radiation. During the last forty years, as knowledge about the effects of radiation exposure has grown, concern to ensure adequate protection against exposure has also increased,. As part of our continuing scrutiny of the Ministry of Defence (MoD), we have undertaken a short inquiry to examine MoD's current and future policy and practice on radiological protection. The principal work involving exposure of Service and civilian personnel to significant levels of radiation falls into two discrete areas: the nuclear weapons programme and the nuclear propulsion programme. The nuclear weapons programme involves research, the production of nuclear warheads and their deployment with Her Majesty's Forces. The nuclear propulsion programme involves research, production, operation, refitting and decommissioning of pressurised water reactors as a source of propulsion power in Royal Navy submarines. These two nuclear programmes are not the only sources of ionising radiation within MoD's responsibility: it also arises from research, non-destructive testing and medical applications, most notably conventional radiography. In this Report we have concentrated upon ionising radiation arising from the two defence nuclear programmes. (author)

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

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

Nuclear science. U.S. electricity needs and DOE's civilian reactor development program

International Nuclear Information System (INIS)

England-Joseph, Judy; Allen, Robert E. Jr.; Fitzgerald, Duane; Young, Edward E. Jr.; Leavens, William P.; Bell, Jacqueline

1990-05-01

Electricity projections developed by the North American Electric Reliability Council (NERC) appear to be the best available estimates of future U.S. electricity needs. NERC, which represents all segments of the utility industry, forecasts that before 1998 certain regions of the country, particularly in the more heavily populated eastern half of the United States, may experience shortfalls during summer peak demand periods. These forecasts considered the utility companies' plans, as of 1989, to meet electricity needs during the period; these plans include such measures as constructing additional generators and conducting demand management programs. Working closely with the nuclear industry, DOE is supporting the development of several reactor technologies to ensure that nuclear power remains a viable electricity supply option. In fiscal year 1990, DOE's Civilian Reactor Development Program was funded at $253 million. DOE is using these funds to support industry-led efforts to develop light water reactors (LWR), advanced liquid-metal reactors (LMR), and modular high-temperature gas-cooled reactors (MHTGR) that are safe, environmentally acceptable, and economically competitive. The utility company officials we spoke with, all of whom were in the Southeast, generally supported DOE's efforts in developing these technologies. However, most of the officials do not plan to purchase nuclear reactors until after 2000 because of the high costs of constructing nuclear reactors and current public opposition to nuclear power

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

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.

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)

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)

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)

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.)

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.)

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

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)

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

Energy Research Advisory Board, Civilian Nuclear Power Panel: Subpanel 3 report, Institutional challenges: Volume IV

International Nuclear Information System (INIS)

1986-10-01

The Institutional Challenges Subpanel of the Energy Research Advisory Board's Civilian Nuclear Power Panel was charged with the task of addressing the institutional issues that affect the future of nuclear power in the United States. Barriers created by non-technical issues are generally considered to be primary obstacles to revitalizing the nuclear fission option as part of a robust supply for future electrical generation. The Subpanel examined the following categories of institutional issues: (1) Administration Policy and Leadership, (2) Licensing Reform, (3) Standardized Designs, (4) Shared Financial Risk, (5) State and Economic Regulation, (6) Waste Disposal, and (7) Public Perception. The Subpanel concluded that the Administration and Congress have the opportunity and responsibility to provide leadership in resolving these difficulties. The main report provides information on the background and current situation for each institutional issue and concludes with the set of recommendations for action

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.)

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

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)

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.)

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.

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

GA-4/GA-9 legal weight truck from reactor spent fuel shipping casks

International Nuclear Information System (INIS)

1990-04-01

The preliminary design report presents the results of General Atomics (GA) preliminary design effort to develop weight truck from reactor spent fuel shipping casks. The thermal evaluation of the Office of Civilian Radioactive Waste Management (OCRWM) cask considered normal and hypothetical accident conditions of transport. We employed analytical modeling as well as fire testing of the neutron shielding material to perform the evaluation. This document addresses the thermal design features of the cask, discusses thermal criteria, and summarizes the results of the thermal evaluation, as well as results of structural containment and nuclear evaluations that support the design. Also included are the results of trade-off studies. 69 refs., 103 figs., 76 tabs

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

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

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.)

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)

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)

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.

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.)

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

Utilization of nuclear power in oceans and its perspective

International Nuclear Information System (INIS)

Yamaji, Akio

2000-01-01

Since 1959, Russia retains many nuclear icebreakers and has a plan to construct two new types of nuclear icebreakers. In Japan, research for advanced marine reactors and its fundamental studies are being conducted by the Japan Atomic Energy Research Institute (JAERI), the Ship Research Institute (SRI) and universities. The advanced marine reactor MRX designed by JAERI is a lightweight and compact integral PWR with a passive decay heat removal system. The Shipbuilding Research Association of Japan (JSRA) and the Japan Atomic Industrial Forum (JAIF) took a survey of the future nuclear ships and conducted an investigation of the total system related to the operation of nuclear ships, respectively, commissioned by JAERI. The committee of JSRA has recommended the displacement type of a large high-speed container ship promises to act as the next generation nuclear merchant ship. In the committee of JAIF, the cost evaluation has been made for a high-speed, large container ship equipped with two MRXs sailing the Pacific Ocean, and it is found that it could have an advantage economically over the diesel in some future conditions. The committee of JSRA has also recommended the deep-sea research vessel has been identified as a promising form for the next generation nuclear special-purpose ship, since the deep-sea represents a vast frontier in terms of basic scientific understanding of the earth. Many countries including Russia, Japan and U.S.A. are conducting a research of reactors for deep-sea vessels. The U.S. Navy made available nuclear powered submarines for civilian oceanographic research and the submarines were used in the Scientific Ice Expedition (SCICEX) program from 1995 to 1999. For floating nuclear power plant, the design of nuclear co-generation plant Pevek' for remote regions of Russia is completed using KLT-40C, based on a marine reactor. In Japan, fundamental studies of floating plants are being performed by private companies and JAERI. The designs of floating

Utilization of nuclear power in oceans and its perspective

Energy Technology Data Exchange (ETDEWEB)

Yamaji, Akio [Ship Research Institute, Ministry of Transport, Mitaka, Tokyo (Japan)

2000-03-01

Since 1959, Russia retains many nuclear icebreakers and has a plan to construct two new types of nuclear icebreakers. In Japan, research for advanced marine reactors and its fundamental studies are being conducted by the Japan Atomic Energy Research Institute (JAERI), the Ship Research Institute (SRI) and universities. The advanced marine reactor MRX designed by JAERI is a lightweight and compact integral PWR with a passive decay heat removal system. The Shipbuilding Research Association of Japan (JSRA) and the Japan Atomic Industrial Forum (JAIF) took a survey of the future nuclear ships and conducted an investigation of the total system related to the operation of nuclear ships, respectively, commissioned by JAERI. The committee of JSRA has recommended the displacement type of a large high-speed container ship promises to act as the next generation nuclear merchant ship. In the committee of JAIF, the cost evaluation has been made for a high-speed, large container ship equipped with two MRXs sailing the Pacific Ocean, and it is found that it could have an advantage economically over the diesel in some future conditions. The committee of JSRA has also recommended the deep-sea research vessel has been identified as a promising form for the next generation nuclear special-purpose ship, since the deep-sea represents a vast frontier in terms of basic scientific understanding of the earth. Many countries including Russia, Japan and U.S.A. are conducting a research of reactors for deep-sea vessels. The U.S. Navy made available nuclear powered submarines for civilian oceanographic research and the submarines were used in the Scientific Ice Expedition (SCICEX) program from 1995 to 1999. For floating nuclear power plant, the design of nuclear co-generation plant Pevek' for remote regions of Russia is completed using KLT-40C, based on a marine reactor. In Japan, fundamental studies of floating plants are being performed by private companies and JAERI. The designs of

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)

Energies and media nr 25. Conditions for the nuclear sector. The Grenelle de l'Environnement. As well as: The civilian nuclear. Nuclear reactors and earthquakes. The Professor Pellerin's scientific rigour

International Nuclear Information System (INIS)

2007-12-01

This issue comments the conditions of the nuclear sector in a context of high oil prices and of high increase of CO 2 content in the atmosphere, of oil reserve shortage, and of China's demand on electricity. Thus, it comments the opportunities of development for AREVA and EDF in China and also in the United States, as well as the development of an international cooperation within the frame of the Global Nuclear Energy Partnership (GNEP). Then, it comments the content of the Grenelle de l'Environnement and of some interventions of the French president regarding the nuclear energy, alternative energies and energy savings. Other topics are briefly addressed: the civilian nuclear and its relationship with the Non proliferation Treaty (NPT), the consequences of an earthquake in Japan in July 2007 and some observations made on a Japanese nuclear power plant (incidents, earthquake amplitude greater than that used for the plant design, dangerous location), and the rigorous attitude of Professor Pellerin

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.)

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.)

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

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)

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

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.)

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.)

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)

Federal interim storage fee study for civilian spent nuclear fuel: a technical and economical analysis

International Nuclear Information System (INIS)

1983-07-01

This report describes the study conducted by the Department of Energy (the Department) regarding payment charges for the federal interim storage (FIS) of spent fuel and presents the details of the study results. It describes the selection of a methodology for calculating a FIS fee schedule, sets forth the estimates of cost for construction and operation of FIS facilities, provides a range of estimates for the fee for FIS services, and identifies special contractual considerations associated with providing FIS services to authorized users. The fee is structured for a range of spent fuel capacities because of uncertainties regarding the schedule of availability and amount of spent fuel that may require and qualify for FIS. The results set forth in the report were used as a basis for development of the report entitled Payment Charges for Federal Interim Storage of Spent Nuclear Fuel from Civilian Nuclear Power Plants in the United States, dated July 1983

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.)

Spanish regulatory perspective for the decommissioning of an old civilian nuclear research centre (CIEMAT)

International Nuclear Information System (INIS)

Gil, E.; Revilla, J.L.; Rodrigo, F.; Ortiz, J.

1999-01-01

The Center for Energy-related, Environmental and Technical Research (CIEMAT) is the main Spanish energy research center. CIEMAT is the heir of the former Nuclear Energy Board (Junta de Energia Nuclear - JEN), which was created in 1951 with a view to promoting the development and use of nuclear energy in Spain. Most of the centres for civilian nuclear research created in the fifties, like the JEN, had among their basic objectives to carry out investigations guided to the industrial development of the nuclear fuel cycle. The majority of them were endowed with experimental facilities that reproduced in a pilot scale the different stages of the full nuclear cycle facilities. The JEN main experimental facilities were: Plants for the treatment of uranium ores and for the concentration process; The manufacturing of fuel elements for research reactors; The JEN-1 thermal neutron experimental reactor, and CORAL fast reactor; The pilot plant for the treatment of irradiated fuel (M-1); The metallurgical hot cells for research relating to irradiated fuel; and Plants for the treatment and storage of liquid radioactive wastes. It should be pointed out that most of these installations were designed, built, operated, and even definitively shut down, prior a regulatory system as currently conceived is in force. The Science Act was passed in 1986, transforming the JEN into CIEMAT, and assigning to the latter a series of new functions, while making it the direct heir of the assets and strategic functions of its predecessor. The CIEMAT continued the process of 'denuclearization' of the installations inherited from the JEN, and used certain of them for the performance of research projects oriented towards the development of decontamination and dismantling techniques. (author)

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

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

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.)

Energy Research Advisory Board, Civilian Nuclear Power Panel: Subpanel 1 report, Light water reactor utilization and improvement: Volume 2

International Nuclear Information System (INIS)

1986-10-01

The Secretary of Energy requested that the Office of Nuclear Energy prepare a strategic national plan that outlines the Department's role in the future development of civilian nuclear power and that the Energy Research Advisory Board establish an ad hoc panel to review and comment on this plan. The Energy Research Advisory Board formed a panel for this review and three subpanels were formed. One subpanel was formed to address the institutional issues surrounding nuclear power, one on research and development for advanced nuclear power plants and a third subpanel on light water reactor utilization and improvement. The subpanel on light water reactors held two meetings at which representatives of the DOE, the NRC, EPRI, industry and academic groups made presentations. This is the report of the subpanel on light water reactor utilization and improvement. This report presents the subpanel's assessment of initiatives which the Department of Energy should undertake in the national interest, to develop and support light water reactor technologies

DOE reassesses civilian radioactive waste management program

International Nuclear Information System (INIS)

Yates, M.

1990-01-01

This article reports on the announcement by the Department of Energy (DOE) that the opening of a high-level radioactive nuclear waste repository site will be delayed for seven years. The article discusses DOE's reassessment plan, the restructuring of the Office of Civilian Radioactive Waste Management, site access and evaluation, the Monitored Retrievable Storage Commission proposal, and the industry's response

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

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.)

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.

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.

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

The analysis of the program to develop the Nuclear Waste Management System: Allocated requirements for the Office of Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

Woods, T.W.

1991-09-01

This report is volume 3, part B, of the program to satisfy the allocated requirements of the Office of Civilian Radioactive Waste Management Program, in the development of the nuclear waste management system. The report is divided into the following sections: regulatory compliance; external relations; international programs; strategic and contingency planning; contract business management; and administrative services. (CS)

Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume VII. International perspectives

International Nuclear Information System (INIS)

1979-12-01

The purpose of this volume is to assess the proliferation vulnerabilities of the present deployment of civilian nuclear-power systems within the current nonproliferation regime and, in light of their prospective deployment, to consider technical and institutional measures and alternatives which may contribute to an improved regime in which nuclear power could play a significant part. An assessment of these measures must include consideration of their nonproliferation effectiveness as well as their bearing upon energy security, and their operational, economic, and political implications. The nature of these considerations can provide some measure of their likely acceptability to various nations. While any final assessment of such measures and alternatives would have to examine the circumstances particular to each nation, it is hoped that the more generic assessments conducted here will be useful in suggesting guidelines for developing an improved nonproliferation regime which also helps to meet nuclear-energy needs. One chapter outlines the existing nonproliferation regime, including the Treaty for the Non-Proliferation of Nuclear Weapons (NPT), International Atomic Energy Agency (IAEA) safeguards, bilateral and multilateral requirements for agreements of cooperation and transfers of technology, and existing provisons for sanctions for violation of nonproliferation commitments. The chapter then proceeds to an assessment of various alternatives for providing assurance of fuel supply in light of this current regime. Another chapter examines a set of technical and institutional measures and alternatives for various components of once-through and closed fuel cycles. The components of the once-through fuel cycle assessed are enrichment services and spent-fuel management; the components of closed fuel cycles assessed are reprocessing and plutonium management and fast-breeder reactor (FBR) deployment

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.)

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.)

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.)

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.)

Radioactive wastes: a comparison of U.S. military and civilian inventories

International Nuclear Information System (INIS)

Krugmann, H.; von Hippel, F.

1977-01-01

Contrary to widespread belief, the accumulated inventory of fission products generated by the still small U.S. civilian nuclear power industry may already be comparable to that generated in the past by U.S. military nuclear programs. Although the volumes of the military wastes are very large, they are on the average almost 100 times more dilute than projected commercial high-level wastes

A strategic framework for proliferation resistance: a systematic approach for the identification and evaluation of technology opportunities to enhance the proliferation resistance of civilian nuclear energy systems

International Nuclear Information System (INIS)

Hassberger, J.A.; Isaac, T.; Schock, R.N.

2001-01-01

The United State Department of Energy Nuclear Energy Research Advisory Committee recently completed a study ''Technological Opportunities To Increase The Proliferation Resistance Of Global Civilian Nuclear Power Systems (TOPS)''. That effort included the development of a set of both intrinsic and extrinsic barriers to proliferation that technologies can directly impact. In this paper we will review these barriers as and framework for assisting in the evaluation of the relative proliferation resistance of various nuclear fuel cycles, technologies and alternatives. (author)

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.)

Operationalizing Civilian Protection in Mali: The Case for a Civilian Casualty Tracking, Analysis, and Response Cell

Directory of Open Access Journals (Sweden)

Marla B. Keenan

2013-06-01

Full Text Available This practice note details an emerging best practice of civilian harm mitigation in armed conflict: namely, the creation of civilian casualty tracking, analysis and response processes by a warring party or peace operation force. It asserts that in Iraq, Afghanistan and soon Somalia, these processes to better understand civilian harm and address consequences have positively shaped mission tactics, training, and overall operations. In both Iraq and Afghanistan, tracking and analysis has lead to a marked decrease in civilian casualties and facilitated the making of amends for any civilian losses. The paper argues that for warring parties to achieve their mission—particularly one with a protection of civilians mandate as with the United Nations Multidimensional Integrated Stabilization Mission in Mali (MINUSMA—they must fully understand the impact of their actions on the civilian population, positive or negative. For this reason, a Civilian Casualty Tracking, Analysis, and Response Cell should be created for MINUSMA to improve its ability mitigate risk to civilians as required by its Security Council mandate.

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.)

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

Tactic-operational problems of soldiers, civilians and environmental protection against contamination

International Nuclear Information System (INIS)

Krauze, M.

1994-01-01

The military problems connected with the probable use in warfare the chemical and nuclear weapon have been discussed. The concept of soldiers, civilians and environmental protection against the chemical and radiological contamination has been presented from the view point of military tactics

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

What is Wrong in Killing Civilians?

OpenAIRE

Majima, Shunzo

2009-01-01

In this article, we examine the status of civilians in the ethical context. For this purpose, we explore the ethical sources that address their status; specifically, we consider the ethical reasons that civilians should be protected in armed conflict by examining ethical concepts that could differentiate civilians from combatants and justify the protection of civilians. In order to assess how the status of civilians can be characterised and their protection justified by ethical concepts, we e...

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.)

How the radiologic and nuclear medical communities can improve nuclear security.

Science.gov (United States)

Kahn, Laura H; von Hippel, Frank

2007-04-01

Highly enriched uranium (HEU) is used to manufacture technetium-99m, the most widely used medical radioisotope in the world. Highly enriched uranium is also used to make nuclear bombs; 50 kg of HEU is enough to make a Hiroshima-type bomb. It is generally agreed that this technology is within the reach of a terrorist group; the main obstacle is acquiring HEU. Currently, as a legacy of the US and Soviet Atoms for Peace Program, there are civilian users of HEU in 40 countries, and about 1,000 kg are still being shipped each year. Unfortunately, the major international manufacturers of technetium-99m have been refusing to convert their production facilities to use low-enriched uranium (LEU), which cannot be used to make a nuclear bomb. Only 1% to 2% of the HEU is consumed in the process of producing technetium-99m. The remainder is accumulating in radioactive waste storage facilities. The radiologic and nuclear medical communities could make a tremendous contribution to a safer world by supporting the replacement of HEU with LEU in the production of technetium-99m. Low-enriched uranium is just as cost effective as HEU for the manufacture of technetium-99m and does not contribute to the risk for nuclear terrorism.

Nuclear waste

International Nuclear Information System (INIS)

1990-06-01

DOE estimates that disposing of radioactive waste from civilian nuclear power plants and its defense-related nuclear facilities could eventually end up costing $32 billion. To pay for this, DOE collects fees from utilities on electricity generated by nuclear power plants and makes payments from its defense appropriation. This report states that unless careful attention is given to its financial condition, the nuclear waste program is susceptible to future shortfalls. Without a fee increase, the civilian-waste part of the program may already be underfunded by at least $2.4 billion (in discounted 1988 dollars). Also, DOE has not paid its share of cost-about $480 million-nor has it disclosed this liability in its financial records. Indexing the civilian fee to the inflation rate would address one major cost uncertainty. However, while DOE intends to do this at an appropriate time, it does not use a realistic rate of inflation as its most probable scenario in assessing whether that time has arrived

Contribution of civilian industry to the management of military fissile materials

International Nuclear Information System (INIS)

Montalembert de, J.A.

2001-01-01

The situation about using of highly enriched uranium (HEU) and weapon grade plutonium (WgPu) for nuclear fuel preparation in U.S.A. and Russian Federation is reviewed. A few remarks were concluded: (1) We stand at the onset of a process that will be lengthy and which is unlikely to stop with the elimination of the 700 t of HEU and 2 x 34.5 t of WgPu concerned so far. If the announced negotiation of the third START treaty concludes favorably, additional tonnages will have to be recycled, particularly on the Russian side whose estimated inventory is larger. (2) The time scales necessitated by the management of these materials should be no surprise. On the one hand, the aim is to reduce an arsenal built up during 45 years of a Cold War. And this return to civilian life of materials of military origin must be achieved in conditions of safety and bilateral or international safeguards (IAEA), which obviously did not constitute the primary concern of the powers who produced them. Besides, insofar as it enlists the services of civilian industry, this return must be carried out with due respect for the equilibrium of markets that are severely mauled today, in other words, in an orderly and progressive manner. (3) Finally, it is important to recognize that without the contribution of the nuclear power industry, the elimination of military fissile materials would raise problems at another scale and would inevitably lead to regrettable waste. It is to be hoped that this will jog the minds of those who urge a rapid end to nuclear energy, when all the evidence demonstrates that the best way to eliminate surplus weapon grade materials is to recycle them in a reactor, in other words, to destroy them or to denature them while generating electricity. (4) The civilian nuclear industry is happy to contribute concretely and significantly to the solution of a problem of surplus nuclear weaponry, while at the same time utilizing technologies successfully developed for power generation

Comparing Civilian Support for Terrorism

Directory of Open Access Journals (Sweden)

Srobana Bhattacharya

2017-06-01

Full Text Available Terrorism is an extreme form of political violence, that is inherently abhorrent in nature. Yet, it continues to attain enough support to continue and survive. The recent proliferation of Islamic State and its ever increasing domestic and international civilian support base urges immediate attention to this question. While most research holds that provision of public goods by terrorist groups is the primary cause for high levels of civilian support, I argue that, terrorist groups are more interested in resource extraction rather than resource provision. Additionally, these studies pay scant attention to existing resource structure, especially territorial and political control to explain terrorist-civilian interaction. This paper emphasizes the bi-directional nature of this interaction – a. perception of civilians by the terrorist group and b. terrorist group’s perception of the civilians. To analyze levels of civilian support for terrorism, I compare fifteen terrorist groups using qualitative comparative analysis and show how territory, political competition, ethnicity, target selection and organizational structure combine to explain conditions that lead terrorist groups to include or exclude civilian population for support. Based on the variance in support networks of terrorist groups, counter-terrorism policies should also differ. High civilian support indicates the need to use non-military methods to decrease the appeal of terrorist groups. However, terrorist groups with more diffused and multiple support structures need more collaborative and coercive measures to intercept all the possible links to the main group.

Proceedings of the 1983 civilian radioactive waste management information meeting

International Nuclear Information System (INIS)

1984-02-01

This proceedings document from the 1983 Civilian Radioactive Waste Management Information Meeting serves to highlight developments since the passage of the Nuclear Policy Act of 1982 and reviews program activities necessary to provide for the permanent disposal and storage of commercially generated high-level radioactive waste. Presentations included in this program cover topics concerning interim spent fuel, monitored retrievable storage, geologic repository deployment as well as management of the Nuclear Waste Fund. Individual papers were abstracted for inclusion in the Energy Data Base

Status of United States civilian waste management program

International Nuclear Information System (INIS)

Lawrence, M.J.

1984-01-01

The Nuclear Waste Policy Act of 1982 confirms the Federal responsibility for nuclear waste management and provides for unprecedented involvement by States, Indian tribes and the public. The Act provides a comprehensive framework for disposing of spent nuclear fuel and high-level radioactive wastes of domestic origin generated by civilian nuclear power reactors. It establishes detailed schedules and procedures for selecting and developing geologic repositories; provides a mechanism for financing the cost of disposal; and sets forth other provisions relating to nuclear waste disposal. The other provisions of the Act include provision for a user-financed federal interim storage facility with time and quantity limitations, as well as strict Nuclear Regulatory Commission-prescribed eligibility criteria; a proposal for a Federally-owned and operated monitored retrievable storage (MRS) facility for the interim period prior to operation of a permanent repository; and provision for a Test and Evaluation Facility (TEF). This paper centers on the schedule and current status and siting of the first two geologic repositories

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)

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)

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)

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.

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)

Nuclear Fuel Cycle Information System. A directory of nuclear fuel cycle facilities. 2009 ed

International Nuclear Information System (INIS)

2009-04-01

The Nuclear Fuel Cycle Information System (NFCIS) is an international directory of civilian nuclear fuel cycle facilities, published online as part of the Integrated Nuclear Fuel Cycle Information System (iNFCIS: http://www-nfcis.iaea.org/). This is the fourth hardcopy publication in almost 30 years and it represents a snapshot of the NFCIS database as of the end of 2008. Together with the attached CD-ROM, it provides information on 650 civilian nuclear fuel cycle facilities in 53 countries, thus helping to improve the transparency of global nuclear fuel cycle activities

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

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.

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)

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)

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)

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)

On the future of civilian plutonium: An assessment of technological impediments to nuclear terrorism and proliferation

Science.gov (United States)

Avedon, Roger Edmond

This dissertation addresses the value of developing diversion- and theft-resistant nuclear power technology, given uncertain future demand for nuclear power, and uncertain risks of nuclear terrorism and of proliferation from the reprocessing of civilian plutonium. The methodology comprises four elements: Economics. An economic growth model coupled with market penetration effects for plutonium and for the hypothetical new technology provides a range of estimates for future nuclear demand. A flow model accounts for the longevity of capital assets (nuclear plants) over time. Terrorism. The commercial nuclear fuel cycle may provide a source of fissile material for terrorists seeking to construct a crude nuclear device. An option value model is used to estimate the effects of the hypothetical new technology on reducing the probability of theft. A game theoretic model is used to explore the deterrence value of physical security and then to draw conclusions about how learning on the part of terrorists or security forces might affect the theft estimate. The principal uncertainties in the theft model can be updated using Bayesian techniques as new data emerge. Proliferation. Access to fissile material is the principal technical impediment to a state's acquisition of nuclear weapons. A game theoretic model is used to determine the circumstances under which a state may proliferate via diversion. The model shows that the hypothetical new technology will have little value for counter-proliferation if diversion is not a preferred proliferation method. A technology policy analysis of the choice of proliferation method establishes that diversion is unlikely to be used because it has no constituency among the important parties to the decision, namely the political leadership, the scientific establishment, and the military. Value. The decision whether to develop a diversion- and theft-resistant fuel cycle depends on the perceived value of avoiding nuclear terrorism and proliferation

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

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)

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

Agreement between the Government of India and the International Atomic Energy Agency for the application of safeguards to civilian nuclear facilities

International Nuclear Information System (INIS)

2009-01-01

The text of the Agreement between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities is reproduced in this document for the information of all Members of the Agency. The Board of Governors approved the Agreement on 1 August 2008. It was signed in Vienna on 2 February 2009. Pursuant to paragraph 108 of the Agreement, the Agreement entered into force on 11 May 2009, the date on which the Agency received from India written notification that India's statutory and constitutional requirements for entry into force had been met

Military Versus Civilian Murder-Suicide.

Science.gov (United States)

Patton, Christina L; McNally, Matthew R; Fremouw, William J

2015-07-03

Previous studies have implicated significant differences between military members and civilians with regard to violent behavior, including suicide, domestic violence, and harm to others, but none have examined military murder-suicide. This study sought to determine whether there were meaningful differences between military and civilian murder-suicide perpetrators. Using data from the Center for Disease Control's (CDC) National Violent Death Reporting System (NVDRS), military (n = 259) and civilian (n = 259) murder-suicide perpetrators were compared on a number of demographic, psychological, and contextual factors using chi-square analyses. Logistic regression was used to determine which variables predicted membership to the military or civilian perpetrator groups. Military murder-suicide perpetrators were more likely to be older, have physical health problems, be currently or formerly married, less likely to abuse substances, and to exhibit significantly different motives than civilian perpetrators. Logistic regression revealed that membership to the military, rather than the civilian, perpetrator group was predicted by age, physical health problems, and declining heath motive-reflecting the significance of a more than 15-year difference in mean age between the two groups. Findings point to the need to tailor suicide risk assessments to include questions specific to murder-suicide, to assess attitudes toward murder-suicide, and to the importance of assessing suicide and violence risk in older adult military populations. © The Author(s) 2015.

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)

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)

Civilian protection and Britain's commercial nuclear installations

International Nuclear Information System (INIS)

1981-01-01

The subject is treated as follows: initial conclusions (major nuclear attack on military installations; nuclear attack including civil nuclear targets; conventional attack on civil nuclear installations); nature of nuclear weapons explosions and power reactor releases (general; dose effects and biologically significant isotopes; nuclear weapon effects; effect of reactors and other fuel-cycle installations in a thermonuclear area; implications of reactor releases due to conventional attack, sabotage, civil disorder or major accident). (U.K.)

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.

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)

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

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

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)

Communication received from the Governor of Norway to the Agency concerning the International Symposium of Minimisation of Highly Enriched Uranium in the Civilian Nuclear Sector

International Nuclear Information System (INIS)

2006-01-01

The Director General has received a communication from the Governor of Norway, attaching the Chair's Summary of the discussions held during the International Symposium of Minimisation of Highly Enriched Uranium in the Civilian Nuclear Sector which was held in Oslo from 17 to 20 June 2006 as well as the summary from the technical workshop of the Symposium. The communication and, as requested therein, the attached two summaries, are herewith circulated for the information of Member States

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

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

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)

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)

Management systems improvement strategy for the Office of Civilian Radioactive Waste Management

International Nuclear Information System (INIS)

Shelor, D.E.

1991-01-01

To achieve the goal of permanent disposal of spent nuclear fuel and high-level radioactive waste, the US DOE's Office of Civilian Radioactive Waste Management (OCRWM) is implementing a Management Systems Improvement Strategy (MSIS). This MSIS is structured around the systems engineering approach that separates the program mission into system and programmatic functions. OCRWM believes that this strategy will significantly improve the program and provide the framework needed to ensure successful implementation of the activities necessary to fulfill the mandate of the Nuclear Waste Policy Act, as amended

Avoiding dual regulation of the Civilian Radioactive Waste Management Program

International Nuclear Information System (INIS)

Vlahakis, J.G.; Palabrica, R.J.

1994-01-01

The Office of Civilian Radioactive Waste Management (RW) has successfully negotiated the issuance of a Department of Energy (DOE) Headquarters Order that provides for exemption of RW from certain DOE directives. This exemption assures precedence of Nuclear Regulatory Commission (NRC) requirements in radiation protection, nuclear safety (including quality assurance), and safeguards and security of nuclear materials. This Order is necessary to avoid the unwarranted cost and potential confusion resulting from dual regulation of RW facilities and activities by DOE and NRC. Development of this Order involved a systematic review of applicable DOE directives and NRC requirements to identify potential overlaps and duplication when applied to the RW program. Following this review and extensive negotiations with appropriate DOE organizations responsible for directives development, this Order was issued as HQ 1321.1 on December 22, 1993

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.

Invisible nuclear; converting nuclear

International Nuclear Information System (INIS)

Park, Jongmoon

1993-03-01

This book consists of 14 chapters which are CNN era and big science, from East and West to North and South, illusory nuclear strategy, UN and nuclear arms reduction, management of armaments, advent of petroleum period, the track of nuclear power generation, view of energy, internationalization of environment, the war over water in the Middle East, influence of radiation and an isotope technology transfer and transfer armament into civilian industry, the end of nuclear period and the nuclear Nonproliferation, national scientific and technological power and political organ and executive organ.

Nuclear energy fur civilian uses given the prospects of a changing climate; L'energie nucleaire civile dans le cadre temporel des changements climatiques

Energy Technology Data Exchange (ETDEWEB)

Dautray, R. [Academy des Aciences, 75 - Paris (France); Turpin, M. [ERAP, 75 - Paris (France)

2003-01-01

The worrisome issues resulting from the civilian use of nuclear energy are subjected to a scientific analysis in R. Dautray's report. They include: the risks of accidents and radiation, the question of nuclear wastes (in particular, plutonium and actinides), and the dangers of atomic weapons proliferating or nuclear plants being menaced by terrorists. The nuclear industry will not be able to go on unless it comes up with solutions acceptable to citizens. Even if the decision were made to put an end to nuclear power plants, a solution would have to be found for putting an end to the aftereffects. According to this report, it is indispensable to have a base of knowledge accepted by all if we are to weigh various proposals and make decisions. It contends that the program under way in France since the 1991 Bataille Act should, for the 2006 deadline, set as its main objective to define 'a general criterion of protection and confidence of the concerned workers and populations, a criterion worked out by their elected representatives, thus by public authorities'. The report's author has proposed points for drawing up such a criterion. (author)

Nuclear Italy. An International history of Italian Nuclear Policies during the Cold War

International Nuclear Information System (INIS)

Bini, Elisabetta; Londer, Igor

2017-01-01

This book examines the history of Italy’s nuclear policies during the Cold War, by placing the Italian case in an international and comparative framework. It highlights the importance the international context had in shaping the country’s specific experience, and analyzes the ways in which international politics and economics, technological and scientific exchanges, as well as social and cultural movements, influenced Italian nuclear policies, both civilian and military. All the essays published in this volume assume that the history of nuclear energy should be written by adopting an international perspective. The spread of nuclear knowledge (scientific, civilian, as well as military), and the implementation of nuclear policies, have a specific international dimension that should be taken into consideration, since no nuclear program has ever had a distinctly national character, and every country pursuing a nuclear policy has been, in one way or another, deeply influenced by the international context.

Inter-modal Transportation of Spent Nuclear Fuel from Office of Civilian Radioactive Waste Management Sites

International Nuclear Information System (INIS)

Schmid, St.; Thrower, A.; Best, R.E.

2009-01-01

U.S. Department of Energy (DOE) plans to ship most commercial spent nuclear fuel (SNF) by rail in sealed transportation, aging and disposal (TAD) canisters. Based on current and projected dry SNF storage programs, DOE believes the majority of commercial nuclear sites would have the capacity to load and prepare large-capacity, canister-based dry storage canisters such as the proposed TAD systems. Thus, only a small fraction of SNF, such as odd lots and SNF not meeting TAD criteria, is projected for truck (highway) shipment. However, at some commercial facilities rail tracks do not extend to the site, or on-site rail does not extend to the site's proposed loading spot, and inter-modal transfers will be required. Advance coordination between DOE and commercial site operators, commercial carriers, specialized carriers and riggers, and state, tribal and local routing officials will be necessary to establish inter-modal transfer areas and obtain necessary permits to move heavy loads over highways. Although inter-modal transfers can involve a number of steps and several different entities acting in close coordination, such moves are commonly performed by industry and the system requirements are well-understood. (authors)

Nuclear terrorism - an unavoidable companion of nuclear fission?

International Nuclear Information System (INIS)

Mueller, H.

1989-01-01

Comparing the security measures provided for with regard to nuclear weapons or to the nuclear inventory of the civilian fuel cycle, it is shown that there are significantly lower standards applied to the storage, processing, and transport of the radioactive fuel material. The difference becomes most obvious when looking at the planning horizons of those responsible for the security measures. The NATO institutions establish their system of security measures on the basis of a dynamical 'threat analysis' reaching far into the future. In the civilian sector, risk analyses and the deduced security measures are well lagging behind the development of realistic risk scenarios. This makes life easier for the operators of nuclear fuel cycle facilities, who otherwise would be obliged to continuously backfit their installations. The cost advantage on the operator's part, however, is obtained at the expense of security. (orig./HSCH) [de

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

Nuclear questions

International Nuclear Information System (INIS)

Berg, Eugene

2012-01-01

Civilian and military nuclear questions fill a multitude of publications these days, especially after the Japanese tsunami and the Fukushima disaster. The author analyses some of them and highlights the links between civil and military nuclear industries, the realities of the nuclear cycle and related industrial questions before concluding on the controversial issue of weapons and their proliferation potential

Management of civilian ballistic fractures.

Science.gov (United States)

Seng, V S; Masquelet, A C

2013-12-01

The management of ballistic fractures, which are open fractures, has often been studied in wartime and has benefited from the principles of military surgery with debridement and lavage, and the use of external fixation for bone stabilization. In civilian practice, bone stabilization of these fractures is different and is not performed by external fixation. Fifteen civilian ballistic fractures, Gustilo II or IIIa, two associated with nerve damage and none with vascular damage, were reviewed. After debridement and lavage, ten internal fixations and five conservative treatments were used. No superficial or deep surgical site infection was noted. Fourteen of the 15 fractures (93%) healed without reoperation. Eleven of the 15 patients (73%) regained normal function. Ballistic fractures have a bad reputation due to their many complications, including infections. In civilian practice, the use of internal fixation is not responsible for excessive morbidity, provided debridement and lavage are performed. Civilian ballistic fractures, when they are caused by low-velocity firearms, differ from military ballistic fractures. Although the principle of surgical debridement and lavage remains the same, bone stabilization is different and is similar to conventional open fractures. Copyright © 2013 Elsevier Masson SAS. All rights reserved.

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

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)

32 CFR 700.320 - The Civilian Executive Assistants.

Science.gov (United States)

2010-07-01

... the Navy. (b) Each Civilian Executive Assistants, within his or her assigned area of responsibility... 32 National Defense 5 2010-07-01 2010-07-01 false The Civilian Executive Assistants. 700.320... of the Navy The Office of the Secretary of the Navy/the Civilian Executive Assistants § 700.320 The...

32 CFR 191.7 - Civilian EEO program staff.

Science.gov (United States)

2010-07-01

... 32 National Defense 2 2010-07-01 2010-07-01 false Civilian EEO program staff. 191.7 Section 191.7...) MISCELLANEOUS THE DOD CIVILIAN EQUAL EMPLOYMENT OPPORTUNITY (EEO) PROGRAM § 191.7 Civilian EEO program staff. (a) EEO Managers, including SEP Managers and other staff who are responsible for EEO and affirmative...

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.)

Air Force Civilian Senior Leadership Development Challenges

National Research Council Canada - National Science Library

Webb, Billy P

2008-01-01

.... While Gen Jumper's sight picture recognizes the need to grow civilians for leadership positions, there is a more compelling reason for the Air Force to focus on civilian leadership development...

Civilian radioactive waste management program plan. Revision 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy`s site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program`s ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program`s mission and vision, and summarizes the Program`s broad strategic objectives. Chapter 2 describes the Program`s approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program`s organization chart; the Commission`s regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms.

Civilian radioactive waste management program plan. Revision 2

International Nuclear Information System (INIS)

1998-07-01

This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy's site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program's ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program's mission and vision, and summarizes the Program's broad strategic objectives. Chapter 2 describes the Program's approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program's organization chart; the Commission's regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms

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.)

Nuclear weapons research in Sweden. The co-operation between civilian and military research, 1947 - 1972

International Nuclear Information System (INIS)

Jonter, Thomas

2002-05-01

The Swedish nuclear weapons research began as early as 1945, shortly after the first atomic bombs fell over Japan. The assignment to look into the new weapon of mass destruction went to the Swedish National Defence Research Establishment (FOA). Admittedly, the main aim of the research initiated at that time was to find out how Sweden could best protect itself against a nuclear weapon attack. However, from the outset FOA was interested in investigating the possibilities of manufacturing what was then called an atomic bomb. A co-operation between FOA and AB Atomenergi (AE), which was created in 1947 in order to be responsible for the industrial development of civilian nuclear energy, was initiated. AE made several technical investigations within this co-operation regarding choice of reactors and preconditions for a production of weapons-grade plutonium. The first purpose of this report is therefore to investigate how this co-operation emerged and what consequences it had for the project to produce basic information for the Swedish manufacture of nuclear weapons. In general terms, the finding of this report is that FOA was responsible for the overall nuclear weapons research. For this reason, FOA was in charge of the construction of the nuclear device and the studies of its effects. Additionally, AE should deliver basic information of a possible production of weapons-grade plutonium and investigate the possibilities of a production or a procurement of inspection-free heavy water (i.e. without inspections by the supplying country). AE should also build a reprocessing plant and manufacture fuel elements to be used in the reactors for a production of weapons-grade plutonium. Furthermore, it is important to emphasise that both FOA and AE conducted plutonium research. The reason why FOA conducted this research was that the plutonium had to be in metallic form in order to be used in a nuclear weapons device. Therefore, FOA carried out research with the purpose of producing

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.)

20 CFR 609.20 - Information to Federal civilian employees.

Science.gov (United States)

2010-04-01

... UNEMPLOYMENT COMPENSATION FOR FEDERAL CIVILIAN EMPLOYEES Responsibilities of Federal Agencies § 609.20 Information to Federal civilian employees. Each Federal agency shall: (a) Furnish information to its employees... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Information to Federal civilian employees...

Site and facility waste transportation services planning documents

International Nuclear Information System (INIS)

Ratledge, J.E.; Schmid, S.; Danese, L.

1991-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) will eventually ship Purchasers' (10 CFR 961.3) spent nuclear fuel from approximately 122 commercial nuclear facilities. The preparation and maintenance of Site- and Facility-Specific Transportation Services Planning Documents (SPDs) and Site-Specific Servicing Plans (SSSPs) provides a focus for advanced planning and the actual shipping of waste, as well as the overall development of transportation requirements for the waste transportation system. SPDs will be prepared for each of the affected nuclear waste facilities, with initial emphasis on facilities likely to be served during the earliest years of the Federal Waste Management System (FWMS) operations

Technical bases for OCRWM's [Office of Civilian Radioactive Waste Management] policy decisions on international safeguards

International Nuclear Information System (INIS)

Sprecher, W.M.

1989-01-01

The purpose of this paper is to discuss the technical factors that contributed to the formulation of the international safeguards policy enunciated in September 1988 by the U.S. Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM), which is the federal organization responsible for the implementation of the Nuclear Waste Policy Act of 1982, as amended

The Nuclear Department, Royal Naval School of Marine Engineering - Provision of nuclear education and training to the naval nuclear propulsion programme and beyond

International Nuclear Information System (INIS)

Trethewey, K.R.; Beeley, P.A.; Lockwood, R.S.; Harrop, I.

2004-01-01

The Nuclear Department at HMS SULTAN provides education, training and research support to the Royal Navy Nuclear Propulsion Programme, as well as a growing number of civilian programmes within the wider British nuclear industry. As an aspiring centre of excellence in nuclear engineering, the Department will play an important role as a repository of nuclear knowledge for the foreseeable future. (author)

Department of Energy mission plan for the civilian radioactive waste management program

International Nuclear Information System (INIS)

Shaw, G.H.

1988-01-01

Volume I is the Mission Plan itself, Volume II is a 700+-page collection of public comments on the Draft Mission Plan, and Volume III contains DOE responses to the public comments. Taken as a whole, the document illustrates the development of an agency approach to solving a problem, and the extent to which public input may or may not influence that approach. The Mission Plan itself is DOE's clear statement of how it proposes to go about selecting a permanent site for the disposal of high-level nuclear waste: spent fuel from civilian nuclear power plants and high-level waste produced in reprocessing both civilian and military nuclear materials. Since this program is focused upon site selection based to a large extent upon geologic factors important in inhibiting the release of radionuclides for a long interval of time, it is of considerable interest to see how DOE has organized the necessary geologic investigations, and to what extent it proposes to concentrate on the geologic aspects. A key element in the high-level waste disposal program is public confidence in the process. If the public perceives that DOE is continuing investigations at one or more sites when substantial evidence shows that the site(s) are not geologically favorable, then public confidence in the program will disappear. It remains to be seen whether this Mission Plan will be considered the planning document for a successful, carefully organized program of geological input to public policy or merely an element in a record of bureaucratic failure

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

Nuclear weapons research in Sweden. The co-operation between civilian and military research, 1947 - 1972

Energy Technology Data Exchange (ETDEWEB)

Jonter, Thomas [Uppsala Univ. (Sweden). Dept. of History

2002-05-01

The Swedish nuclear weapons research began as early as 1945, shortly after the first atomic bombs fell over Japan. The assignment to look into the new weapon of mass destruction went to the Swedish National Defence Research Establishment (FOA). Admittedly, the main aim of the research initiated at that time was to find out how Sweden could best protect itself against a nuclear weapon attack. However, from the outset FOA was interested in investigating the possibilities of manufacturing what was then called an atomic bomb. A co-operation between FOA and AB Atomenergi (AE), which was created in 1947 in order to be responsible for the industrial development of civilian nuclear energy, was initiated. AE made several technical investigations within this co-operation regarding choice of reactors and preconditions for a production of weapons-grade plutonium. The first purpose of this report is therefore to investigate how this co-operation emerged and what consequences it had for the project to produce basic information for the Swedish manufacture of nuclear weapons. In general terms, the finding of this report is that FOA was responsible for the overall nuclear weapons research. For this reason, FOA was in charge of the construction of the nuclear device and the studies of its effects. Additionally, AE should deliver basic information of a possible production of weapons-grade plutonium and investigate the possibilities of a production or a procurement of inspection-free heavy water (i.e. without inspections by the supplying country). AE should also build a reprocessing plant and manufacture fuel elements to be used in the reactors for a production of weapons-grade plutonium. Furthermore, it is important to emphasise that both FOA and AE conducted plutonium research. The reason why FOA conducted this research was that the plutonium had to be in metallic form in order to be used in a nuclear weapons device. Therefore, FOA carried out research with the purpose of producing

Proliferation and the Civilian Nuclear Fuel Cycle. Towards a Simplified Recipe to Measure Proliferation Risk

Energy Technology Data Exchange (ETDEWEB)

Brogli, R.; Krakowski, R.A

2001-08-01

The primary goal of this study is to frame the problem of nuclear proliferation in the context of protection and risks associated with nuclear materials flowing in the civilian nuclear fuel cycle. The perspective adopted for this study is that of a nuclear utility and the flow of fresh and spent nuclear fuel with which that utility must deal in the course of providing economic, safe, and ecologically acceptable electrical power to the public. Within this framework quantitative approaches to a material-dependent, simplified proliferation-risk metric are identified and explored. The driving force behind this search for such a proliferation metric derives from the need to quantify the proliferation risk in the context of evaluating various commercial nuclear fuel cycle options (e.g., plutonium recycle versus once-through). While the formulation of the algebra needed to describe the desired, simplified metric(s) should be straight forward once a modus operandi is defined, considerable interaction with the user of any final product that results is essential. Additionally, a broad contextual review of the proliferation problem and past efforts in the quantification of associated risks was developed as part of this study. This extensive review was essential to setting perspectives and establishing (feasibility) limits to the search for a proliferation metric(s) that meets the goals of this study. Past analyses of proliferation risks associated with the commercial nuclear fuel cycle have generally been based on a range of decision-analysis, operations-research tools. Within the time and budget constraints, as well as the self-enforced (utility) customer focus, the more subjective and data-intensive decision-analysis methodologies where not pursued. Three simplified, less-subjective approaches were investigated instead: a) a simplified 'four-factor' formula expressing as a normalized product political, material-quantity, material-quality, and material

Proliferation and the Civilian Nuclear Fuel Cycle. Towards a Simplified Recipe to Measure Proliferation Risk

International Nuclear Information System (INIS)

Brogli, R.; Krakowski, R.A.

2001-08-01

The primary goal of this study is to frame the problem of nuclear proliferation in the context of protection and risks associated with nuclear materials flowing in the civilian nuclear fuel cycle. The perspective adopted for this study is that of a nuclear utility and the flow of fresh and spent nuclear fuel with which that utility must deal in the course of providing economic, safe, and ecologically acceptable electrical power to the public. Within this framework quantitative approaches to a material-dependent, simplified proliferation-risk metric are identified and explored. The driving force behind this search for such a proliferation metric derives from the need to quantify the proliferation risk in the context of evaluating various commercial nuclear fuel cycle options (e.g., plutonium recycle versus once-through). While the formulation of the algebra needed to describe the desired, simplified metric(s) should be straight forward once a modus operandi is defined, considerable interaction with the user of any final product that results is essential. Additionally, a broad contextual review of the proliferation problem and past efforts in the quantification of associated risks was developed as part of this study. This extensive review was essential to setting perspectives and establishing (feasibility) limits to the search for a proliferation metric(s) that meets the goals of this study. Past analyses of proliferation risks associated with the commercial nuclear fuel cycle have generally been based on a range of decision-analysis, operations-research tools. Within the time and budget constraints, as well as the self-enforced (utility) customer focus, the more subjective and data-intensive decision-analysis methodologies where not pursued. Three simplified, less-subjective approaches were investigated instead: a) a simplified 'four-factor' formula expressing as a normalized product political, material-quantity, material-quality, and material-protection metrics; b

Nuclear fuel cycle assessment of India: A technical study for U.S.-India cooperation

Science.gov (United States)

Krishna, Taraknath Woddi Venkat

The recent civil nuclear cooperation proposed by the Bush Administration and the Government of India has heightened the necessity of assessing India's nuclear fuel cycle inclusive of nuclear materials and facilities. This agreement proposes to change the long-standing U.S. policy of preventing the spread of nuclear weapons by denying nuclear technology transfer to non-NPT signatory states. The nuclear tests in 1998 have convinced the world community that India would never relinquish its nuclear arsenal. This has driven the desire to engage India through civilian nuclear cooperation. The cornerstone of any civilian nuclear technological support necessitates the separation of military and civilian facilities. A complete nuclear fuel cycle assessment of India emphasizes the entwinment of the military and civilian facilities and would aid in moving forward with the separation plan. To estimate the existing uranium reserves in India, a complete historical assessment of ore production, conversion, and processing capabilities was performed using open source information and compared to independent reports. Nuclear energy and plutonium production (reactor- and weapons-grade) was simulated using declared capacity factors and modern simulation tools. The three-stage nuclear power program entities and all the components of civilian and military significance were assembled into a flowsheet to allow for a macroscopic vision of the Indian fuel cycle. A detailed view of the nuclear fuel cycle opens avenues for technological collaboration. The fuel cycle that grows from this study exploits domestic thorium reserves with advanced international technology and optimized for the existing system. To utilize any appreciable fraction of the world's supply of thorium, nuclear breeding is necessary. The two known possibilities for production of more fissionable material in the reactor than is consumed as fuel are fast breeders or thermal breeders. This dissertation analyzes a thermal

Reacting to Conflict: Civilian Capabilities in the EU, UN and OSCE

NARCIS (Netherlands)

Dijkstra, Hylke; Petrov, Petar; Mahr, Ewa

2016-01-01

This report analyses how the EU, UN and OSCE make resources available for civilian missions. It starts with an overview of civilian missions around the world before comparing civilian planning and conduct procedures in these international organisations. The report zooms in on EU civilian

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)

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.)

Nuclear waste: How the issue falls out

International Nuclear Information System (INIS)

Garner, W.L.

1995-01-01

Unless Congress takes some action, utilities will be forced to provide onsite storage of spent fuel from civilian nuclera reactors much longer than they ever imagined. Congress's failure to authorize the Department of Energy (DOE) to begin planning a centralized, interim storage facility and, equally important, to accelerate development of a permanent repository, means that spent nuclear fuel will remain in limbo at 73 reactor sites in 34 states. Today's 30,000 metric tons of spent fuel from civilian nuclear plants will grow to 85,000 metric tons by 2033, according to DOE. The agency also must find a home for a future 70,000 tons of defense waste. There is a growing sense of urgency in Congress this year that something must be done about the nation's nuclear waste problem. By 1998, 26 civilian nuclear units will have exhausted their storage capacity. By 2010 - the earliest DOE says it could open a permanent repository at Yucca Mountain in Nevada, provided the site proves feasible - 80 nuclear units will be out of storage space. At least half a dozen bills have been introduced so far in the 104th Congress, by both propoents and opponents of nuclear power. Recent events in Washington suggest this will be a hard-fought battle

Command and Control of Civilian Contract Manned Navy Fleet Support and Military Sealift Command Ships.

Science.gov (United States)

1983-12-01

58 APPENDIX B: COVER LEITERS RxErV FRC4 LABOR AND SHIPPING ORGANIZATINS ................................ 70 LIST CF...result of a merger between the Coast Seamen’ s Union and the Pacific Steamship Sailors’ Union. The SUP was under the leadership of Mr. Andrew Furuseth... leadership to emerge on the West Coast. As this emerging leadership tried to make new gains on the East Coast, it began to cme in conflict with the old-line

Exploring Quantitative Framework to Evaluate Nuclear Transparency

International Nuclear Information System (INIS)

Ha, Jeemin; Yim, Mansung; Park, Hyeon Seok

2014-01-01

In this work, a definition of nuclear transparency is elaborated and ways to represent a country's nuclear transparency are examined. For evaluating nuclear transparency, it is necessary to define three elements first; an information seeker who wants to see, an information seek whom an information seeker wants to see, and information related to nuclear materials and activities. The States with high capacity of civilian nuclear power had a tendency to follow IAEA safeguards agreements well. And it means that their levels of the transparency are relatively high. Besides, the data of international assurances is one of the good indicators to confirm States' transparency. The current study explored the use of two measures, IAEA safeguards and voluntary reporting as a way to represent nuclear transparency. Using these measures seemed to agree with the notion that nuclear transparency is important in the success of civilian nuclear power development

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)

Civilian Aeronautical Futures - The Responsibly Imaginable

Science.gov (United States)

Bushnell, Dennis M.

2006-01-01

Since 1940 Aeronautics has had an immense impact upon Global Human lifestyles and affairs - in both the Civilian and Military arenas. During this period Long distance Train and Ship passenger transport were largely supplanted by Air Travel and Aviation assumed a dominant role in warfare. The early 1940 s to the mid 1970 s was a particularly productive period in terms of Aeronautical Technology. What is interesting is that, since the mid 1970 s, the rate of Aeronautical Technological Progress has been far slower, the basic technology in nearly all of our current Aero Systems dates from the mid 70 s or earlier. This is especially true in terms of Configuration Aerodynamics, Aeronautics appears to have "settled" on the 707, double delta and rotary wing as the approach of choice for Subsonic long haul, supersonic cruise and VTOL respectively. Obviously there have been variants and some niche digression from this/these but in the main Aeronautics, particularly civilian Aeronautics, has become a self-professed "mature", Increasingly "Commodity", Industry. The Industry is far along an existing/deployed technology curve and focused, now for decades, on incremental/evolutionary change - largely Appliers vs. developers of technology. This is, of course, in sharp contrast to the situation in the early-to-later 20th century where Aeronautics was viewed as A Major Technological Engine, much the way IT/Bio/Nano/Energetics/Quantum Technologies are viewed today. A search for Visionary Aeronautical "Futures" papers/projections indicates a decided dearth thereof over the last 20 plus years compared to the previous quarter Century. Aeronautics is part of Aerospace and Aerospace [including Aeronautics] has seen major cutbacks over the last decades. Some numbers for the U.S. Aerospace Industry serve as examples. Order of 600,000 jobs lost, with some 180,000 more on the block over the next 10 years. Approximately 25% of the Aerospace workforce is eligible to retire and the average

Safety of the Transport of Radioactive Materials for Civilian Use in France. Lessons learned by IRSN from analysis of significant events reported in 2012 and 2013

International Nuclear Information System (INIS)

2015-01-01

Every two years since 2008, IRSN has published in a report the lessons learnt from its analysis of significant events involving the transport of radioactive materials for civilian purposes in France. Each year in France, some 770,000 shipments of radioactive materials for civilian use are done by road, railway, inland waterway, sea and air. For 2012 and 2013, the report did not find evidence of degradation compared with previous years, particularly for industrial activities in the nuclear power industry, which raise the most significant safety issues. Since 1999, approximately a hundred events are reported each year, which represents, on average, one event per 10,000 packages transported. IRSN notes that none of the events that occurred over the two years had an impact on public health or environmental protection. Events involving a defect in the closure of spent fuel shipping packages and deviations concerning the content of the packages, which had increased in 2010 and 2011, are now down. It would seem to confirm that the organizational measures implemented by those sending the packages have had a positive impact. Previous trends which brought to light failures in the preparation of packages and their handling, in particular in the medical sector, have been confirmed. Even if most of the packages concerned contain low levels of radioactivity, recurrence of these events confirms the value of implementing appropriate preventive actions on the part of the companies involved. Lastly, descriptions of several typical events that occurred in 2012 and 2013 provide illustrations of the analyses that were performed on actual cases

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

Thermal-hydraulic transient characteristics of ship-propulsion reactor investigated through safety analysis

International Nuclear Information System (INIS)

Fujiki, Kazuo; Asaka, Hideaki; Ishida, Toshihisa

1986-01-01

Thermal-hydraulic behaviors in the reactor of Nuclear Ship ''Mutsu'' were investigated through safety evaluation of operational transients by using RETRAN and COBRA-IV codes. The results were compared to the transient behaviors of typical commercial PWR and the characteristics of transient thermal-hydraulic behaviors in ship-loaded reactor were figured out. ''Mutsu'' reactor has larger thermal margin than commercial PWR because it is designed to be used as ship-propulsion power source in the load-following operation mode. This margin makes transient behavior in general milder than in commercial PWR but high opening pressure set point of main-steam safety valves leads poor heat-sink condition after reactor trip. The effects of other small-sized components are also investigated. The findings in the paper will be helpful in the design of future advanced reactor for nuclear ship. (author)

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

Site and facility transportation services planning documents

Energy Technology Data Exchange (ETDEWEB)

Ratledge, J.E. (Oak Ridge National Lab., TN (USA)); Danese, L.; Schmid, S. (Science Applications International Corp., Oak Ridge, TN (USA))

1990-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) will eventually ship Purchasers' (10 CFR 961.3) spent nuclear fuel from approximately 122 commercial nuclear facilities. The preparation and processing of Site and Facility Specific Transportation Services Planning Documents (SPDs) and Site Specific Servicing Plans (SSSPs) provides a focus for advanced planning and the actual shipping of waste, as well as the overall development of transportation requirements for the waste transportation system. SPDs will be prepared for each of the affected nuclear waste facilities over the next 2 years with initial emphasis on facilities likely to be served during the earliest years of the Federal Waste Management System (FWMS) operations. 3 figs., 1 tab.

Site and facility transportation services planning documents

International Nuclear Information System (INIS)

Ratledge, J.E.; Danese, L.; Schmid, S.

1990-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) will eventually ship Purchasers' (10 CFR 961.3) spent nuclear fuel from approximately 122 commercial nuclear facilities. The preparation and processing of Site and Facility Specific Transportation Services Planning Documents (SPDs) and Site Specific Servicing Plans (SSSPs) provides a focus for advanced planning and the actual shipping of waste, as well as the overall development of transportation requirements for the waste transportation system. SPDs will be prepared for each of the affected nuclear waste facilities over the next 2 years with initial emphasis on facilities likely to be served during the earliest years of the Federal Waste Management System (FWMS) operations. 3 figs., 1 tab

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.

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)

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

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

Analysis of civilian processing programs in reduction of excess separated plutonium and high-enriched uranium

International Nuclear Information System (INIS)

Persiani, P.J.

1995-01-01

The purpose of this preliminary investigation is to explore alternatives and strategies aimed at the gradual reduction of the excess inventories of separated plutonium and high-enriched uranium (HEU) in the civilian nuclear power industry. The study attempts to establish a technical and economic basis to assist in the formation of alternative approaches consistent with nonproliferation and safeguards concerns. The analysis addresses several options in reducing the excess separated plutonium and HEU, and the consequences on nonproliferation and safeguards policy assessments resulting from the interacting synergistic effects between fuel cycle processes and isotopic signatures of nuclear materials

Civilian Personnel: Career Management

National Research Council Canada - National Science Library

2001-01-01

This revision; (1) Contains changes required by the establishment of a consolidated and realigned management structure for civilian personnel, manpower, and related functions in the Office of the Assistant Secretary of the Army...

Energy issues, destabilization challenge? The nuclear power example

International Nuclear Information System (INIS)

Castel, Viviane du

2010-01-01

The depletion of oil, geopolitical uncertainties resulting, fluctuation and price volatility leads, since the 2000's, a development in which the economy favors nuclear energy for civilian use. Thus, the development of the international market for nuclear industry is linked to the competitiveness of nuclear deal with their competitors using fossil fuels (oil, gas, coal). Nuclear power is both an energy benefit to the countries that we use (low emissions of greenhouse gas emissions, low pollution, stable prices and competitive supply without major obstacles) and worrying (no real solution for waste, transfer risk from civilian to nuclear weapons). The Business Intelligence (BI) appears to be essential for companies in this industry and is based on technical and urgent challenges. BI has become an imperative for companies in the energy sector

Educational support programs: Office of Civilian Radioactive Waste Management

International Nuclear Information System (INIS)

Williamson, R.C.

1989-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) currently sponsors two educationally related programs: the Radioactive Waste Management Fellowship Program and the Radioactive Waste Management Research Program for Historically Black Colleges and Universities (HBCU). The graduate fellowship program was implemented in 1985 to meet the US Department of Energy's (DOE's) expected manpower needs for trained scientists and engineers to assist in carrying out the activities of the Nuclear Waste Policy Act. It is recognized that a shortage of master's and doctoral level scientists and engineers in disciplines supportive of the nation's high-level radioactive waste management (RWM) program may impede the DOE's ability to properly carry out its mission under the act. The fellowship program encourages talented undergraduate students to enter graduate programs designed to educate and train them in fields directly related to RWM. The program supports graduate students in various disciplines, including nuclear science and engineering, health physics, and certain area of geology and chemical engineering. It also encourages universities to support and improve research activities and academic programs related to the management of spent nuclear fuel and high-level radioactive waste

Proliferation of nuclear weapons. Civilian and military exploitation of nuclear power

International Nuclear Information System (INIS)

Andresen, S.; Kongstad, S.

1978-01-01

Following brief technical and historical surveys the structure of the nuclear power market is discussed. In the 1970s a major change has been the decline of USA's virtual monopoly and the active entry of West Germany, France and Canada into the merket. Another development has been the commercialisation of progressively more of the fuel cycle, vide the agreements between Brazil and W. Germany, and Pakistan and France. These tendencies, added to the general spread of nuclear technologial ability and the adoption of nuclear power in more and more developing countries is presumed to increase the danger of nuclear weapon proliferation. The motives for, and means of, such proliferation are analysed. The tripartite agreement between Brazil, W. Germany and USA is discussed in great detail to illustrate the situation. The role of the NPT is not found to be significant. It is concluded that though proliferation may be inevitible, the motives may be for prestige and negotiating power, rather than use, and that the policy of the superpowers seems in the long run to lead to a reduction of their military dominance, and possible also their economic and political position in the international community. (JIW)

Export of nuclear equipment and materials and the non-proliferation of nuclear weapons

International Nuclear Information System (INIS)

Courteix, Simone.

1977-01-01

The problem of the non-proliferation of nuclear weapons is one of great concern today despite the entry into force in the early '70s of the NPT. To master civilian nuclear technology implies the ability to develop nuclear explosive devices; therefore in recent years contacts have strengthened between countries exporting nuclear equipment, specially in the frame of the 'London Club' so as to ensure that their exports will not result in disseminating nuclear weapons. (NEA) [fr

Nudging Armed Groups: How Civilians Transmit Norms of Protection

Directory of Open Access Journals (Sweden)

Oliver Kaplan

2013-12-01

Full Text Available What are the varying roles that norms play to either enable or constrain violence in armed conflict settings? The article examines this question by drawing on experiences from communities and armed groups in Colombia and Syria. It begins by presenting an explanation of how norms of violence and nonviolence may arise within communities and influence the behavior of civilian residents, reducing the chances of them becoming involved with armed groups. It then considers how civilian communities can transmit those same norms, shared understandings, and patterns of interaction to the ranks of illegal armed groups and subsequently shape their decisions about the use of violence against civilians. The author argues that civilians may be better positioned to promote the principles codified in International Humanitarian Law than international humanitarian organizations because they have closer contact with irregular armed actors and are viewed with greater legitimacy. The analysis illustrates that to better understand civilian protection mechanisms it is essential to study the interactions between communities and armed actors.

NUCLEAR NONPROLIFERATION: Concerns With the U.S. International Nuclear Materials Tracking System

National Research Council Canada - National Science Library

Rezendes, Victor

1996-01-01

...) provide data to policymakers and other government officials. The United States regulates and controls its exports of civilian-use nuclear materials through three mechanisms-agreements for cooperation, export licenses, and subsequent arrangements...

Office of Civilian Radioactive Waste Management annual report to Congress

International Nuclear Information System (INIS)

1985-05-01

This is the second Annual Report on the activities and expenditures of the Office of Civilian Radioactive Waste Management (OCRWM) and covers the fiscal year ending September 30, 1984. Research over the past 30 years has shown that high-level radioactive waste and spent nuclear fuel can be safely disposed of in geologic repositories. This report provides an overview of the OCRWM organization. The specific accomplishments of the Office are presented. The Office's financial statements for fiscal years 1983 and 1984 are included, and a concluding chapter updates the report with a brief summary of key accomplishments since the end of fiscal year 1984. 9 figs., 5 tabs

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

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

Constraining potential nuclear-weapons proliferation from civilian reactors

International Nuclear Information System (INIS)

Travelli, A.; Gaines, L.L.; Minkov, V.; Olson, A.P.; Snelgrove, J.

1993-01-01

Cessation of the Cold War and renewed international attention to the proliferation of weapons of mass destruction are leading to national policies aimed at restraining nuclear-weapons proliferation that could occur through the nuclear-fuel cycle. Argonne, which has unique experience, technology, and capabilities, is one of the US national laboratories contributing to this nonproliferation effort

An assessment of the transportation costs of shipping non-fuel assembly hardware to FWMS facilities

International Nuclear Information System (INIS)

Shappert, L.B.; Joy, D.S.; Johnson, P.E.; Danese, F.L.; Best, R.E.

1991-01-01

This study examines the cost of using Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) Initiative I casks for transporting 62,700 MTU of spent fuel plus associated non-fuel assembly hardware (NFAH) between reactor sites and either a monitored retrievable storage (MRS) or a repository facility. The study further considers the benefits of increasing the cell size of the Initiative I BWR cask baskets to accommodate the fuel plus channels (which also would decrease the capacity of the cask to carry BWR fuel without channels) and the use of a commercial, non-spent-fuel cask to carry compacted NFAH that could not be shipped integrally. Costs that are developed involve transportation charges, capital costs for casks, and canning costs of NFAH that have been separated from the fuel. The results indicate that significant cost savings are possible if NFAH is accepted into the Federal Waste Management System (FWMS) that is either integral with the spent fuel, or consolidated if it has been separated. Shipment of unconsolidated NFAH is very expensive. Transportation costs for shipping to a western repository are approximately 50 to 75% higher than the costs for shipping to an eastern MRS

Military to civilian nurse: Personal and professional reconstruction.

Science.gov (United States)

Elliott, Brenda; Chargualaf, Katie A; Patterson, Barbara

2017-05-01

To examine and describe the transition process of military nurses from military nursing practice to civilian nursing practice. A second aim was to identify challenges and facilitators to this transition. Serving in the military, and embodying its values, can have a major impact on a person's worldview. These individuals serve not only as nurses but also as part of a larger military culture with a mission to protect. The decision to separate from the military and transition into the civilian workforce carries many challenges capable of influencing nurses' personal and professional identities. Qualitative descriptive. Semi-structured interviews of 10 nurse veterans were conducted in 2015-2016. Data were collected until saturation was reached. The transition includes four major phases from military to civilian nurse: Separating from Military Life, Conflict and Chaos, Shifting Sands and Personal and Professional Reconstruction. Duration and progress through each phase varied slightly for individual nurses. Both work-role and personal identity transition occur when a nurse leaves the military and enters civilian practice. Military and civilian organisations, in both the USA and other countries, can implement supports to aid these nurses during this personal and professional change. Recommendations from the study group are provided. The global nursing profession, as well as healthcare organisations that employ nurse veterans, has a commitment and obligation to understand the transition process of nurses who practise within the scope of military nursing and later in civilian nursing environments so that they may be supported and used to the extent of their prior experience. Lessons learned and advice from this group of nurses may positively aid others in their transition experience. © 2016 John Wiley & Sons Ltd.

Hysteresis of targeting civilians in armed conflicts

OpenAIRE

Uih Ran Lee

2015-01-01

This article explores warring groups’ intentional targeting behavior against civilians, a strictly prohibited war strategy by international norms. Using dynamic panel regressions run on a comprehensive dataset of contemporary warfare which covers 22 years (1989-2010), I find that warring actors, both sovereign states and formally organized armed groups, behave systematically in terms of civilian targeting when they are involved in prolonged armed conflict (15-22 years). Warring actors’ lethal...

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.

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)

Military and civilian media coverage of suicide.

Science.gov (United States)

Edwards-Stewart, Amanda; Kinn, Julie T; June, Jennifer D; Fullerton, Nicole R

2011-01-01

Military suicide has increased over the past decade and reports of Service Member and Veteran suicides receive media attention. Some methods of reporting suicide appear to cause a "media contagion" effect, potentially increasing suicide. This effect is explored in relation to media reports of both military and civilian suicides. To reduce possible contagion, recommendations for media reporting of suicides were adapted by the Suicide Prevention Resource Center (SPRC). We assessed 240 military and civilian newspaper reports of suicide from 15 different sources for compliance with the SPRC guidelines. Nearly all reviewed articles violated at least one guideline. Results highlighted military news articles regarding Service Members included more pejorative language and discussion of failed psychological treatment. Conversely, civilian articles romanticized the victim and provided more details regarding the suicide. Further exploration of military suicide reporting bias is discussed as a need in future research.

Nuclear questions; Le nucleaire en questions

Energy Technology Data Exchange (ETDEWEB)

Berg, Eugene

2012-02-15

Civilian and military nuclear questions fill a multitude of publications these days, especially after the Japanese tsunami and the Fukushima disaster. The author analyses some of them and highlights the links between civil and military nuclear industries, the realities of the nuclear cycle and related industrial questions before concluding on the controversial issue of weapons and their proliferation potential

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.)

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

USSR orders computers to improve nuclear safety

International Nuclear Information System (INIS)

Anon.

1990-01-01

Control Data Corp (CDC) has received an order valued at $32-million from the Soviet Union for six Cyber 962 mainframe computer systems to be used to increase the safety of civilian nuclear powerplants. The firm is now waiting for approval of the contract by the US government and Western Allies. The computers, ordered by the Soviet Research and Development Institute of Power Engineering (RDIPE), will analyze safety factors in the operation of nuclear reactors over a wide range of conditions. The Soviet Union's civilian nuclear program is one of the largest in the world, with over 50 plants in operation. Types of safety analyses the computers perform include: neutron-physics calculations, radiation-protection studies, stress analysis, reliability analysis of equipment and systems, ecological-impact calculations, transient analysis, and support activities for emergency response. They also include a simulator with realistic mathematical models of Soviet nuclear powerplants to improve operator training

Cutaneous reactions in nuclear, biological and chemical warfare

Directory of Open Access Journals (Sweden)

Arora Sandeep

2005-03-01

Full Text Available Nuclear, biological and chemical warfare have in recent times been responsible for an increasing number of otherwise rare dermatoses. Many nations are now maintaining overt and clandestine stockpiles of such arsenal. With increasing terrorist threats, these agents of mass destruction pose a risk to the civilian population. Nuclear and chemical attacks manifest immediately while biological attacks manifest later. Chemical and biological attacks pose a significant risk to the attending medical personnel. The large scale of anticipated casualties in the event of such an occurrence would need the expertise of all physicians, including dermatologists, both military and civilian. Dermatologists are uniquely qualified in this respect. This article aims at presenting a review of the cutaneous manifestations in nuclear, chemical and biological warfare and their management.

An Argument for Documenting Casualties: Violence Against Iraqi Civilians 2006

National Research Council Canada - National Science Library

Hall, Katharine; Stahl, Dale

2008-01-01

The problem of measuring the number of civilian fatalities in Iraq gained widespread media coverage when the Lancet published a study in October 2004 claiming that more than 100,000 Iraqi civilians...

Nuclear weapons proliferation as a world order problem

International Nuclear Information System (INIS)

Falk, R.

1977-01-01

World-order concerns have intensified recently in light of mounting evidence that a weapons capability will soon be within easy reach of more and more governments and of certain nongovernmental groupings as well. One reliable source estimates that by 1985 as many as fifty countries could ''produce enough plutonium each year for at least several dozen nuclear explosives.'' In an even more immediate sense, ''economic competition among nuclear suppliers today could soon lead to a world in which twenty or more nations are but a few months from a nuclear weapons force.'' Three developments have created this ''world order'' sense of concern: (1) increased pace of civilian nuclear power deployment globally as a consequence of rising oil prices, unreliability of oil supplies, and reality of dwindling oil reserves in any case; (2) actuality of India's nuclear explosion in May 1974 which demonstrated vividly how any state that pursues a ''civilian'' program can also develop its own weapons capability; and (3) the intensification of competition for international nuclear sales which makes it increasingly evident that nonproliferation goals are no longer compatible with the pursuit of national commercial advantage; essentially, this reality has emerged from a break in the American monopoly over civilian nuclear technology and the willingness of French and German suppliers to provide all elements of the nuclear fuel cycle, including enrichment and reprocessing facilities,to any nation that feels it can afford to buy them; the German-Brazilian deal (worth at least $4 billion) has proven to be the equivalent in the commercial realm of India's ''peaceful'' nuclear explosion. Such developments disclose the alarming prospect that easier access to nuclear technology will make it relatively simple and thus more likely for a beleaguered government or a desperate political actor of any sort to acquire and possibly use nuclear weapons

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.)

Bibliography of studies for the Salt Repository Project Office of the Civilian Radioactive Waste Management Program, April 1978-May 1986

International Nuclear Information System (INIS)

1986-10-01

DOE/CH/10140-05 is an annotated bibliography of approved reports that have been produced for the US Department of Energy Salt Repository Project Office of the Civilian Radioactive Waste Management Program since April 1978. This document is intended for use by the US Department of Energy, State and local officials, the US Nuclear Regulatory Commission, contractors to the Office of Nuclear Waste Isolation, concerned citizens, and others who need a comprehensive listing of reports related to a nuclear waste repository in salt. This document consists of a main report listing, appendixes with Work Breakdown Structure lists, and a topical index

Bibliography of studies for the Salt Repository Project Office of the Civilian Radioactive Waste Management Program, April 1978-December 1986

International Nuclear Information System (INIS)

1987-06-01

This document is an annotated bibliography of approved reports that have been produced for the US Department of Energy Salt Repository Project Office of the Civilian Radioactive Waste Management Program since April 1978. This document is intended for use by the US Department of Energy, State and local officials, the US Nuclear Regulatory Commission, contractors to the Office of Nuclear Waste Isolation, concerned citizens, and others who need a comprehensive listing of reports related to a nuclear waste repository in salt. This document consists of a main report listing, appendixes with Work Breakdown Structure lists, and a topical index

Science, Society, and America's Nuclear Waste: Nuclear Waste, Unit 1. Teacher Guide. Second Edition.

Science.gov (United States)

Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

This guide is Unit 1 of the four-part series Science, Society, and America's Nuclear Waste produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to help students establish the relevance of the topic of nuclear waste to their everyday lives and activities. Particular attention is…

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

Science, Society, and America's Nuclear Waste: The Nuclear Waste Policy Act, Unit 3. Teacher Guide. Second Edition.

Science.gov (United States)

Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

This guide is Unit 3 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to identify the key elements of the United States' nuclear waste dilemma and introduce the Nuclear Waste Policy Act and the role of the…

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)

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.)

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.

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.)

Civilian Nuclear Power. A report to the President, 1962

Energy Technology Data Exchange (ETDEWEB)

Seaborg, Glenn T. [United States Atomic Energy Commission, Washington, DC (United States)

1962-11-20

This overarching report on the role of nuclear power in the U.S. economy was requested by U.S. President John F. Kennedy in March, 1962. The U.S. Atomic Energy Commission was charged with producing the report, gaining input from individuals inside and outside government, including the Department of Interior, the Federal Power Commission, and the National Academy of Sciences Committee on Natural Resources. The study was to identify the objectives, scope, and content of a nuclear power development program in light of prospective energy needs and resources. It should recommend appropriate steps to assure the proper timing of development and construction of nuclear power projects, including the construction of necessary prototypes and continued cooperation between government and industry. There should also be an evaluation of the extent to which the U.S. nuclear power program will further international objectives in the peaceful uses of atomic energy.

Global comparison of warring groups in 2002-2007: fatalities from targeting civilians vs. fighting battles.

Science.gov (United States)

Hicks, Madelyn Hsiao-Rei; Lee, Uih Ran; Sundberg, Ralph; Spagat, Michael

2011-01-01

Warring groups that compete to dominate a civilian population confront contending behavioral options: target civilians or battle the enemy. We aimed to describe degrees to which combatant groups concentrated lethal behavior into intentionally targeting civilians as opposed to engaging in battle with opponents in contemporary armed conflict. We identified all 226 formally organized state and non-state groups (i.e. actors) that engaged in lethal armed conflict during 2002-2007: 43 state and 183 non-state. We summed civilians killed by an actor's intentional targeting with civilians and combatants killed in battles in which the actor was involved for total fatalities associated with each actor, indicating overall scale of armed conflict. We used a Civilian Targeting Index (CTI), defined as the proportion of total fatalities caused by intentional targeting of civilians, to measure the concentration of lethal behavior into civilian targeting. We report actor-specific findings and four significant trends: 1.) 61% of all 226 actors (95% CI 55% to 67%) refrained from targeting civilians. 2.) Logistic regression showed actors were more likely to have targeted civilians if conflict duration was three or more years rather than one year. 3.) In the 88 actors that targeted civilians, multiple regressions showed an inverse correlation between CTI values and the total number of fatalities. Conflict duration of three or more years was associated with lower CTI values than conflict duration of one year. 4.) When conflict scale and duration were accounted for, state and non-state actors did not differ. We describe civilian targeting by actors in prolonged conflict. We discuss comparable patterns found in nature and interdisciplinary research. Most warring groups in 2002-2007 did not target civilians. Warring groups that targeted civilians in small-scale, brief conflict concentrated more lethal behavior into targeting civilians, and less into battles, than groups in larger

Outcomes of the international forum. Illegal nuclear traffic: Risks, safeguards and countermeasures

International Nuclear Information System (INIS)

Martellini, M.; Cotta-Ramusino, P.

1998-01-01

Two important meetings were held in Como, Italy, at the Centre for Scientific Culture A.Volta on illegal nuclear traffic from research of military and civilian nuclear installations around the world, technologies suitable to detect it and counter measures. This paper summarizes the outcome of these meetings which discussed obstacles existing in control of illegal nuclear material trafficking and indicated specific measures to overcome some of these obstacles. These measures include working out standardised procedures and methodology of analysis of nuclear materials, setting up a civilian world data bank to collect information on the type, features and isotopic composition of stolen materials, development and application of highly sensitive stationary and field detectors and distance monitoring systems

Imagined Modernity. Nuclear Power and West German Society in the 1960s

International Nuclear Information System (INIS)

Metzler, G.

2012-01-01

In 1969 the first commercial nuclear power plant went into operation in West Germany, making the country a latecomer (compared to other Western countries) in the civilian use of nuclear energy. Yet, in the late 1950s and 1960s, nuclear energy played a major part in public debates on energy supply, on science and technology policy, and the relationship between state and the economy. The civilian use of atomic energy also served as a source of national identity and a projection of modernity. The paper seeks to connect analyses of technical, economic, political, and cultural developments, in order to assess the overall impact of nuclear power on West German society. (author)

Utilities press Congress to salvage nuclear R and D

International Nuclear Information System (INIS)

Crawford, M.

1986-01-01

A proposal to reduce DOE's advanced civilian reactor research and expand military work worries nuclear industry. The Reagan Administration has emphasized high-risk, long term research over applied research and demonstrations on the grounds that industry should be responsible for technology development. The proposed fiscal year 1987 budget for civilian reactor research is $222.5 million, a deep cut below this year's budget of $319.7 million. Funding for advanced reactor research and development alone shows a 61.5% reduction to $49.5 million. With this grim budget outlook, funding restorations may have to be gotten from other nuclear research programs

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

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

Department of Defense Civilian Personnel Manual

National Research Council Canada - National Science Library

1996-01-01

.... It implements policy, establishes uniform DoD-wide procedures, provides guidelines and model programs, delegates authority, and assigns responsibilities regarding civilian personnel management within...

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...

Nuclear energy - a vote for reason. 2. ed.

International Nuclear Information System (INIS)

Waas, U.

1978-01-01

The book approaches civilians, politicians, technicians, and journalists. The civilian is given the task to judge opinions not with regard to their simple formulation but to the correctness of their contents. For the politicians, technique should not be a world of wonders in which solutions can be found without regard to political advantages and disadvantages. Technicians have the task to present politically important aspects of technical problems to civilians in a way so they can be understood also by non-professionals. Journalists should realize that there are no specialists for a political-technical discussion and that they therefore have a special responsibility as mediators of information and should do without sensational effects. Safety in the application of nuclear energy and discussions concerning alternative energy sources, such as the extents of uranium and other nuclear fuel resources are included in the energy political aspects. The bibliography which has been updated until mid 1978 represents a valuable documentation on the current situation. (GL) [de

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)

Estimates of fire environments in ship holds containing radioactive material packages

International Nuclear Information System (INIS)

Koski, J.A.; Cole, J.K.; Hohnstreiter, G.F.; Wix, S.D.

1995-01-01

Fire environments that occur on cargo ships differ significantly from the fire environments found in land transport. Cargo ships typically carry a large amount of flammable fuel for propulsion and shipboard power, and may transport large quantities of flammable cargo. As a result, sea mode transport accident records contain instances of long lasting and intense fires. Since Irradiated Nuclear Fuel (INF) casks are not carried on tankers with large flammable cargoes, most of these dramatic, long burning fires are not relevant threats, and transport studies must concentrate on those fires that are most likely to occur. By regulation, INF casks must be separated from flammable cargoes by a fire-resistant, liquid-tight partition. This makes a fire in an adjacent ship hold the most likely fire threat. The large size of a cargo ship relative to any spent nuclear fuel casks on board, however, may permit a severe, long lasting fire to occur with little or no thermal impact on the casks. Although some flammable materials such as shipping boxes or container floors may exist in the same hold with the cask, the amount of fuel available may not provide a significant threat to the massive transport casks used for radioactive materials. This shipboard fire situation differs significantly from the regulatory conditions specified in 10 CFR 71 for a fully engulfing pool fire. To learn more about the differences, a series of simple thermal analyses has been completed to estimate cask behavior in likely marine and land thermal accident situations. While the calculations are based on several conservative assumptions, and are only preliminary, they illustrate that casks are likely to heat much more slowly in shipboard hold fires than in an open pool fire. The calculations also reinforce the basic regulatory concept that for radioactive materials, the shipping cask, not the ship, is the primary protection barrier to consider

Reporting Iraqi civilian fatalities in a time of war

Directory of Open Access Journals (Sweden)

Olander William E

2009-11-01

Full Text Available Abstract Background In February, 2007, the Associated Press (AP conducted a poll of 1,002 adults in the United States about their attitudes towards the war in Iraq. Respondents were remarkably accurate estimating the current death toll of US soldiers, yet were grossly inaccurate in estimating the current death toll of Iraqi civilians. We conducted a search of newspapers reports to determine the extent of the discrepancy between reporting Coalition and Iraqi civilian deaths, hypothesizing that there would be an over-representation of Coalition deaths compared to Iraqi civilian deaths. Methods We examined 11 U.S. newspapers and 5 non-U.S. newspapers using electronic databases or newspaper web-archives, to record any reports between March 2003 and March 2008 of Coalition and Iraqi deaths that included a numeric indicator. Reports were described as "events" where they described a specific occurrence involving fatalities and "tallies" when they mentioned the number of deaths over a period of time. We recorded the number of events and tallies related to Coalition deaths, Iraqi civilian deaths, and Iraqi combatant deaths Results U.S. newspapers report more events and tallies related to Coalition deaths than Iraqi civilian deaths, although there are substantially different proportions amongst the different U.S. newspapers. In four of the five non-US newspapers, the pattern was reversed. Conclusion This difference in reporting trends may partly explain the discrepancy in how well people are informed about U.S. and Iraqi civilian fatalities in Iraq. Furthermore, this calls into question the role of the media in reporting and sustaining armed conflict, and the extent to which newspaper and other media reports can be used as data to assess fatalities or trends in the time of war.

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

25th anniversary of the Lenin nuclear icebreaker

International Nuclear Information System (INIS)

Khlopkin, N.S.; Mitenkov, F.M.; Movshevich, Z.M.; Pologikh, B.G.; Sledzyuk, A.K.

1984-01-01

The main results of operation and prospects of further development of nuclear ships in the USSR are considered. The main characteristics and the data on the most important stages of operation of nuclear-powered ice-breakers ''Lenin'', ''Leonid Brezhnev'' and ''Sibir''' are presented. Advantages of nuclear-powered ice-breakers as compared with diesel electric ice-breakers are analyzed. In the course of operation of nuclear-powered ice-breakers high reliability of water-pressurized reactors, installed in the ships, the crew and environment safety, and economic advisability of nuclear power on big ships durably worbing far from bases have been proved. The exploitation of nuclear-powered ice-breakers permitted considerably increase the periods of navigation to have made it all-theMyear-round in the western sector of the Arctic. The speed of steering the ships has increased 1.5-2 times. Presently shallow-draught nuclear ice-breakers are developed for the Siberian rivers. An ice-breaker transport lighter-carrier is now being built, that can take on board 74 lighters 370 t each

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.

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

Global comparison of warring groups in 2002-2007: fatalities from targeting civilians vs. fighting battles.

Directory of Open Access Journals (Sweden)

Madelyn Hsiao-Rei Hicks

Full Text Available BACKGROUND: Warring groups that compete to dominate a civilian population confront contending behavioral options: target civilians or battle the enemy. We aimed to describe degrees to which combatant groups concentrated lethal behavior into intentionally targeting civilians as opposed to engaging in battle with opponents in contemporary armed conflict. METHODOLOGY/PRINCIPAL FINDINGS: We identified all 226 formally organized state and non-state groups (i.e. actors that engaged in lethal armed conflict during 2002-2007: 43 state and 183 non-state. We summed civilians killed by an actor's intentional targeting with civilians and combatants killed in battles in which the actor was involved for total fatalities associated with each actor, indicating overall scale of armed conflict. We used a Civilian Targeting Index (CTI, defined as the proportion of total fatalities caused by intentional targeting of civilians, to measure the concentration of lethal behavior into civilian targeting. We report actor-specific findings and four significant trends: 1. 61% of all 226 actors (95% CI 55% to 67% refrained from targeting civilians. 2. Logistic regression showed actors were more likely to have targeted civilians if conflict duration was three or more years rather than one year. 3. In the 88 actors that targeted civilians, multiple regressions showed an inverse correlation between CTI values and the total number of fatalities. Conflict duration of three or more years was associated with lower CTI values than conflict duration of one year. 4. When conflict scale and duration were accounted for, state and non-state actors did not differ. We describe civilian targeting by actors in prolonged conflict. We discuss comparable patterns found in nature and interdisciplinary research. CONCLUSIONS/SIGNIFICANCE: Most warring groups in 2002-2007 did not target civilians. Warring groups that targeted civilians in small-scale, brief conflict concentrated more lethal

The Epidemiology of Operation Stress during Continuing Promise 2011: A Humanitarian Response and Disaster Relief Mission aboard a US Navy Hospital Ship.

Science.gov (United States)

Scouten, William T; Mehalick, Melissa L; Yoder, Elizabeth; McCoy, Andrea; Brannock, Tracy; Riddle, Mark S

2017-08-01

Introduction Operational stress describes individual behavior in response to the occupational demands and tempo of a mission. The stress response of military personnel involved in combat and peace-keeping missions has been well-described. The spectrum of effect on medical professionals and support staff providing humanitarian assistance, however, is less well delineated. Research to date concentrates mainly on shore-based humanitarian missions. Problem The goal of the current study was to document the pattern of operational stress, describe factors responsible for it, and the extent to which these factors impact job performance in military and civilian participants of Continuing Promise 2011 (CP11), a ship-based humanitarian medical mission. This was a retrospective study of Disease Non-Battle Injury (DNBI) data from the medical sick-call clinic and from weekly self-report questionnaires for approximately 900 US military and civilian mission participants aboard the USNS COMFORT (T-AH 20). The incidence rates and job performance impact of reported Operational Stress/Mental Health (OS/MH) issues and predictors (age, rank, occupation, service branch) of OS/MH issues (depression, anxiety) were analyzed over a 22-week deployment period. Incidence rates of OS/MH complaints from the sick-call clinic were 3.7% (4.5/1,000 persons) and 12.0% (53/1,000 persons) from the self-report questionnaire. The rate of operational stress increased as the mission progressed and fluctuated during the mission according to ship movement. Approximately 57% of the responders reported no impact on job performance. Younger individuals (enlisted ranks E4-6, officer ranks O1-3), especially Air Force service members, those who had spent only one day off ship, and those who were members of specific directorates, reported the highest rates of operational stress. The overall incidence of OS/MH complaints was low in participants of CP11 but was under-estimated by clinic-based reporting. The OS

Protecting against failure by brittle fracture in ferritic steel shipping containers

International Nuclear Information System (INIS)

Schwartz, M.W.; Langland, R.T.

1983-01-01

The possible use of ferritic steels for the containment structure of shipping casks has motivated the development of criteria for assuring the integrity of these casks under both normal and hypothetical accident conditions specified in Part 71 of the Code of Federal Regulations. The US Nuclear Regulatory Commission Regulation Guide 7.6 provides design criteria for preventing ductile failure steel shipping containers. The research described in this paper deals with criteria for preventing brittle fracture of ferritic steel shipping containers. Initially guidelines were developed for ferritic steel up to four inches thick (I). This was followed by an investigation of various criteria that might be used for monolithic thick walled casks greater than four inches thick (2). Three categories of safety are identified in the design of shipping containers. Category I, the highest level of safety, is appropriate for containment systems for spent nuclear fuel and high level waste transport packaging. In Category I, containers are designed to the highest level of safety and brittle fracture is essentially not possible. Categories II and III represent levels of safety commensurate with the consequences of release of lower levels of radioactivity. In these latter categories, consideration of factors contributing to brittle fracture, good engineering practice, and careful selection of material make brittle fracture unlikely under environmental conditions encountered during shipping. This paper will deal primarily with Category I containers. The guidelines for Category II and III containers are fully described elsewhere. 5 references, 10 figures, 3 tables

Transportation of spent nuclear fuels

International Nuclear Information System (INIS)

Meguro, Toshiichi

1976-01-01

The spent nuclear fuel taken out of reactors is cooled in the cooling pool in each power station for a definite time, then transported to a reprocessing plant. At present, there is no reprocessing plant in Japan, therefore the spent nuclear fuel is shipped abroad. In this paper, the experiences and the present situation in Japan are described on the transport of the spent nuclear fuel from light water reactors, centering around the works in Tsuruga Power Station, Japan Atomic Power Co. The spent nuclear fuel in Tsuruga Power Station was first transported in Apr. 1973, and since then, about 36 tons were shipped to Britain by 5 times of transport. The reprocessing plant in Japan is expected to start operation in Apr. 1977, accordingly the spent nuclear fuel used for the trial will be transported in Japan in the latter half of this year. Among the permission and approval required for the transport of spent nuclear fuel, the acquisition of the certificate for transport casks and the approval of land and sea transports are main tasks. The relevant laws are the law concerning the regulations of nuclear raw material, nuclear fuel and reactors and the law concerning the safety of ships. The casks used in Tsuruga Power Station and EXL III type, and the charging of spent nuclear fuel, the decontamination of the casks, the leak test, land transport with a self-running vehicle, loading on board an exclusive carrier and sea transport are briefly explained. The casks and the ship for domestic transport are being prepared. (Kato, I.)

In defiance of nuclear deterrence: anti-nuclear New Zealand after two decades.

Science.gov (United States)

Reitzig, Andreas

2006-01-01

In 1984, nuclear-armed and nuclear-powered vessels were banned from New Zealand to express the country's rejection of the nuclear deterrence concept. This led to a disagreement with the United States. Today, the ban on nuclear-powered ships is the only element of the nuclear-free legislation that still strains US-New Zealand relations. This article presents the reasons for the ban on nuclear-powered ships, which include scientific safety concerns, a symbolic rejection of the nuclear deterrence posture, and patriotic factors such as a nuclear-free national identity. The military and economic consequences of the ban are also examined. Since the ban on nuclear-powered vessels appears to be neither widely known abroad nor commonly recognised as a supportive disarmament measure outside New Zealand, it is concluded that whatever the future of this ban will be, New Zealand's anti-nuclear image will remain known internationally through the ban on nuclear arms.

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

Stress analysis of closure bolts for shipping casks

International Nuclear Information System (INIS)

Mok, G.C.; Fischer, L.E.; Hsu, S.T.

1993-01-01

This report specifies the requirements and criteria for stress analysis of closure bolts for shipping casks containing nuclear spent fuels or high level radioactive materials. The specification is based on existing information conceming the structural behavior, analysis, and design of bolted joints. The approach taken was to extend the ASME Boiler and Pressure Vessel Code requirements and criteria for bolting analysis of nuclear piping and pressure vessels to include the appropriate design and load characteristics of the shipping cask. The characteristics considered are large, flat, closure lids with metal-to-metal contact within the bolted joint; significant temperature and impact loads; and possible prying and bending effects. Specific formulas and procedures developed apply to the bolt stress analysis of a circular, flat, bolted closure. The report also includes critical load cases and desirable design practices for the bolted closure, an in-depth review of the structural behavior of bolted joints, and a comprehensive bibliography of current information on bolted joints

Senior Service College: A Pillar of Civilian Senior Leader Development

Science.gov (United States)

2011-02-16

other burgeoning global issues mandate the existence of capable senior civilian leaders who can effectively participate within the whole-of-government...experience that provides the opportunity to discuss and debate current global issues with the members of the world’s finest military. Civilians not only

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...

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)

Liability for international nuclear transport: an overview

International Nuclear Information System (INIS)

Brown, O.F.; Horbach, N.

2000-01-01

Many elements can bear on liability for nuclear damage during transport. For example, liability may depend upon a number of facts that may be categorized as follows: shipment, origin or destination of the shipment, deviation from the planed route, temporary storage incidental to carriage; content of shipment, type of nuclear material involved, whether its origin is civilian or defence-related; sites of accident, number and type of territories damaged (i.e. potential conventions involved), applicable territorial limits, exclusive economic zone, high seas, etc.; nature of damages, personal injury, property damage, damage to the means of carriage, indirect damage, preventive measures, environmental cleanup or retrieval at seas, res communis, transboundary damages etc.; victims involved, nationality and domiciles of victims; jurisdiction, flag (for ships) or national registration (for aircraft) of the transporting vessel, courts of one or more states may have (or assert) jurisdiction to hear claims, and may have to determine what law to apply to a particular accident; applicable law, the applicability laws and/or international nuclear liability conventions; the extent to which any applicable convention has been implemented or modified by domestic legislation, conflicts with the 1982 Law of the Sea Convention or other applicable international agreements, and finally, also written agreements between installation operators and carriers can define applicable law as well as responsibilities. Harmonizing nuclear liability protection and applying it to additional international shipments would be facilitated by more countries being in treaty relations with each other as soon as possible. Adherence to an international convention by more countries (including China, Russia, the United States, etc.) would promote the open flow of services and advanced technology, and better facilitate international transport. The conventions protect the public, harmonize legislation in the

History of radiation and nuclear disasters in the former USSR

International Nuclear Information System (INIS)

Malko, M.V.

2013-01-01

The report describes the history of radiation and nuclear accidents in the former USSR. These accidents accompanied development of military and civilian use of nuclear energy. Some of them as testing of the first Soviet nuclear, Kyshtym radiation accident, radiation contamination of the Karachai lake and the Techa river, nuclear accidents at the Soviet submarine on August 10, 1985 in the Chazhma Bay (near Vladivostok) as well as nuclear accidents on April 26, 1986 at the Chernobyl NPP were of large scale causing significant radiological problems for many hundreds thousands of people. There were a number of important reasons of these and other accidents. The most important among them were time pressure by development of nuclear weapon, an absence of required financial and material means for adequate management of problems of nuclear and radiation safety, and inadequate understanding of harmful interaction of ionizing radiation on organism as well as a hypersecrecy by realization of projects of military and civilian use of nuclear energy in the former USSR. (author)

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

32 CFR 720.23 - Naval prisoners as witnesses or parties in civilian courts.

Science.gov (United States)

2010-07-01

... assume responsibility for the prisoner while he is in its custody; and (3) that the civilian authority... civilian courts. 720.23 Section 720.23 National Defense Department of Defense (Continued) DEPARTMENT OF THE... civilian courts. (a) Criminal actions. When Federal or State authorities desire the attendance of a naval...

Civilian casualties of Iraqi ballistic missile attack to

Directory of Open Access Journals (Sweden)

Khaji Ali

2012-06-01

Full Text Available 【Abstract】Objective: To determine the pattern of causalities of Iraqi ballistic missile attacks on Tehran, the capital of Iran, during Iraq-Iran war. Methods: Data were extracted from the Army Staff Headquarters based on daily reports of Iranian army units during the war. Results: During 52 days, Tehran was stroked by 118 Al-Hussein missiles (a modified version of Scud missile. Eighty-six missiles landed in populated areas. During Iraqi missile attacks, 422 civilians died and 1 579 injured (4.9 deaths and 18.3 injuries per missile. During 52 days, 8.1 of the civilians died and 30.4 injured daily. Of the cases that died, 101 persons (24% were excluded due to the lack of information. Among the remainders, 179 (55.8% were male and 142 (44.2% were female. The mean age of the victims was 25.3 years±19.9 years. Our results show that the high accuracy of modified Scud missiles landed in crowded ar-eas is the major cause of high mortality in Tehran. The pres-ence of suitable warning system and shelters could reduce civilian casualties. Conclusion: The awareness and readiness of civilian defense forces, rescue services and all medical facilities for dealing with mass casualties caused by ballistic missile at-tacks are necessary. Key words: Mortality; War; Mass casualty incidents; Wounds and injuries

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

Study of Radiation Shielding Analysis for Low-Intermediate Level Waste Transport Ship

Energy Technology Data Exchange (ETDEWEB)

Kim, Dohyung; Lee, Unjang; Song, Yangsoo; Kim, Sukhoon; Ko, Jaehoon [Korea Nuclear Engineering and Service Corporation, Seoul (Korea, Republic of)

2007-07-01

In Korea, it is planed to transport Low-Intermediate Level Radioactive Waste (LILW) from each nuclear power plant site to Kyongju LILW repository after 2009. Transport through the sea using ship is one of the most prospective ways of LILW transport for current situation in Korea. There are domestic and international regulations for radiation dose limit for radioactive material transport. In this article, radiation shielding analysis for LILW transport ship is performed using 3-D computer simulation code, MCNP. As a result, the thickness and materials for radiation shielding walls next to cargo in the LILW transport ship are determined.

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...

The nuclear proliferation

International Nuclear Information System (INIS)

Gere, F.

1995-04-01

In this book is detailed the beginning of nuclear military power, with the first bomb of Hiroshima, the different ways of getting uranium 235 and plutonium 239, and how the first countries (Usa, Ussr, China, United kingdom, France) got nuclear weapons. Then the most important part is reviewed with the details of non-proliferation treaty and the creation of IAEA to promote civilian nuclear power in the world and to control the use of plutonium and uranium in nuclear power plants. The cases of countries who reached the atom mastery, such Israel, South Africa, Pakistan, Iraq, North Korea, Argentina, Brazil, Iran, Algeria, Taiwan and the reasons which they wanted nuclear weapon for or why they gave up, are exposed

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.)

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.

Swords from plowshares: the military potential of civilian nuclear energy

International Nuclear Information System (INIS)

Wohlstetter, A.; Brown, T.A.; Jones, G.; McGarvey, D.C.; Rowen, H.; Taylor, V.; Wohlstetter, R.

1977-01-01

The historical and political aspects of relations between civil nuclear technology and the proliferation of nuclear weapons are analyzed. Many countries will soon be able to come close to making a bomb without violating their nonproliferation agreement. While peaceful nuclear power production should continue, there is a need for basic changes in its development and export. The driving forces behind proliferation are examined and the initial steps set out which need to be taken

Global Comparison of Warring Groups in 2002–2007: Fatalities from Targeting Civilians vs. Fighting Battles

Science.gov (United States)

Hicks, Madelyn Hsiao-Rei; Lee, Uih Ran; Sundberg, Ralph; Spagat, Michael

2011-01-01

Background Warring groups that compete to dominate a civilian population confront contending behavioral options: target civilians or battle the enemy. We aimed to describe degrees to which combatant groups concentrated lethal behavior into intentionally targeting civilians as opposed to engaging in battle with opponents in contemporary armed conflict. Methodology/Principal Findings We identified all 226 formally organized state and non-state groups (i.e. actors) that engaged in lethal armed conflict during 2002–2007: 43 state and 183 non-state. We summed civilians killed by an actor's intentional targeting with civilians and combatants killed in battles in which the actor was involved for total fatalities associated with each actor, indicating overall scale of armed conflict. We used a Civilian Targeting Index (CTI), defined as the proportion of total fatalities caused by intentional targeting of civilians, to measure the concentration of lethal behavior into civilian targeting. We report actor-specific findings and four significant trends: 1.) 61% of all 226 actors (95% CI 55% to 67%) refrained from targeting civilians. 2.) Logistic regression showed actors were more likely to have targeted civilians if conflict duration was three or more years rather than one year. 3.) In the 88 actors that targeted civilians, multiple regressions showed an inverse correlation between CTI values and the total number of fatalities. Conflict duration of three or more years was associated with lower CTI values than conflict duration of one year. 4.) When conflict scale and duration were accounted for, state and non-state actors did not differ. We describe civilian targeting by actors in prolonged conflict. We discuss comparable patterns found in nature and interdisciplinary research. Conclusions/Significance Most warring groups in 2002–2007 did not target civilians. Warring groups that targeted civilians in small-scale, brief conflict concentrated more lethal behavior into

78 FR 56869 - Nuclear Infrastructure Programmatic Environmental Impact Statement Supplement Analysis...

Science.gov (United States)

2013-09-16

... DEPARTMENT OF ENERGY Nuclear Infrastructure Programmatic Environmental Impact Statement Supplement... of Energy (DOE) has completed the Supplement Analysis (SA) of the Programmatic Environmental Impact Statement for Accomplishing Expanded Civilian Nuclear Energy Research and Development and Isotope Production...

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

Nuclear weapons industry

International Nuclear Information System (INIS)

Bertsch, K.A.; Shaw, L.S.

1984-01-01

This unique study was written specifically as a reference source for institutional investors concerned about the threat posed to their stock portfolios by the debate over nuclear arms production. The authors focus their analysis on the 26 leading companies in the field. The perspective is neutral and refreshing. Background information on strategic policy, arms control and disarmament, and the influence of the industry on defense policy and the economy is presented rationally. The study also discusses the economic significance of both the conversion from military to civilian production and nuclear freeze initiatives. An appendix contains a fact-filled guide to nuclear weapon systems

Design and criticality considerations for 9977 and 9978 shipping packages

International Nuclear Information System (INIS)

Reed, R.; Biswas, D.; Abramczyk, G.

2009-01-01

Savannah River National Laboratory (SRNL) has developed two new, Type B, state-of-the-art, general purpose, fissile material Shipping Packages, designated as 9977 and 9978, as replacements for the U.S. Dept. of Transportation (DOT) specification 6M container. The packages accommodate plutonium, uranium, and other special nuclear materials in bulk quantities and in many forms with capabilities exceeding those of the 6M. A nuclear criticality safety evaluation demonstrates the safe configurations of the new shipping container for plutonium and uranium metal/oxide loading under various conditions for the Safety Analysis Report for Packaging (SARP). The evaluation is in compliance with the performance requirements of 10CFR 71, specifically 10CFR71.55 and 71.59. The criticality safety index (CSI) is 1.0 for most of the contents (Max. Pu Loading -4.4 kg). (authors)

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

Investing today in energy for tomorrow. U.S. civilian nuclear industry: high-level oversight. Oil prices: getting close to the psychological threshold. The future of biofuels in question

International Nuclear Information System (INIS)

Anon.

2008-01-01

This issue of Alternatives newsletter features 4 main articles dealing with: 1 - Investing today in energy for tomorrow: Whether to increase or to replace generating capacity, the amount of investment needed in energy infrastructure to meet rising demand has been identified, but many obstacles must be overcome before they become a reality. A status report and personal perspective from Pierre Gadonneix, CEO of EDF, in the 'Expert opinion' section. 2 - U.S. civilian nuclear industry - high-level oversight: The approaches are clearly different, but the licensing processes for nuclear reactor development and operation in France and the United States are both strictly regulated. Alternatives delves further. 3 - Oil prices - getting close to the psychological threshold: Are we going to stop using oil sooner rather than later if crude prices keep going up? European commodities expert Philippe Chalmin shares his opinion. 4 - The future of biofuels in question In many countries, biofuels are seen as an alternative to oil. Still, farmland is not expandable forever and the economics of biofuels deserve some scrutiny

Project on standards on good behaviour for the civilian nuclear industry

International Nuclear Information System (INIS)

Strohl, Pierre; Derche, Bernard

1995-01-01

Nuclear energy has provoked complex and sometimes heated debates involving politic, economic, scientific and moral issues, objective data alongside irrational feelings, short-term calculations as well as concerns touching on the far-reaching of humanity and the earth. These debates go beyond national borders as it is obvious that even though each country may hold divergent positions regarding the development of nuclear energy, their effects have an international scope, and, therefore, must be taken into account by all nations, even those who do not operate nuclear installations. Whatever conclusion may be drawn from these debates, decisions on nuclear energy are always taken by the political authorities, almost always at the highest level, be it national or international. These political decisions then become the body of legal standards, particularly the regulations which govern how nuclear energy is used. The main standards are for technical and scientific quality, applying to energy resource needs, to the reasons why the nuclear industry should be developed, to radioprotection and nuclear security, to protection of the environment, to radioactive waste management, to information and consulting to the public, to international cooperation, to non-proliferation of atomic weapons and to physical protection of nuclear materials. (author)

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.

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)

Civilian Agency Industry Working Group EVM World Update

Science.gov (United States)

Kerby, Jerald

2013-01-01

Objectives include: Promote the use of standards ]based, objective, and quantitative systems for managing projects and programs in the federal government. Understand how civilian agencies in general, manage their projects and programs. Project management survey expected to go out soon to civilian agencies. Describe how EVM and other best practices can be applied by the government to better manage its project and programs irrespective of whether work is contracted out or the types of contracts employed. Develop model policies aimed at project and program managers that are transportable across the government.

IMO and the peaceful use of nuclear energy through the last 30 years

International Nuclear Information System (INIS)

Jansen, E.

1990-01-01

All nuclear electric power reactors in operation and under construction by the end of 1988 are tabulated. Unclassified published statistics show that in 1988, on a world basis, there were 376 active nuclear powered submarines and surface craft, while 47 were under construction or in the process of conversion. Information on types, number of units, and nationality of these nuclear powered navy vessels is given. Parallel to this development, the Soviet Union has successfully built and put into operation a fleet of nuclear powered icebreakers, starting with the Lenin, commissioned in 1959. The first nuclear powered merchant ship, the United States' Savannah, was launched on 21 July 1959, and put into service on 1 May 1962. The Federal Republic of Germany put their nuclear propelled merchant ship Otto Hahn into operation in October 1968, and in November the same year the keel of the first Japanese nuclear ship, the Mutsu, was laid. The International Maritime Organisation (IMO) has, throughout its thirty year existence, made recommendations and developed a Nuclear Ship Safety Code to cover the safety requirements of nuclear ships, and has promoted the peaceful uses of nuclear energy. With the depletion of natural resources and environmental pollution such as the emission of gases causing the greenhouse effect, the correct and safe application of nuclear energy for peaceful purposes, including merchant ships, is likely to be the most efficient and hygienic source of energy in the next century. (UK)

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.)

Proposed advanced satellite applications utilizing space nuclear power systems

International Nuclear Information System (INIS)

Bailey, P.G.; Isenberg, L.

1990-01-01

A review of the status of space nuclear reactor systems and their possible applications is presented. Such systems have been developed over the past twenty years and are capable of use in various military and civilian applications in the 5-1000 kWe power range. The capabilities and limitations of the currently proposed nuclear reactor systems are summarized. Safety issues are shown to be identified, and if properly addressed should not pose a hindrance. Applications are summarized for the federal and civilian community. These applications include both low and high altitude satellite surveillance missions, communications satellites, planetary probes, low and high power lunar and planetary base power systems, broad-band global telecommunications, air traffic control, and high-definition television

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.

DoD Civilian Training: Source, Content, Frequency and Cost

Science.gov (United States)

1994-03-01

statistics. This especially includes Mr. Mike Dove, Ms. Kris Hoffman, Ms. Ninfa Camargo , Mr. Edward Christie, Ms. Rebecca Tag, Ms. Elizabeth Kundift Ms...Center, San Francisco , CA, will close. DoD Civilian Training Study Page 10 Chapter 2: Source There were 1,507 civilians trained We learned that 166...San Diego, CA Service School Command 13 60 San Diego, CA Submarine Training Facility 4 61 San Francisco , CA Naval Technical Training Center 13 62

The Nuclear Power Revival in Eastern Europe

International Nuclear Information System (INIS)

Bayou, Celine

2007-01-01

Far from traumatized by the April 1986 Chernobyl accident, the Central and Eastern European countries as well as the CIS are showing a growing interest in nuclear energy: this choice may be explained by increased energy demands and safer supply requirements but also by the battle against global warming. In effect, commitments made on limiting greenhouse gas emissions (particularly for the EU new member states) are becoming increasingly important as these countries return to growth. Thus, nuclear power seems to be a partial but secure means of not endangering the latter while adopting a more respectful stance vis-a-vis the environment. Thus, each country is coming out in favour of the civilian use of nuclear power: Russia has been reviving its nuclear program over the last few years, while countries obliged to close their decrepit or Soviet style power stations (Bulgaria, Slovakia, Lithuania, Slovenia, Armenia) have projects to build new ones. Those who possess reactors (the Czech Republic, Hungary, Romania, the Ukraine) are endeavouring to increase their potential, those which had hitherto no civilian nuclear facilities are now planning to build them (Belarus, Albania) or are contributing to projects in neighbouring countries (Estonia, Latvia, Poland). Within this context, the anti-nuclear argument has difficulty in finding a voice in the East

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.

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 ...

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

Materialistic Aspects of Raising Resource of Pressurized Water Reactors for Low-Power Nuclear Plants

International Nuclear Information System (INIS)

Parshin, A.M.; Muratov, O.E.

2005-01-01

The opportunity of using ships reactors for low-power nuclear plants is considered. Some aspects of working constructional materials on cases of water-water reactors of ships nuclear units are considered. Advantages of raising resource of ships reactors are shown

Sunken nuclear submarines

International Nuclear Information System (INIS)

Eriksen, V.O.

1990-01-01

The increasing number of accidents with nuclear submarines is a worriment to the general public. Five nuclear submarines are resting on the bottom of the North Atlantic. Design information on nuclear propulsion plants for submarines is classified. The author describes a potential generic nuclear submarine propulsion plant. Design information from the civilian nuclear industry, nuclear power plants, research reactors, nuclear cargo vessels and nuclear propelled icebreakers are used for illustration of relevant problems. A survey is given of nuclear submarines. Factors influencing the accident risks and safety characteristics of nuclear submarines are considered, and potential accident scenarios are described. The fission product content of the nuclear plant can be estimated, '' source terms'' can be guessed and potential release rates can be judged. The mechanisms of dispersion in the oceans is reviewed and compared with the dumping of radioactive waste in the Atlantic and other known releases. 46 refs., 49 figs., 14 tabs

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)

Nuclear proliferation-resistance and safeguards for future nuclear fuel cycle

International Nuclear Information System (INIS)

Kuno, Y.; Inoue, N.; Senzaki, M.

2009-01-01

Corresponding to the world nuclear security concerns, future nuclear fuel cycle (NFC) should have high proliferation-resistance (PR) and physical protection (PP), while promotion of the peaceful use of the nuclear energy must not be inhibited. In order to accomplish nuclear non-proliferation from NFC, a few models of the well-PR systems should be developed so that international community can recognize them as worldwide norms. To find a good balance of 'safeguard-ability (so-called extrinsic measure or institutional barrier)' and 'impede-ability (intrinsic feature or technical barrier)' will come to be essential for NFC designers to optimize civilian nuclear technology with nuclear non-proliferation, although the advanced safeguards with high detectability can still play a dominant role for PR in the states complying with full institutional controls. Accomplishment of such goal in a good economic efficiency is a future key challenge

Nuclear proliferation-resistance and safeguards for future nuclear fuel cycle

Science.gov (United States)

Kuno, Y.; Inoue, N.; Senzaki, M.

2009-03-01

Corresponding to the world nuclear security concerns, future nuclear fuel cycle (NFC) should have high proliferation-resistance (PR) and physical protection (PP), while promotion of the peaceful use of the nuclear energy must not be inhibited. In order to accomplish nuclear non-proliferation from NFC, a few models of the well-PR systems should be developed so that international community can recognize them as worldwide norms. To find a good balance of 'safeguard-ability (so-called extrinsic measure or institutional barrier)' and 'impede-ability (intrinsic feature or technical barrier)' will come to be essential for NFC designers to optimize civilian nuclear technology with nuclear non-proliferation, although the advanced safeguards with high detectability can still play a dominant role for PR in the states complying with full institutional controls. Accomplishment of such goal in a good economic efficiency is a future key challenge.

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

The reasons why Iran will never give up its nuclear program

International Nuclear Information System (INIS)

Bordes, Marjorie

2013-01-01

After having noticed that there is still an ambiguity about the civilian or military purpose of the Iranian nuclear program, and evoked the new commitments and propositions made by the new Iranian government, the author outlines that it would be an illusion to believe that Iran will ever give up its nuclear program. She outlines that this program, although it was started earlier, is a symbol of the 1979 revolution, that the development of civilian nuclear activities is an inalienable right for any country, that the geopolitical environment is a critical issue for Iran (the country is surrounded by potential threats). She evokes the development made by Iran to master the whole atom cycle and thus states that Iran will not give up its program after these substantial investments

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)

Office of Civilian Response Deployment Tracking System

Data.gov (United States)

US Agency for International Development — The purpose of OCR DTS is to establish, manage and track relevant Civilian Response Corps teams for deployment by sector experience, training, education etc.

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)

Nuclear energy and the environment

Energy Technology Data Exchange (ETDEWEB)

NONE

1971-07-01

Despite a generally excellent history of protecting man and his environment against the harmful effects of radioactive and thermal contamination from the peaceful uses of nuclear energy, civilian nuclear programmes in many countries are beset by a doubting and, in some cases, highly critical reaction from some sections of the public. The genesis and evolution of public controversy over nuclear power were explored in a number of papers presented at general and technical sessions during the Fourth Geneva Conference, and were the subject of a panel discussion on one afternoon. (author)

Nuclear Waste Fund management

International Nuclear Information System (INIS)

Mills, L.

1984-01-01

The Nuclear Waste Policy Acts requires that DOE enter into contracts with nuclear utilities and others to accept their nuclear wastes at some unspecified date, at some unspecified rate, hopefully starting in 1998. Contracts between DOE and the states, and with civilian and other government agencies must be sufficiently detailed to secure competitive bids on definable chunks of work at a fixed-cost basis with incentives. The need is stressed for a strong central program for the selection of contractors on the basis of competitive bidding on a fixed price basis to perform the task with defined deliverables

A Survey of Civilian Employee Attitudes

Science.gov (United States)

1989-06-01

U.S. Army Troop Support Command. The survey was conducted as part of an organizational diagnosis in preparation for the implementation of a civilian...survey as part of the program evaluation is recommended. Keywords: Surveys; Questionnaires; Employee attitudes; Attitude measurement; Organizational diagnosis .

Nuclear radiation in warfare

International Nuclear Information System (INIS)

Rotblat, J.

1986-01-01

The subject is covered in chapters, entitled: introduction; digest of nuclear weaponry (characteristics of nuclear weapons; effects of nuclear weapons other than ionizing radiation (fire-ball, fall-out, thermal radiation, blast wave, electromagnetic pulse); the nuclear arms race; war scenarios; biological effects of radiations on man (radiation doses; natural sources of radiation; acute effects of radiation; long-term somatic effects; genetic effects; factors affecting the biological response to radiation; internal exposure; synergistic effects; protection against radiation effects); radiations from nuclear explosions (initial radiation; fall-out; effects of fall-out on animal and plant life; contamination of water and food supplies by fall-out); radiation casualties in a nuclear war; effectiveness of civil defence; other warlike uses of radiation (attacks on civilian nuclear power installations; radiological warfare; terrorist activities); conclusion. (orig./HP) [de

Nuclear radiation in warfare

International Nuclear Information System (INIS)

Rotblat, J.

1981-01-01

The subject is covered in chapters, entitled: introduction; digest of nuclear weaponry (characteristics of nuclear weapons; effects of nuclear weapons other than ionizing radiation (fire-ball, fall-out, thermal radiation, blast wave, electromagnetic pulse); the nuclear arms race; war scenarios); biological effects of radiations on man (radiation doses; natural sources of radiation; acute effects of radiation; long-term somatic effects; genetic effects; factors affecting the biological response to radiation; internal exposure; synergistic effects; protection against radiation effects); radiations from nuclear explosions (initial radiation; fall-out; effects of fall-out on animal and plant life; contamination of water and food supplies by fall-out); radiation casualties in a nuclear war; effectiveness of civil defence; other warlike uses of radiation (attacks on civilian nuclear power installations; radiological warfare; terrorist activities); conclusion. (U.K.)

A review of the status of and prospects for nuclear marine propulsion

International Nuclear Information System (INIS)

Edwards, J.

1976-01-01

The review relates particularly to commercial nuclear merchant ships. The effects of the oil price escalation on world trade recession and price inflation are shown in relation to the rapid decrease in demand for new shipping and inflation in costs of any new construction. Economic analyses which began to be accepted as in favour of nuclear ships of relatively high power and high load factor have become somewhat less favourable, particularly from the point of view of higher investment costs and the presumed reluctance of shipowners to risk having these ships idle. On the other hand it is pointed out that the overall energy crisis remains and it is considered prudent to identify and seek solutions to those problems in nuclear ship propulsion which either still leave important uncertainties or which are likely to inhibit its use on a wide commercial scale. These are discussed under the following headings: economic assessments; safety acceptance and port entry; licensing and legislative problems; accidents and their consequences; decommissioning a nuclear ship; developments in the marine reactor designs. (U.K.)

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

LCA-ship. Design tool for energy efficient ships. A Life Cycle Analysis Program for Ships. Final report

Energy Technology Data Exchange (ETDEWEB)

Jiven, Karl; Sjoebris, Anders [MariTerm AB, Goeteborg (Sweden); Nilsson, Maria [Lund Univ. (Sweden). Stiftelsen TEM; Ellis, Joanne; Traegaardh, Peter; Nordstroem, Malin [SSPA Sweden AB, Goeteborg (Sweden)

2004-05-01

In order to make it easier to include aspects during ship design that will improve environmental performance, general methods for life cycle calculations and a prototype tool for LCA calculations of ships and marine transportation have been developed. The base of the life cycle analyses is a comprehensive set of life cycle data that was collected for the materials and consumables used in ship construction and vessel operations. The computer tool developed makes it possible to quickly and simply specify (and calculate) the use of consumables over the vessel's life time cycle. Special effort has been made to allow the tool to be used for different types of vessels and sea transport. The main result from the project is the computer tool LCA ship, which incorporates collected and developed life cycle data for some of the most important materials and consumables used in ships and their operation. The computer application also contains a module for propulsion power calculations and a module for defining and optimising the energy system onboard the vessel. The tool itself is described in more detail in the Computer application manual. The input to the application should, as much as possible, be the kind of information that is normally found in a shipping company concerning vessel data and vessel movements. It all starts with defining the ship to be analysed and continues with defining how the ship is used over the lifetime. The tool contains compiled and processed background information about specific materials and processes (LCA data) connected to shipping operations. The LCA data is included in the tool in a processed form. LCA data for steel will for example include the environmental load from the steel production, the process to build the steel structure of the ship, the scrapping and the recycling phase. To be able to calculate the environmental load from the use of steel the total amount of steel used over the life cycle of the ship is also needed. The

2013 Center for Army Leadership Annual Survey of Army Leadership (CASAL): Army Civilian Leaders

Science.gov (United States)

2014-05-30

Army civilian workforce with regard to gender and ethnic origin (Office of the Assistant G-1 for Civilian Personnel, 2013). The reported education...climates of perceived inequality . Civilian leader comments frequently referenced favoritism as reflecting cronyism, unfair personnel actions, and...interests of others, unequal enforcement of standards and discipline, and use of discretion in workplace justice. As demonstrated in previous CASAL

Civilian social work: serving the military and veteran populations.

Science.gov (United States)

Savitsky, Laura; Illingworth, Maria; DuLaney, Megan

2009-10-01

This article discusses social work practice areas for civilian social workers who provide services to military service members,veterans, and their families. These practice areas include education, child welfare, domestic violence, mental health, health care, substance abuse, and criminal justice. The authors examine the impact of the contemporary military lifestyle and current military operations on service members and their families in the context of these practice areas, with the goal of compelling civilian social workers to acknowledge their responsibility to competently serve military and veteran clients.

32 CFR 705.36 - Government transportation of civilians for public affairs purposes.

Science.gov (United States)

2010-07-01

....36 Government transportation of civilians for public affairs purposes. (a) General policy. (1... Assistant Secretary of Defense (Public Affairs), as appropriate. (8) Point to point transportation within... 32 National Defense 5 2010-07-01 2010-07-01 false Government transportation of civilians for...

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.)

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

Heterotopic ossification in civilians with lower limb amputations.

Science.gov (United States)

Matsumoto, Mary E; Khan, Mohammed; Jayabalan, Prakash; Ziebarth, Jessica; Munin, Michael C

2014-09-01

To report the incidence of symptomatic heterotopic ossification (HO) in a defined civilian amputee population, describe its characteristics, and compare these findings to published data in military amputees. Retrospective chart analysis from July 1998 to July 2009. Ambulatory amputee clinic within a large university medical center. Adults with lower limb amputation (N=158). Not applicable. Patients with symptomatic HO confirmed by radiographs. A total of 261 patients were evaluated; 158 met inclusion criteria, with 59% having traumatic etiology, 18% vascular etiology, 22% infection, and 1% tumor. Symptomatic HO was diagnosed in 36 (22.8%) patients, and 94% patients had mild HO on radiographic scoring. Rate of HO in amputations related to trauma was not increased compared with those of other etiologies. Surgical resection of the ectopic bone was required in 4 (11%) patients. HO is seen commonly after civilian lower limb amputation regardless of etiology. The prevalence was less than that observed in previous reports from military populations. This is the first report estimating the prevalence of HO in adult civilian amputees. Copyright © 2014 American Congress of Rehabilitation Medicine. Published by Elsevier Inc. All rights reserved.

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)

The Protection of Civilians: An Evolving Paradigm?

Directory of Open Access Journals (Sweden)

Stuart Gordon

2013-08-01

Full Text Available Whilst the protection of civilians (POC in conflict has been a recurring feature of the humanitarian discourse the same has not been true in military doctrines, where the protection of civilians has long been cast in terms of arms bearers upholding their responsibilities under international humanitarian law (IHL. However, opportunities for and pressures on military actors to develop more specific capacities and approaches in this field have grown: partly as a response to the changing nature, location and scope of conflict, particularly the increasing proportion of internal conflicts fought by irregular armed groups in urban environments. It is also a response to the scale and complexity of protection challenges in the Balkans, Rwanda, Darfur and Libya - each of which has clearly demonstrated that threats to civilians are complex and dynamic and that no single international actor is capable of mitigating them without significant support from other institutions (O’Callaghan and Pantuliano, 2007. Despite the enormous growth in opportunities for interaction between militaries and humanitarians there is only a very limited literature on their interaction over protection issues and evaluations of the emerging doctrines. Consequently this article charts the growth in military policies towards POC in the UN, UK, NATO and a range of other states as well as drawing attention to the challenges that still remain in operationalising responses.

Nuclear, biological and chemical warfare. Part I: Medical aspects of nuclear warfare.

Science.gov (United States)

Kasthuri, A S; Pradhan, A B; Dham, S K; Bhalla, I P; Paul, J S

1990-04-01

Casualties in earlier wars were due much more to diseases than to weapons. Mention has been made in history of the use of biological agents in warfare, to deny the enemy food and water and to cause disease. In the first world war chemical agents were used to cause mass casualties. Nuclear weapons were introduced in the second world war. Several countries are now involved in developing nuclear, biological and chemical weapon systems, for the mass annihilation of human beings, animals and plants, and to destroy the economy of their enemies. Recently, natural calamities and accidents in nuclear, chemical and biological laboratories and industries have caused mass instantaneous deaths in civilian population. The effects of future wars will not be restricted to uniformed persons. It is time that physicians become aware of the destructive potential of these weapons. Awareness, immediate protective measures and first aid will save a large number of persons. This series of articles will outline the medical aspects of nuclear, biological and chemical weapon systems in three parts. Part I will deal with the biological effects of a nuclear explosion. The short and long term effects due to blast, heat and associated radiation are highlighted. In Part II, the role of biological agents which cause commoner or new disease patterns is mentioned. Some of the accidents from biological warfare laboratories are a testimony to its potential deleterious effects. Part III deals with medical aspects of chemical warfare agents, which in view of their mass effects can overwhelm the existing medical resources, both civilian and military.(ABSTRACT TRUNCATED AT 250 WORDS)

The Nuclear Fuel Cycle Information System

International Nuclear Information System (INIS)

1987-02-01

The Nuclear Fuel Cycle Information System (NFCIS) is an international directory of civilian nuclear fuel cycle facilities. Its purpose is to identify existing and planned nuclear fuel cycle facilities throughout the world and to indicate their main parameters. It includes information on facilities for uranium ore processing, refining, conversion and enrichment, for fuel fabrication, away-from-reactor storage of spent fuel and reprocessing, and for the production of zirconium metal and Zircaloy tubing. NFCIS currently covers 271 facilities in 32 countries and includes 171 references

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.

Complex sequelae of psychological trauma among Kosovar civilian war victims.

Science.gov (United States)

Morina, Nexhmedin; Ford, Julian D

2008-09-01

The impact of war trauma on civilians may include, but also extend beyond, post-traumatic stress disorder (PTSD) to include complex sequelae such as those described by the syndrome of Disorders of Extreme Stress Not Otherwise Specified (DESNOS). In the present study, 102 civilian war victims were interviewed in Kosovo, assessing traumatic life events, PTSD, DESNOS, and depression. Full DESNOS rarely occurred (2% prevalence), however, clinically significant DESNOS symptoms of somatization, altered relationships, and altered systems of meaning were reported by between 24-42% of respondents. Although DESNOS symptoms were correlated with PTSD symptoms, DESNOS symptoms were associated with poorer overall psychological functioning, self-evaluations, satisfaction with life, and social support independent of the effects of PTSD. The findings suggest that DESNOS warrants attention in addition to PTSD in the assessment and treatment of civilians who have been exposed to war and genocide.

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...

Nuclear proliferation-resistance and safeguards for future nuclear fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Kuno, Y. [Japan Atomic Energy Agency (JAEA) Nuclear-Non-proliferation Science and Technology Centre (NPSTC), 2-4 Shirane Shirakata, Tokai-mura, Ibaraki, 319-1195 (Japan); University of Tokyo, Nuclear Engineering and Management, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8656 (Japan)], E-mail: kuno.yusuke@jaea.go.jp; Inoue, N. [Japan Atomic Energy Agency (JAEA) Nuclear-Non-proliferation Science and Technology Centre (NPSTC), 2-4 Shirane Shirakata, Tokai-mura, Ibaraki, 319-1195 (Japan); University of Tokyo, Nuclear Engineering and Management, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8656 (Japan); Senzaki, M. [Japan Atomic Energy Agency (JAEA) Nuclear-Non-proliferation Science and Technology Centre (NPSTC), 2-4 Shirane Shirakata, Tokai-mura, Ibaraki, 319-1195 (Japan)

2009-03-15

Corresponding to the world nuclear security concerns, future nuclear fuel cycle (NFC) should have high proliferation-resistance (PR) and physical protection (PP), while promotion of the peaceful use of the nuclear energy must not be inhibited. In order to accomplish nuclear non-proliferation from NFC, a few models of the well-PR systems should be developed so that international community can recognize them as worldwide norms. To find a good balance of 'safeguard-ability (so-called extrinsic measure or institutional barrier)' and 'impede-ability (intrinsic feature or technical barrier)' will come to be essential for NFC designers to optimize civilian nuclear technology with nuclear non-proliferation, although the advanced safeguards with high detectability can still play a dominant role for PR in the states complying with full institutional controls. Accomplishment of such goal in a good economic efficiency is a future key challenge.

Nuclear Waste Fund management

International Nuclear Information System (INIS)

Rosselli, R.

1984-01-01

The Nuclear Waste Policy Act of 1982 (NWPA) established two separate special bank accounts: the Nuclear Waste Fund (NWF) was established to finance all of the Federal Government activities associated with the disposal of High-Level Waste (HLW) or Spent Nuclear Fuel (SNF). The Interim Storage Fund (ISF) is the financial mechanism for the provision of Federal Interim Storage capacity, not to exceed 1900 metric tons of SNF at civilian power reactors. The management of these funds is discussed. Since the two funds are identical in features and the ISF has not yet been activated, the author's remarks are confined to the Nuclear Waste Fund. Three points discussed include legislative features, current status, and planned activities

The importance of civilian nursing organizations: integrative literature review.

Science.gov (United States)

Santos, James Farley Estevam Dos; Santos, Regina Maria Dos; Costa, Laís de Miranda Crispim; Almeida, Lenira Maria Wanderley Santos de; Macêdo, Amanda Cavalcante de; Santos, Tânia Cristina Franco

2016-06-01

to identify and analyze evidence from studies about the importance of civilian nursing organizations. an integrative literature review, for which searches were conducted in the databases LILACS, PubMed/MEDLINE, SciELO, BDENF, and Scopus. sixteen articles published between the years 2004-2013 were selected, 68.75% of which were sourced from Brazilian journals and 31.25% from American journals. civilian nursing organizations are important and necessary, because they have collaborated decisively in nursing struggles in favor of the working class and society in general, and these contributions influence different axes of professional performance.

Emerging Options and Opportunities in Civilian Aeronautics

Science.gov (United States)

Bushnell, Dennis M.

2012-01-01

This paper addresses the major problems/issues with civilian aeronautics going forward, the contextual ongoing technology revolutions, the several emerging civilian aeronautical "Big Ideas" and associated enabling technological approaches. The ongoing IT Revolution is increasingly providing, as 5 senses virtual presence/reality becomes available, along with Nano/Molecular Manufacturing, virtual alternatives to Physical transportation for both people and goods. Paper examines the potential options available to aeronautics to maintain and perhaps grow "market share" in the context of this evolving competition. Many of these concepts are not new, but the emerging technology landscape is enhancing their viability and marketability. The concepts vary from the "interesting" to the truly revolutionary and all require considerable research. Paper considers the speed range from personal/general aviation to supersonic transports and technologies from energetics to fabrication.

Siting of nuclear facilities. Selections from Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Buchanan, J.R.

1976-07-01

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

Siting of nuclear facilities. Selections from Nuclear Safety

International Nuclear Information System (INIS)

Buchanan, J.R.

1976-07-01

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria

The sea transport of irradiated nuclear fuel

International Nuclear Information System (INIS)

Miller, M.L.

1995-01-01

The paper describes the development of a transport system dedicated to the sea transport of irradiated nuclear fuel. It reviews the background to why shipments were required and the establishment of a specialist shipping company, Pacific Nuclear Transport Limited. A description of the ships, flasks and other equipment utilized is provided, together with details of key procedures implemented to ensure safety and customer satisfaction

Keeping the lid on nuclear arms

International Nuclear Information System (INIS)

Milhollin, G.; Weeks, J.

1991-01-01

In November 1990 Brazil and Argentina agreed not to produce nuclear weapons and to allow mutual inspections of their secret nuclear sites. This exciting move towards nuclear arms control may form the basis of a model of international inspection which other countries may seek to follow. However, neither country will yet unconditionally accept the verification scale proposed by the International Atomic Energy Agency (IAEA). The IAEA seeks to ensure that civilian nuclear materials are not diverted for military use. Military authorities in both countries oppose the plan. It is anticipated that existing difficulties will be overcome. (UK)

The doctor and nuclear warfare

International Nuclear Information System (INIS)

Anon.

1982-01-01

At the 34th World Medical Assembly in Lisbon in 1981 the World Medical Association adopted a motion proposed by the American Medical Association that national medical associations should develop programs to educate the civilian population on the medical consequences of nuclear war. This article discusses the attitude the medical professions should have, should nuclear warfare in some form confront them in the future. The conclusion is drawn that defence against nuclear warfare is only a part of civil defence against any disaster, including the natural disasters such as flood and fire and the man-made disasters of transport accidents, even of problems at nuclear plants designed to supply energy

Characteristics and Pay of Federal Civilian Employees

National Research Council Canada - National Science Library

2007-01-01

...) examined the attributes of a subset of the government's civilian workforce: the roughly 1.4 million salaried workers not including employees of the Postal Service who fill full-time permanent positions in the executive branch...

Office of Civilian Radioactive Waste Management annual report to Congress

International Nuclear Information System (INIS)

1988-08-01

This is the fifth Annual Report to Congress by the Office of Civilian Radioactive Waste Management (OCRWM). The report covers the activities and expenditures of OCRWM during fiscal year 1987, which ended on September 30, 1987. The activities and accomplishments of OCRWM during fiscal year 1987 are discussed in chapters 1 through 9 of this report. The audited financial statements of the Nuclear Waste Fund are provided in chapter 10. Since the close of the fiscal year, a number of significant events have occurred. Foremost among them was the passage of the Nuclear Waste Policy Amendments Act of 1987 (Amendments Act) on December 21, 1987, nearly 3 months after the end of the fiscal year covered by this report. As a result, some of the plans and activities discussed in chapters 1 through 9 are currently undergoing significant change or are being discontinued. Most prominent among the provisions of the Amendments Act is the designation of Yucca Mountain, Nevada, as the only candidate first repository site to be characterized. Therefore, the site characterization plans for Deaf Smith, Texas, and Hanford, Washington, discussed in chapter 3, will not be issued. The refocusing of the waste management program under the Amendments Act is highlighted in the epilogue, chapter 11. 68 refs., 7 figs., 7 tabs

Nuclear power falling to pieces

International Nuclear Information System (INIS)

Moberg, Aa.

1985-01-01

The international development during the 80s is reviewed. It is stated that the construction of plants has come to a standstill. The forecasting of nuclear power as a simple and cheap source of energy has been erroneous because of cracks and leakage, unsolved waste problems and incidents. Nuclear power companies go into liquidation and reactors are for sale. Sweden has become the country with most nuclear power per capita mainly due to its controlled decommissioning. The civilian nuclear power makes the proliferation of nuclear weapons possible. With 324 reactors all over the world, a conventional war may cause disasters like Hiroshima. It is stated that the nuclear power is a dangerous and expensive source of energy and impossible to manage. (G.B.)