ENEN - European nuclear engineering network

International Nuclear Information System (INIS)

Comsa, Olivia; Paraschiva, M.V.; Banutoiu, Maria

2002-01-01

The paper presents the main objectives and expected results of European Project FP5 - ENEN - 'European Nuclear Engineering Network'. The underlying objective of the work is safeguarding the nuclear knowledge and expertise through the preservation of higher nuclear engineering education. Co-operation between universities and universities and research centres, will entail a better use of dwindling teaching capacity, scientific equipment and research infrastructure. 'Today, the priorities of the scientific community regarding basic research lie elsewhere than in nuclear sciences. Taken together, these circumstances create a significantly different situation from three to four decades ago when much of the present competence base was in fact generated. In addition, many of the highly competent engineers and scientists, who helped create the present nuclear industry, and its regulatory structure, are approaching retirement age. These competence issues need to be addressed at Community level and a well designed Community research and training programme should play a role that is more important than ever before. This is an area where the concept of an European research area should be further explored'. The outcome from this project should be a clear road map for the way ahead in nuclear engineering education in Europe. The underlying objective of the concerted action is the preservation of nuclear knowledge and expertise through the preservation of higher nuclear engineering education. 'Many diverse technologies, currently serving nations world-wide, would be affected by an inadequate number of future nuclear scientists and engineers. Nuclear technology is widespread and multidisciplinary: nuclear and reactor physics, thermal hydraulics and mechanics, material science, chemistry, health science, information technology and a variety of other areas. Yet the advancement of this technology, with all its associated benefits, will be threatened if not curtailed unless the

Handbook of advanced nuclear hydrogen safety. 1st edition

International Nuclear Information System (INIS)

Hino, Ryutaro; Takegami, Hiroaki; Ogawa, Toru

2017-03-01

In the aftermath of the Fukushima nuclear accident, safety measures against hydrogen in severe accident has been recognized as a serious technical problem in Japan. Therefore, efforts have begun to form a common knowledge base between nuclear engineers and experts on combustion and explosion, and to secure and improve future nuclear energy safety. As one of such activities, we have prepared the 'Handbook of Advanced Nuclear Hydrogen Safety'. A handbook committee consisting of Japanese experts in the fields of nuclear and combustion-explosion in universities, nuclear companies, electric companies and research institutes was established in 2012. The objective and consents of the handbook were determined, and the outline of the contents was decided. The concepts of the handbook are as follows: to show advanced nuclear hydrogen safety technologies that nuclear engineers should understand, to show hydrogen safety points to make combustion-explosion experts cooperate with nuclear engineers, to expand information on water radiolysis considering the situation from just after the Fukushima accidents and to the waste management necessary for decommissioning after the accident etc. Many experts have participated to manuscript preparation, which was the first step of forming a hydrogen community across the boundaries of fields. The hydrogen community is expected to grow along with its improvement to the knowledge base on nuclear hydrogen safety. (author)

Nuclear reactor engineering: Reactor systems engineering. Fourth edition, Volume Two

International Nuclear Information System (INIS)

Glasstone, S.; Sesonske, A.

1994-01-01

This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in the design and operation of nuclear power plants. Extensively updated, the fourth edition includes new materials on reactor safety and risk analysis, regulation, fuel management, waste management and operational aspects of nuclear power. This volume contains the following: the systems concept, design decisions, and information tools; energy transport; reactor fuel management and energy cost considerations; environmental effects of nuclear power and waste management; nuclear reactor safety and regulation; power reactor systems; plant operations; and advanced plants and the future

Advanced plant engineering and construction of Japanese ABWRs

International Nuclear Information System (INIS)

Gotoh, N.; Sumikawa, J.; Yoshida, N.; Yoshida, M.

1998-01-01

Remarkable improvement has been made in recent nuclear power plant design and construction in Japan. These many improved engineering technologies has been made a good use in the lately commercial operated two world's first 1,356MWe ABW's (Advanced Boiling Water Reactors), and made a great contribution to the smooth progress and the completion of a highly reliable plant construction. Especially, two engineering technologies, (1), three-dimensional computer aided design system through engineering data-base, and (2), large scale modularising construction method, have been successfully applied as the integrated engineering technologies of the plant construction. And two integrated reviews, 'integrated design review, confirmation of new and changed design and prevention of failure recurrence' in the design stage, and 'constructing plant review' at the site, have been widely and systematically conducted as a link in the chain of steady reliability improvement activities. These advanced and/or continuous and steady technologies are one of most important factors for high reliability through the entire lifetime of a nuclear plant, including planning, design, construction, operation and maintenance stages. (author)

The midwest workshop on preparing nuclear engineering professionals

International Nuclear Information System (INIS)

Danofsky, R.A.; Rohach, A.F.; Spinrad, B.I.; Nodean, W.C.

1988-01-01

Personnel training and education are activities of major importance for nuclear utilities and represent fruitful areas for possible cooperation between utilities and educational institutions. Utility personnel have a need for continuing education through advanced and undergraduate degree programs and special courses. Nuclear engineering departments are in a position to meet at least some of these needs. The purpose of the workshop described in this paper was to explore ways to increase the dialogue between utilities and universities and to bring faculty and utility personnel together to discuss the educational needs of nuclear utilities. The workshop was held May 25-27, 1988, at Iowa State University. Planning for the workshop was coordinated by a steering committee with representation from the Department of Nuclear Engineering at Iowa State University, Iowa Electric Light and Power Company (IEL ampersand P), and Kirkwood Community College at Cedar Rapids, Iowa. Participants represented nuclear utilities, nuclear engineering departments, 2- and 4-yr colleges, a nuclear training organization, and the Institute of Nuclear Power Operations

Matching grant program for university nuclear engineering education

International Nuclear Information System (INIS)

Bajorek, Stephen M.

2002-01-01

The grant augmented funds from Westinghouse Electric Co. to enhance the Nuclear Engineering program at KSU. The program was designed to provide educational opportunities and to train engineers for careers in the nuclear industry. It provided funding and access to Westinghouse proprietary design codes for graduate and undergraduate studies on topics of current industrial importance. Students had the opportunity to use some of the most advanced nuclear design tools in the industry and to work on actual design problems. The WCOBRA/TRAC code was used to simulate loss of coolant accidents (LOCAs)

Development of Nuclear Engineering Educational Program at Ibaraki University with Regional Collaboration

Science.gov (United States)

Matsumura, Kunihito; Kaminaga, Fumito; Kanto, Yasuhiro; Tanaka, Nobuatsu; Saigusa, Mikio; Kikuchi, Kenji; Kurumada, Akira

The College of Engineering, Ibaraki University is located at the Hitachi city, in the north part of Ibaraki prefecture. Hitachi and Tokai areas are well known as concentration of advanced technology center of nuclear power research organizations. By considering these regional advantages, we developed a new nuclear engineering educational program for students in the Collage of Engineering and The Graduate School of Science and Engineering of Ibaraki University. The program is consisted of the fundamental lectures of nuclear engineering and nuclear engineering experiments. In addition, several observation learning programs by visiting cooperative organizations are also included in the curriculum. In this paper, we report about the progress of the new educational program for nuclear engineering in Ibaraki University.

4+D digital engineering for advanced nuclear energy systems

International Nuclear Information System (INIS)

Jeong, S. G.; Suh, K. Y.; Nam, S. K.

2007-01-01

Nuclear power plants (NPPs) require massive quantity of data during the design, construction, operation, maintenance and decommissioning stages because of their special features like size, cost, radioactivity, and so forth. The system engineering thus calls for a fully automated way of managing the information flow spanning their life cycle. In line with practice in disciplines of naval architecture, aerospace engineering, and automotive manufacturing, the paper proposes total digital systems engineering based on three-dimensional (3D) computer-aided design (CAD) models. The signature in the proposal lies with the four-plus-dimensional (4 + D) Technology T M, a critical know-how for digital management. The so-called OPIUM (Optimized Plant Integrated Ubiquitous Management) features a 4 + D Technology T M for nuclear energy systems engineering. The technology proposed in the 3D space and time plus cost coordinates, i.e. 4 + D, is the backbone of digital engineering in the nuclear systems design and management. Based on an integrated 3D configuration management system, OPIUM consists of solutions NOTUS (Nuclear Optimization Technique Ubiquitous System), VENUS (Virtual Engineering Nuclear Ubiquitous System), INUUS (Informatics Nuclear Utilities Ubiquitous System), JANUS (Junctional Analysis Numerical Ubiquitous System) and EURUS (Electronic Unit Research Ubiquitous System). These solutions will help initial simulation capability for NPPs to supply the crucial information. NOTUS contributes to reducing the construction cost of the NPPs by optimizing the component manufacturing procedure and the plant construction process. Planning and scheduling construction projects can thus benefit greatly by integrating traditional management techniques with digital process simulation visualization. The 3D visualization of construction processes and the resulting products intrinsically afford most of the advantages realized by incorporating a purely schedule level detail based the 4

Human factors design review guidelines for advanced nuclear control room technologies

International Nuclear Information System (INIS)

O'Hara, J.; Brown, W.; Granda, T.; Baker, C.

1991-01-01

Advanced control rooms (ACRs) for future nuclear power plants are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes the rationale, general approach, and initial development of an NRC Advanced Control Room Design Review Guideline. 20 refs., 1 fig

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 engineering career - Phase 2 Argentina. Final report

International Nuclear Information System (INIS)

1993-01-01

The objective of the project was to consolidate and extend the conditions necessary for the development of nuclear technology, and to observe the problems posed by the application of the nuclear energy through the increase and improvement of the scientific and technical infrastructure. The immediate objective of the project was to complete the advancement of research and development activities in nuclear engineering at the Centro Atomico Bariloche and Instituto Balseiro

Nuclear chemical engineering

International Nuclear Information System (INIS)

Lee, Geon Jae; Shin, Young Jun

1989-08-01

The contents of this book are introduction of chemical engineering and related chemistry on an atomic reactor, foundation of the chemistry nuclear chemical engineering, theory on nuclear engineering, the cycle of uranium and nuclear fuel, a product of nuclear division, nuclear reprocessing, management of spent fuel separation of radioisotope, materials of an atomic reactor, technology and chemistry related water in atomic reactors and utilization of radioisotope and radiation. This book has the exercises and reference books for the each chapter.

BS degree in nuclear engineering or a nuclear option

International Nuclear Information System (INIS)

Williams on, T.G.

1988-01-01

Many nuclear engineering educators are concerned about the health of nuclear engineering academic departments. As part of a review of the BS nuclear engineering degree program at the University of Virginia, the authors surveyed several local utilities with operating nuclear plants about their needs for nuclear engineering graduates. The perception of many of the utility executives about a nuclear engineering degree and about a nuclear option in another engineering curriculum does not agree with the way the authors view these two degrees. The responses to two of the survey questions were of particular interest: (1) does your company have a preference between nuclear engineering graduates and graduates in other fields with a nuclear option? (2) what do you consider to be a minimum level of education in nuclear engineering for a nuclear option in mechanical engineering? All of the four utilities that were surveyed stated a preference for mechanical or electrical engineers with a nuclear option, although two indicated that there are certain jobs for which a nuclear engineering graduate is desired

Education and training in nuclear science/engineering in Taiwan

International Nuclear Information System (INIS)

Chung, C.

1994-01-01

The present status of nuclear education and training in Taiwan is reviewed. The nuclear science/engineering program has been established in Taiwan under the College of Nuclear Science at the National Tsing Hua University since 1956; it remains the only program among 123 universities and colleges in Taiwan where education and training in nuclear fields are offered. The program, with 52 faculty members, offers advanced studies leading to BSc, MSc, and PhD degrees. Lectures and lab classes are given to 600 students currently registered in the program. Career placement program geared for the 200 graduate and 400 undergraduate students is to orientate them into the local nuclear power utilities as well as agricultural, medical, industrial, academic and governmental sectors where nuclear scientists and engineers at all levels are needed. 8 refs., 1 fig

Advanced nuclear reactor and nuclear fusion power generation

International Nuclear Information System (INIS)

2000-04-01

This book comprised of two issues. The first one is a advanced nuclear reactor which describes nuclear fuel cycle and advanced nuclear reactor like liquid-metal reactor, advanced converter, HTR and extra advanced nuclear reactors. The second one is nuclear fusion for generation energy, which explains practical conditions for nuclear fusion, principle of multiple magnetic field, current situation of research on nuclear fusion, conception for nuclear fusion reactor and economics on nuclear fusion reactor.

Human factor engineering applied to nuclear power plant design

International Nuclear Information System (INIS)

Manrique, A.; Valdivia, J.C.; Jimenez, A.

2001-01-01

For the design and construction of new nuclear power plants as well as for maintenance and operation of the existing ones new man-machine interface designs and modifications are been produced. For these new designs Human Factor Engineering must be applied the same as for any other traditional engineering discipline. Advantages of implementing adequate Human Factor Engineering techniques in the design of nuclear reactors have become not only a fact recognized by the majority of engineers and operators but also an explicit requirement regulated and mandatory for the new designs of the so called advanced reactors. Additionally, the big saving achieved by a nuclear power plant having an operating methodology which significantly decreases the risk of operating errors makes it necessary and almost vital its implementation. The first step for this is preparing a plan to incorporate all the Human Factor Engineering principles and developing an integral design of the Instrumentation and Control and Man-machine interface systems. (author)

Experience with a top-down versus bottom-up nuclear engineering educational paradigm

International Nuclear Information System (INIS)

Harms, A.A.

1991-01-01

Nuclear engineering courses are generally taught from a top-down pedagogical perspective; i.e., one begins with a body of knowledge drawn from advanced nuclear science, engineering, and experience and from this distills a selected part to match the intellectual capacity of the class. This pedagogical approach has evidently been most effect at the graduate level of instruction as evidenced by the ready entry of masters and doctoral students into the professions. A schematic depiction of this approach is suggested and is extended to the undergraduate level of nuclear engineering education

Advanced I and C systems for nuclear power plants

International Nuclear Information System (INIS)

Bock, H.W.; Graf, A.; Hofmann, H.

1995-01-01

Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally, specific requirements coming from the nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. The main features of these systems are the clear task related architecture with adaptable redundancy, the consequent application of standards for interfaces and communication, comprehensive tools for easy design and service and a highly ergonomic screen based man-machine-interface. The engineering tasks are supported by an integrated engineering system, which has the capacity for design, test and diagnosis of all I and C functions and the related equipment. TELEPERM XP is designed to optimally perform all automatic functions, which require no nuclear specific qualification. This includes all sequences and closed-loop controls as well as most man-machine-interface functions. TELEPERM XS is designed for all control tasks which require a nuclear specific qualification. This especially includes all functions to initiate automatic countermeasures to prevent or to cope with accidents. By use of the complementary I and C systems TELEPERM XP and TELEPERM XS, economical as well as advanced plant automation and man-machine-interfaces can be implemented into Nuclear Plants, assuring the compliance with the relevant international safety standards. (author). 10 figs

Advanced I and C systems for nuclear power plants

International Nuclear Information System (INIS)

Bock, H.W.; Graf, A.; Hofmann, H.

1997-01-01

Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally specific requirements arising from nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. The main features of these systems are a clear task related architecture with adaptable redundancy, a consequent application of standards for interfaces and communication, comprehensive tools for easy design and service and a highly ergonomic screen based man-machine-interface. The engineering tasks are supported by an integrated engineering system, which has the capacity for design, test and diagnosis of all I and C functions and the related equipment. TELEPERM XP is designed to optimally perform all automatic functions, which require no nuclear specific qualification. This includes all sequences and closed-loop controls as well as most man-machine-interface functions. TELEPERM XS is designed for all control tasks which require a nuclear specific qualification. This especially includes all function to initiated automatic countermeasures to prevent or to cope with accidents. By use of the complementary I and C systems TELEPERM XP and TELEPERM XS, advanced and likewise economical plant automation and man-machine-interfaces can be implemented into Nuclear Power Plant, assuring compliance with the relevant international safety standards. (author). 10 figs

Advanced I and C systems for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Bock, H W; Graf, A; Hofmann, H [Siemens AG, Erlangen (Germany)

1997-07-01

Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally specific requirements arising from nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. The main features of these systems are a clear task related architecture with adaptable redundancy, a consequent application of standards for interfaces and communication, comprehensive tools for easy design and service and a highly ergonomic screen based man-machine-interface. The engineering tasks are supported by an integrated engineering system, which has the capacity for design, test and diagnosis of all I and C functions and the related equipment. TELEPERM XP is designed to optimally perform all automatic functions, which require no nuclear specific qualification. This includes all sequences and closed-loop controls as well as most man-machine-interface functions. TELEPERM XS is designed for all control tasks which require a nuclear specific qualification. This especially includes all function to initiated automatic countermeasures to prevent or to cope with accidents. By use of the complementary I and C systems TELEPERM XP and TELEPERM XS, advanced and likewise economical plant automation and man-machine-interfaces can be implemented into Nuclear Power Plant, assuring compliance with the relevant international safety standards. (author). 10 figs.

Nuclear engineering vocabulary

International Nuclear Information System (INIS)

Dumont, X.; Andrieux, C.

2001-01-01

The members of the CSTNIN - the Special Commission for Nuclear Engineering Terminology and Neology - have just produced a Nuclear Engineering Vocabulary, published by SFEN. A 120-page document which, to date, includes 400 nuclear engineering terms or expressions. For each term or expression, this Glossary gives: the primary and secondary subject field in which it is applied, a possible abbreviation, its definition, a synonym if appropriate, any relevant comments, any associated word(s), the English equivalent, its status on the date of publication of the Glossary. (author)

Earthquake engineering for nuclear facilities

CERN Document Server

Kuno, Michiya

2017-01-01

This book is a comprehensive compilation of earthquake- and tsunami-related technologies and knowledge for the design and construction of nuclear facilities. As such, it covers a wide range of fields including civil engineering, architecture, geotechnical engineering, mechanical engineering, and nuclear engineering, for the development of new technologies providing greater resistance against earthquakes and tsunamis. It is crucial both for students of nuclear energy courses and for young engineers in nuclear power generation industries to understand the basics and principles of earthquake- and tsunami-resistant design of nuclear facilities. In Part I, "Seismic Design of Nuclear Power Plants", the design of nuclear power plants to withstand earthquakes and tsunamis is explained, focusing on buildings, equipment's, and civil engineering structures. In Part II, "Basics of Earthquake Engineering", fundamental knowledge of earthquakes and tsunamis as well as the dynamic response of structures and foundation ground...

Advanced engineering environment collaboration project.

Energy Technology Data Exchange (ETDEWEB)

Lamph, Jane Ann; Pomplun, Alan R.; Kiba, Grant W.; Dutra, Edward G.; Dankiewicz, Robert J.; Marburger, Scot J.

2008-12-01

The Advanced Engineering Environment (AEE) is a model for an engineering design and communications system that will enhance project collaboration throughout the nuclear weapons complex (NWC). Sandia National Laboratories and Parametric Technology Corporation (PTC) worked together on a prototype project to evaluate the suitability of a portion of PTC's Windchill 9.0 suite of data management, design and collaboration tools as the basis for an AEE. The AEE project team implemented Windchill 9.0 development servers in both classified and unclassified domains and used them to test and evaluate the Windchill tool suite relative to the needs of the NWC using weapons project use cases. A primary deliverable was the development of a new real time collaborative desktop design and engineering process using PDMLink (data management tool), Pro/Engineer (mechanical computer aided design tool) and ProductView Lite (visualization tool). Additional project activities included evaluations of PTC's electrical computer aided design, visualization, and engineering calculations applications. This report documents the AEE project work to share information and lessons learned with other NWC sites. It also provides PTC with recommendations for improving their products for NWC applications.

Advanced engineering environment collaboration project

International Nuclear Information System (INIS)

Lamph, Jane Ann; Pomplun, Alan R.; Kiba, Grant W.; Dutra, Edward G.; Dankiewicz, Robert J.; Marburger, Scot J.

2008-01-01

The Advanced Engineering Environment (AEE) is a model for an engineering design and communications system that will enhance project collaboration throughout the nuclear weapons complex (NWC). Sandia National Laboratories and Parametric Technology Corporation (PTC) worked together on a prototype project to evaluate the suitability of a portion of PTC's Windchill 9.0 suite of data management, design and collaboration tools as the basis for an AEE. The AEE project team implemented Windchill 9.0 development servers in both classified and unclassified domains and used them to test and evaluate the Windchill tool suite relative to the needs of the NWC using weapons project use cases. A primary deliverable was the development of a new real time collaborative desktop design and engineering process using PDMLink (data management tool), Pro/Engineer (mechanical computer aided design tool) and ProductView Lite (visualization tool). Additional project activities included evaluations of PTC's electrical computer aided design, visualization, and engineering calculations applications. This report documents the AEE project work to share information and lessons learned with other NWC sites. It also provides PTC with recommendations for improving their products for NWC applications

Educating nuclear engineers at German universities

International Nuclear Information System (INIS)

Knorr, J.

1995-01-01

Nuclear technology is a relatively young university discipline. Yet, as a consequence of the declining public acceptance of the peaceful use of nuclear power, its very existence is already being threatened at many universities. However, if Germany needs nuclear power, which undoubtedly is the case, highly qualified, committed experts are required above all. Nuclear technology develops internationally. Consequently, also university education must meet international standards. Generally, university education has been found to be the most effective way of increasing the number of scientific and engineering personnel. Nuclear techniques have meanwhile found acceptance in many other scientific disciplines, thus advancing those branches of science. Teaching needs research; like research in nucelar technology at the national research centers, also the universities are suffering massive financial disadvantages. Research is possible only if outside funds are solicited, which increase dependency and decreases basic research. (orig.) [de

Development of design and analysis software for advanced nuclear system

International Nuclear Information System (INIS)

Wu Yican; Hu Liqin; Long Pengcheng; Luo Yuetong; Li Yazhou; Zeng Qin; Lu Lei; Zhang Junjun; Zou Jun; Xu Dezheng; Bai Yunqing; Zhou Tao; Chen Hongli; Peng Lei; Song Yong; Huang Qunying

2010-01-01

A series of professional codes, which are necessary software tools and data libraries for advanced nuclear system design and analysis, were developed by the FDS Team, including the codes of automatic modeling, physics and engineering calculation, virtual simulation and visualization, system engineering and safety analysis and the related database management etc. The development of these software series was proposed as an exercise of development of nuclear informatics. This paper introduced the main functions and key techniques of the software series, as well as some tests and practical applications. (authors)

Licensed bases management for advanced nuclear plants

International Nuclear Information System (INIS)

O'Connell, J.; Rumble, E.; Rodwell, E.

2001-01-01

Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

Licensed bases management for advanced nuclear plants

Energy Technology Data Exchange (ETDEWEB)

O' Connell, J [Duke Engineering and Services, Marlborough, MA (United States); Rumble, E; Rodwell, E [EPRI, Palo Alto, CA (United States)

2001-07-01

Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

Building an integrated nuclear engineering and nuclear science human resources pipeline at the Idaho National Engineering and Environmental Laboratory

International Nuclear Information System (INIS)

Sneed, A.; Sikorski, B.; Lineberry, M.; Jolly, J.

2004-01-01

In a joint effort with the Argonne National Laboratory - West (ANL-W), the Idaho National Engineering and Environmental Laboratory (INEEL) has assumed the lead role for nuclear energy reactor research for the United States Government. In 2005, these two laboratories will be combined into one entity, the Idaho National Laboratory (INL). There are two objectives for the INL: (1) to act as the lead systems integrator for the Department of Energy's Office of Nuclear Energy Science and Technology and, (2) to establish a Center for Advanced Energy Studies. Focusing on the Center for Advanced Energy Studies, this paper presents a Human Resources Pipeline Model outlining a nuclear educational pathway that leads to university and industry research partnerships. The pathway progresses from education to employment and into retirement. Key to the model is research and mentoring and their impact upon each stage. The Center's success will be the result of effective and advanced communications, faculty/student involvement, industry support, inclusive broadbased involvement, effective long-term partnering, and increased federal and state support. (author)

Human factor engineering applied to nuclear power plant design

International Nuclear Information System (INIS)

Manrique, A.; Valdivia, J.C.

2007-01-01

Advantages of implementing adequate Human Factor Engineering techniques in the design of nuclear reactors have become not only a fact recognized by the majority of engineers and operators but also an explicit requirement regulated and mandatory for the new designs of the so called advanced reactors. The first step for this is preparing a plan to incorporate all the Human Factor Engineering principles and developing an integral design of the Instrumentation and Control and Man-machine interface systems. Such a plan should state: -) Activities to be performed, and -) Creation of a Human Factor Engineering team adequately qualified. The Human Factor Engineering team is an integral part of the design team and is strongly linked to the engineering organizations but simultaneously has independence to act and is free to evaluate designs and propose changes in order to enhance human behavior. TECNATOM S.A. (a Spanish company) has been a part of the Design and Human Factor Engineering Team and has collaborated in the design of an advanced Nuclear Power Plant, developing methodologies and further implementing those methodologies in the design of the plant systems through the development of the plant systems operational analysis and of the man-machine interface design. The methodologies developed are made up of the following plans: -) Human Factor Engineering implementation in the Man-Machine Interface design; -) Plant System Functional Requirement Analysis; -) Allocation of Functions to man/machine; -) Task Analysis; -) Human-System Interface design; -) Control Room Verification and -) Validation

Advanced nuclear turbojet powerplant characteristics summary for supersonic aircraft

International Nuclear Information System (INIS)

Larson, John W.

1959-01-01

The estimated powerplant characteristics of an advanced nuclear powerplant intended for use in a nuclear supersonic manned airplane is contained in this report. This nuclear powerplant consists of a 575 MW, high temperature, lithium-cooled, solid fuel element-type reactor coupled to six turbojet engines especially designed for a supersonic nuclear airplane. The lithium coolant passes from the reactor at 2000F directly to the engine radiators without the use of an intermediate heat exchanger. The engines are fitted with burners enabling the thrust produced by the nuclear powerplant to be augmented by the use of chemical fuel for the take-off, transonic acceleration and landing portions of the flight. The powerplant components have been selected for a maximum thrust-to-weight ratio at Mach 3 and 55,000 feet altitude on nuclear heat only operation compromised for net thrust produced with chemical fuel augmentation during the transonic portion of flight. The power plant data presented, therefore, are primarily applicable to an all supersonic mission on nuclear heat alone. The powerplant data presented in this report are an extension of data contained in PWAC-243, 'NJ-14 All-Nuclear Supersonic Bomber Powerplant Characteristics Summary, March 11, 1958', to a higher reactor power. In addition, the engine compressor pressure ratio has been increased to improve transonic thrust characteristics. Weight data are tabulated for the 575 MW powerplant. The engine envelope based on preliminary radiator size estimates is illustrated. A liquid metal system flow schematic and piping data are included. Shield information including reactor shield outline, assumptions, weights, and direct dose pattern at 50 feet is also included. Estimated performance on nuclear heat only operation and nuclear heat plus burning is presented for an envelope of flight conditions.

Introducing Knowledge Management in Study Program of Nuclear Engineering

International Nuclear Information System (INIS)

Pleslic, S.

2012-01-01

Nuclear engineering is the branch of engineering concerning application of the fission as well as the fusion of atomic nuclei, and the application of other sub-atomic physics, based on the principles of nuclear physics. In the sub-field of nuclear fission there are many investigations of interactions and maintaining of systems and components like nuclear reactors and nuclear power plants. The field also includes the study of different applications of ionizing radiation (medicine, agriculture...), nuclear safety, the problems of thermodynamics transport, nuclear materials and nuclear fuels, and other related technologies like radioactive waste management. In the area of nuclear science and engineering a big amount of knowledge has been accumulated over the last decades. Different levels of nuclear knowledge were considered in different ways and they were taught to different parts of population as a general human culture and as a general scientific-technical-technological culture (high schools, nuclear information centres, training centres, universities...). An advanced level of nuclear knowledge has been accumulated by many experienced workers, specialists and experts in all nuclear and nuclear-related fields and applications. In the last 20 years knowledge management has established itself as a discipline of enabling individuals, teams and whole organizations to create, share and apply knowledge collectively and systematically, with goal to better achieve their objectives. Also, knowledge management became key strategic approach for management of intellectual assets and knowledge that can improve safety, efficiency and innovation, and lead to preserve and enhance current knowledge. Knowledge management could be applied in education, training, networking, human resource development and capacity building, sharing, pooling and transferring knowledge form centres of knowledge to centres of growth. Considering the critical importance of nuclear knowledge it is important

Engineering opportunities in nuclear engineering

International Nuclear Information System (INIS)

Walton, D.G.

1980-01-01

The pattern of education and training of Nuclear Engineers in the UK is outlined under the headings; degree courses for professional engineers, postgraduate courses, education of technician engineers. Universities which offer specific courses are stated and useful addresses listed. (UK)

History of nuclear engineering curricula

International Nuclear Information System (INIS)

Murphy, G.

1975-01-01

With the realization that nuclear energy had a vast potential for peacetime development, universities throughout the country began to develop courses in nuclear energy. A pioneering educational effort was necessary because there was an inadequate number of trained faculty, no established curricula, no textbooks, and very little suitable equipment. Nevertheless, by the early 1950's, several programs in nuclear science and engineering were beginning to provide instruction to potential nuclear engineers. At that time, the American Society for Engineering Education (ASEE) established a nuclear committee to cooperate with the U. S. Atomic Energy Commission (AEC) in nuclear education matters. With the financial support of the AEC, textbook material was developed, faculty training programs were instituted, and funds were made available for equipment. Because of the large interest shown in the field, many colleges and universities began to develop nuclear engineering curricula. After a few years, the need arose for general guidelines in curricular development. This led to the development of a Committee on Objective Criteria in Nuclear Engineering Education in which ASEE and the American Nuclear Society cooperated with the support of AEC. The committee report emphasized basic science, nuclear energy concepts, and nuclear technology, which have continued to be the significant components of a nuclear engineering curriculum. The last ten years have brought increased emphasis on BS programs, the introduction of extensive computer-based instruction, and an increasing emphasis on the engineering aspects of nuclear reactor power systems

Annual report of Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, fiscal year 1995

International Nuclear Information System (INIS)

1996-08-01

This is an annual report prepared on research education action, operation state of research instruments and others in FY 1995 at Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo. The laboratory has four large instruments such as high speed neutron source reactor, 'Yayoi', electron linac, fundamentally experimental equipment for blanket design of nuclear fusion reactor, and heavy radiation research equipment (HIT), of which former two are used for cooperative research with universities in Japan, and the next blanket and the last HIT are also presented for cooperative researches in Faculty of Engineering and in University of Tokyo, respectively. FY 1995 was the beginning year of earnest discussion on future planning of this facility with concentrated effort. These four large research instruments are all in their active use. And, their further improvement is under preparation. In this report, the progress in FY 1995 on operation and management of the four large instruments are described at first, and on next, research actions, contents of theses for degree and graduation of students as well as research results of laboratory stuffs are summarized. These researches are constituted mainly using these large instruments in the facility, aiming at development of advanced and new field of atomic energy engineering and relates to nuclear reactor first wall engineering, nuclear reactor fuel cycle engineering, electromagnetic structure engineering, thermal-liquid engineering, mathematical information engineering, quantum beam engineering, new type reactor design and so on. (G.K.)

Annual report of Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, fiscal year 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-08-01

This is an annual report prepared on research education action, operation state of research instruments and others in FY 1995 at Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo. The laboratory has four large instruments such as high speed neutron source reactor, `Yayoi`, electron linac, fundamentally experimental equipment for blanket design of nuclear fusion reactor, and heavy radiation research equipment (HIT), of which former two are used for cooperative research with universities in Japan, and the next blanket and the last HIT are also presented for cooperative researches in Faculty of Engineering and in University of Tokyo, respectively. FY 1995 was the beginning year of earnest discussion on future planning of this facility with concentrated effort. These four large research instruments are all in their active use. And, their further improvement is under preparation. In this report, the progress in FY 1995 on operation and management of the four large instruments are described at first, and on next, research actions, contents of theses for degree and graduation of students as well as research results of laboratory stuffs are summarized. These researches are constituted mainly using these large instruments in the facility, aiming at development of advanced and new field of atomic energy engineering and relates to nuclear reactor first wall engineering, nuclear reactor fuel cycle engineering, electromagnetic structure engineering, thermal-liquid engineering, mathematical information engineering, quantum beam engineering, new type reactor design and so on. (G.K.)

Materials for advanced power engineering 2010. Proceedings

International Nuclear Information System (INIS)

Lecomte-Beckers, Jacqueline; Contrepois, Quentin; Beck, Tilmann; Kuhn, Bernd

2010-01-01

The 9th Liege Conference on ''Materials for Advanced Power Engineering'' presents the results of the materials related COST Actions 536 ''Alloy Development for Critical Components of Environmentally Friendly Power Plants'' and 538 ''High Temperature Plant Lifetime Extension''. In addition, the broad field of current materials research perspectives for high efficiency, low- and zero- emission power plants and new energy technologies for the next decades are reported. The Conference proceedings are structured as follows: 1. Materials for advanced steam power plants; 2. Gas turbine materials; 3. Materials for nuclear fission and fusion; 4. Solid oxide fuel cells; 5. Corrosion, thermomechanical fatigue and modelling; 6. Zero emission power plants.

Materials for advanced power engineering 2010. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Lecomte-Beckers, Jacqueline; Contrepois, Quentin; Beck, Tilmann; Kuhn, Bernd [eds.

2010-07-01

The 9th Liege Conference on ''Materials for Advanced Power Engineering'' presents the results of the materials related COST Actions 536 ''Alloy Development for Critical Components of Environmentally Friendly Power Plants'' and 538 ''High Temperature Plant Lifetime Extension''. In addition, the broad field of current materials research perspectives for high efficiency, low- and zero- emission power plants and new energy technologies for the next decades are reported. The Conference proceedings are structured as follows: 1. Materials for advanced steam power plants; 2. Gas turbine materials; 3. Materials for nuclear fission and fusion; 4. Solid oxide fuel cells; 5. Corrosion, thermomechanical fatigue and modelling; 6. Zero emission power plants.

Unique nuclear thermal rocket engine

International Nuclear Information System (INIS)

Culver, D.W.; Rochow, R.

1993-06-01

In January, 1992, a new, advanced nuclear thermal rocket engine (NTRE) concept intended for manned missions to the moon and to Mars was introduced (Culver, 1992). This NTRE promises to be both shorter and lighter in weight than conventionally designed engines, because its forward flowing reactor is located within an expansion-deflection rocket nozzle. The concept has matured during the year, and this paper discusses a nearer term version that resolves four open issues identified in the initial concept: (1) the reactor design and cooling scheme simplification while retaining a high pressure power balance option; (2) elimination need for a new, uncooled nozzle throat material suitable for long life application; (3) a practical provision for reactor power control; and (4) use of near-term, long-life turbopumps

Licensed bases management for advanced nuclear plants

Energy Technology Data Exchange (ETDEWEB)

O' Connell, J. [Duke Engineering and Services, Marlborough, MA (United States); Rumble, E.; Rodwell, E. [EPRI, Palo Alto, CA (United States)

2001-07-01

Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

Preliminary Thermo-hydraulic Core Design Analysis of Korea Advanced Nuclear Thermal Engine Rocket for Space Application

Energy Technology Data Exchange (ETDEWEB)

Nam, Seung Hyun; Lee, Jeong Ik; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2014-05-15

Nclear rockets improve the propellant efficiency more than twice compared to CRs and thus significantly reduce the propellant requirement. The superior efficiency of nuclear rockets is due to the combination of the huge energy density and a single low molecular weight propellant utilization. Nuclear Thermal Rockets (NTRs) are particularly suitable for manned missions to Mars because it satisfies a relatively high thrust as well as a high propellant efficiency. NTRs use thermal energy released from a nuclear fission reactor to heat a single low molecular weight propellant, i. e., Hydrogen (H{sub 2}) and then exhausted the extremely heated propellant through a thermodynamic nozzle to produce thrust. A propellant efficiency parameter of rocket engines is specific impulse (I{sub sp}) which represents the ratio of the thrust over the rate of propellant consumption. The difference of I{sub sp} makes over three times propellant savings of NTRs for a manned Mars mission compared to CRs. NTRs can also be configured to operate bimodally by converting the surplus nuclear energy to auxiliary electric power required for the operation of a spacecraft. Moreover, the concept and technology of NTRs are very simple, already proven, and safe. Thus, NTRs can be applied to various space missions such as solar system exploration, International Space Station (ISS) transport support, Near Earth Objects (NEOs) interception, etc. Nuclear propulsion is the most promising and viable option to achieve challenging deep space missions. Particularly, the attractions of a NTR include excellent thrust and propellant efficiency, bimodal capability, proven technology, and safe and reliable performance. The ROK has also begun the research for space nuclear systems as a volunteer of the international space race and a major world nuclear energy country. KANUTER is one of the advanced NTR engines currently under development at KAIST. This bimodal engine is operated in two modes of propulsion with 100 MW

Computational intelligence in nuclear engineering

International Nuclear Information System (INIS)

Uhrig, Robert E.; Hines, J. Wesley

2005-01-01

Approaches to several recent issues in the operation of nuclear power plants using computational intelligence are discussed. These issues include 1) noise analysis techniques, 2) on-line monitoring and sensor validation, 3) regularization of ill-posed surveillance and diagnostic measurements, 4) transient identification, 5) artificial intelligence-based core monitoring and diagnostic system, 6) continuous efficiency improvement of nuclear power plants, and 7) autonomous anticipatory control and intelligent-agents. Several Changes to the focus of Computational Intelligence in Nuclear Engineering have occurred in the past few years. With earlier activities focusing on the development of condition monitoring and diagnostic techniques for current nuclear power plants, recent activities have focused on the implementation of those methods and the development of methods for next generation plants and space reactors. These advanced techniques are expected to become increasingly important as current generation nuclear power plants have their licenses extended to 60 years and next generation reactors are being designed to operate for extended fuel cycles (up to 25 years), with less operator oversight, and especially for nuclear plants operating in severe environments such as space or ice-bound locations

Use of computer simulations for the early introduction of nuclear engineering concepts

International Nuclear Information System (INIS)

Ougouag, A.M.; Zerguini, T.H.

1985-01-01

A sophomore level nuclear engineering (NE) course is being introduced at the University of Illinois. Via computer simulations, this course presents materials covering the most important aspects of the field. It is noted that computer simulations in nuclear engineering are cheaper and safer than experiments yet they provide an effective teaching tool for the early introduction of advanced concepts. The new course material can be used as a tutorial and for remedial learning. The use of computer simulation motivates learning since students associate computer activities with games. Such a course can help in the dissemination of the proper information to students from different fields, including liberal arts, and eventually increase undergraduate student enrollment in nuclear engineering

Dictionary of nuclear engineering

International Nuclear Information System (INIS)

Sube, R.

1985-01-01

This dictionary covers nuclear engineering defined in its general sense as applied nuclear physics: industrial and other applications of nuclear power, isotopes and ionizing radiation, nuclear materials, nuclear facilities and nuclear weapons together with their scientific and technological fundamentals. During the compilation of terms, great attention was only given to generally valid basic expressions and to special terms where these occurred in all four languages. A great number of textbooks and monographs, as well as specialist journals covering many years, have been evaluated. Detailed attention has been paid to standards. Of importance in nuclear engineering are the international standards of the International Atomic Energy Organization (including the terminology employed by the International Nuclear Information System INIS), the International Organization of Standardization, the Council for Mutual Economic Assistance, the World Energy Conference, the International Electrical Engineering Commission, and also a great many national standards which, unfortunately, frequently deviate from one another as regards definition and, in particular, designation. (orig.)

Design study on advanced nuclear fuel recycling system by pyrometallurgical reprocessing technology

Energy Technology Data Exchange (ETDEWEB)

Kasai, Yoshimitsu; Kakehi, Isao; Moro, Satoshi; Tobe, Kenji; Kawamura, Fumio; Higashi, Tatsuhiro; Yonezawa, Shigeaki [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center; Yoshiuji, Takahiro

1998-12-01

The Japan Nuclear Fuel Cycle Development Institute is conducting research and development on the nuclear fuel recycling system, which will improve the economy, safety, and environmental impact of the nuclear fuel recycling system in the age of the FBR. The System Engineering Division in the O-arai Engineering Center has conducted a design study on an advanced nuclear fuel recycling system for FBRs by using pyrometallurgical reprocessing technology. The system is an economical and compact module-type system, and can be used for reprocessing oxide fuel and also new types of fuel (metal fuel and nitride fuel). This report describes the concept of this system and results of the design study. (author)

Design study on advanced nuclear fuel recycling system by pyrometallurgical reprocessing technology

International Nuclear Information System (INIS)

Kasai, Yoshimitsu; Kakehi, Isao; Moro, Satoshi; Tobe, Kenji; Kawamura, Fumio; Higashi, Tatsuhiro; Yonezawa, Shigeaki; Yoshiuji, Takahiro

1998-01-01

The Japan Nuclear Fuel Cycle Development Institute is conducting research and development on the nuclear fuel recycling system, which will improve the economy, safety, and environmental impact of the nuclear fuel recycling system in the age of the FBR. The System Engineering Division in the O-arai Engineering Center has conducted a design study on an advanced nuclear fuel recycling system for FBRs by using pyrometallurgical reprocessing technology. The system is an economical and compact module-type system, and can be used for reprocessing oxide fuel and also new types of fuel (metal fuel and nitride fuel). This report describes the concept of this system and results of the design study. (author)

KINGS Model: Achieving Sustainable Change in Nuclear Engineering Education for the Post-COP21 Era

International Nuclear Information System (INIS)

Oh, S.-K.

2016-01-01

Full text: In spite of the world nuclear community’s systematic and multilateral efforts during the COP21, most of the conference participants were reluctant to acknowledge the value of nuclear as a low-carbon energy source. In fact, the on-going aftermath of the Fukushima nuclear disaster has been overwhelming despite the evidence that there was neither any critical technical flaw nor fatal radiation casualties. This shows that advanced nuclear knowledge failed to resonate with public perception on nuclear energy. In this respect, it is now time to focus on achieving sustainable change in nuclear engineering education for the future. The KEPCO International Nuclear Graduate School (KINGS) was established to nurture leadership-level nuclear power professionals in the global standard. It affiliates with Korean nuclear industry to achieve three major goals that are also a universal prerequisite for higher education of engineering in the 21st century as follows: “a balance between education and training,” “harmony between engineering and managerial skills,” and “the application of systems engineering to nuclear power projects.” KINGS curriculum requires transdisciplinary coordination among engineering disciplines, engineering specialties, and socioeconomic methods. (author

Evaluation and development of advanced nuclear materials: IAEA activities

International Nuclear Information System (INIS)

Inozemtsev, V.; Basak, U.; Killeen, J.; Dyck, G.; Zeman, A.; )

2011-01-01

Economical, environmental and non-proliferation issues associated with sustainable development of nuclear power bring about a need for optimization of fuel cycles and implementation of advanced nuclear systems. While a number of physical and design concepts are available for innovative reactors, the absence of reliable materials able to sustain new challenging irradiation conditions represents the real bottle-neck for practical implementation of these promising ideas. Materials performance and integrity are key issues for the safety and competitiveness of future nuclear installations being developed for sustainable nuclear energy production incorporating fuel recycling and waste transmutation systems. These systems will feature high thermal operational efficiency, improved utilization of resources (both fissile and fertile materials) and reduced production of nuclear waste. They will require development, qualification and deployment of new and advanced fuel and structural materials with improved mechanical and chemical properties combined with high radiation and corrosion resistance. The extensive, diverse, and expensive efforts toward the development of these materials can be more effectively organized within international collaborative programmes with wide participation of research, design and engineering communities. IAEA carries out a number of international projects supporting interested Member States with the use of available IAEA program implementation tools (Coordinated Research Projects, Technical Meetings, Expert Reviews, etc). The presentation summarizes the activities targeting material developments for advanced nuclear systems, with particular emphasis on fast reactors, which are the focal topics of IAEA Coordinated Research Projects 'Accelerator Simulation and Theoretical Modelling of Radiation Effects' (on-going), 'Benchmarking of Structural Materials Pre-Selected for Advanced Nuclear Reactors', 'Examination of advanced fast reactor fuel and core

Progress of teaching and learning of nuclear engineering courses at College of Engineering, Universiti Tenaga Nasional (UNITEN)

Science.gov (United States)

Hamid, Nasri A.; Mohamed, Abdul Aziz; Yusoff, Mohd. Zamri

2015-04-01

Developing human capital in nuclear with required nuclear background and professional qualifications is necessary to support the implementation of nuclear power projects in the near future. Sufficient educational and training skills are required to ensure that the human resources needed by the nuclear power industry meets its high standard. The Government of Malaysia has made the decision to include nuclear as one of the electricity generation option for the country, post 2020 in order to cater for the increasing energy demands of the country as well as to reduce CO2 emission. The commitment by the government has been made clearer with the inclusion of the development of first NPP by 2021 in the Economic Transformation Program (ETP) which was launched by the government in October 2010. The In tandem with the government initiative to promote nuclear energy, Center for Nuclear Energy, College of Engineering, Universiti Tenaga Nasional (UNITEN) is taking the responsibility in developing human capital in the area of nuclear power and technology. In the beginning, the College of Engineering has offered the Introduction to Nuclear Technology course as a technical elective course for all undergraduate engineering students. Gradually, other nuclear technical elective courses are offered such as Nuclear Policy, Security and Safeguards, Introduction to Nuclear Engineering, Radiation Detection and Nuclear Instrumentation, Introduction to Reactor Physics, Radiation Safety and Waste Management, and Nuclear Thermal-hydraulics. In addition, another course Advancement in Nuclear Energy is offered as one of the postgraduate elective courses. To enhance the capability of teaching staffs in nuclear areas at UNITEN, several junior lecturers are sent to pursue their postgraduate studies in the Republic of Korea, United States and the United Kingdom, while the others are participating in short courses and workshops in nuclear that are conducted locally and abroad. This paper describes

Progress of teaching and learning of nuclear engineering courses at College of Engineering, Universiti Tenaga Nasional (UNITEN)

International Nuclear Information System (INIS)

Hamid, Nasri A.; Mohamed, Abdul Aziz; Yusoff, Mohd. Zamri

2015-01-01

Developing human capital in nuclear with required nuclear background and professional qualifications is necessary to support the implementation of nuclear power projects in the near future. Sufficient educational and training skills are required to ensure that the human resources needed by the nuclear power industry meets its high standard. The Government of Malaysia has made the decision to include nuclear as one of the electricity generation option for the country, post 2020 in order to cater for the increasing energy demands of the country as well as to reduce CO 2 emission. The commitment by the government has been made clearer with the inclusion of the development of first NPP by 2021 in the Economic Transformation Program (ETP) which was launched by the government in October 2010. The In tandem with the government initiative to promote nuclear energy, Center for Nuclear Energy, College of Engineering, Universiti Tenaga Nasional (UNITEN) is taking the responsibility in developing human capital in the area of nuclear power and technology. In the beginning, the College of Engineering has offered the Introduction to Nuclear Technology course as a technical elective course for all undergraduate engineering students. Gradually, other nuclear technical elective courses are offered such as Nuclear Policy, Security and Safeguards, Introduction to Nuclear Engineering, Radiation Detection and Nuclear Instrumentation, Introduction to Reactor Physics, Radiation Safety and Waste Management, and Nuclear Thermal-hydraulics. In addition, another course Advancement in Nuclear Energy is offered as one of the postgraduate elective courses. To enhance the capability of teaching staffs in nuclear areas at UNITEN, several junior lecturers are sent to pursue their postgraduate studies in the Republic of Korea, United States and the United Kingdom, while the others are participating in short courses and workshops in nuclear that are conducted locally and abroad. This paper describes

Progress of teaching and learning of nuclear engineering courses at College of Engineering, Universiti Tenaga Nasional (UNITEN)

Energy Technology Data Exchange (ETDEWEB)

Hamid, Nasri A., E-mail: Nasri@uniten.edu.my; Mohamed, Abdul Aziz; Yusoff, Mohd. Zamri [Nuclear Energy Center, College of Engineering, Universiti Tenaga Nasional, Jalan IKRAM-UNITEN, 43000 Kajang, Selangor (Malaysia)

2015-04-29

Developing human capital in nuclear with required nuclear background and professional qualifications is necessary to support the implementation of nuclear power projects in the near future. Sufficient educational and training skills are required to ensure that the human resources needed by the nuclear power industry meets its high standard. The Government of Malaysia has made the decision to include nuclear as one of the electricity generation option for the country, post 2020 in order to cater for the increasing energy demands of the country as well as to reduce CO{sub 2} emission. The commitment by the government has been made clearer with the inclusion of the development of first NPP by 2021 in the Economic Transformation Program (ETP) which was launched by the government in October 2010. The In tandem with the government initiative to promote nuclear energy, Center for Nuclear Energy, College of Engineering, Universiti Tenaga Nasional (UNITEN) is taking the responsibility in developing human capital in the area of nuclear power and technology. In the beginning, the College of Engineering has offered the Introduction to Nuclear Technology course as a technical elective course for all undergraduate engineering students. Gradually, other nuclear technical elective courses are offered such as Nuclear Policy, Security and Safeguards, Introduction to Nuclear Engineering, Radiation Detection and Nuclear Instrumentation, Introduction to Reactor Physics, Radiation Safety and Waste Management, and Nuclear Thermal-hydraulics. In addition, another course Advancement in Nuclear Energy is offered as one of the postgraduate elective courses. To enhance the capability of teaching staffs in nuclear areas at UNITEN, several junior lecturers are sent to pursue their postgraduate studies in the Republic of Korea, United States and the United Kingdom, while the others are participating in short courses and workshops in nuclear that are conducted locally and abroad. This paper

Human Factors Engineering Review Model for advanced nuclear power reactors

International Nuclear Information System (INIS)

O'Hara, J.; Higgins, J.; Goodman, C.; Galletti, G.: Eckenrode, R.

1993-01-01

One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model's rationale, scope, objectives, development, general characteristics. and application

Framatome advanced nuclear power-benefits for our clients from the new company

International Nuclear Information System (INIS)

Weber, P.

2001-01-01

Framatome ANP (Advanced Nuclear Power) merges the complementary strengths of two global nuclear industry leaders Framatome and Siemens - offering clients the best technological solutions for safe, reliable and economical plant performance. With a combined workforce of 13,300 skilled individuals, Framatome ANP is now the nuclear industry's leading supplier. Serving as Original Equipment Manufacturer (OEM) for more than 90 reactors that provide about 30% of the world's total installed nuclear power capacity, our experienced resources remain focused on the local needs of individual clients, wherever in the world they may be. The Company main business used to be turnkey construction of complete Nuclear Power plants, BWR and PWR capabilities, heavy equipment manufacturing, comprehensive I and C capabilities, and also expertise and knowledge of VVER. Framatome ANP will benefit in all of its fields of activity of the experience gained through Framatome and Siemens' collaboration on the next generation reactor, the EPR, as well as on steam generators replacements and or modernization of VVER. Framatome ANP nuclear fuel designs for both PWR and BWR plants provide innovative features and world-leading performance. Framatome ANP is organized according a matrix organization with: - 4 Business Groups (Project and Engineering, Service, Nuclear Fuel, Mechanical Equipment) - 3 Regional Divisions (Framatome Advanced Nuclear Power S.A.S., France; Framatome Advanced Nuclear Power GmbH, Germany; Framatome Advanced Nuclear Power Inc., USA). By 30th January 2001 Siemens Nuclear Power GmbH, founded in 2000 as successor of the Nuclear Division of Siemens Power Generation Group (KWU), was renamed to Framatome Advanced Nuclear Power GmbH forming the German part of the world wide acting company. Over the past 40 years 23 nuclear power plants all around the world - not only pressurized and boiling water reactors, but also two heavy-watermoderated reactors have been designed, constructed and

Open-Source Integrated Design-Analysis Environment For Nuclear Energy Advanced Modeling & Simulation Final Scientific/Technical Report

Energy Technology Data Exchange (ETDEWEB)

O' Leary, Patrick [Kitware, Inc., Clifton Park, NY (United States)

2017-01-30

The framework created through the Open-Source Integrated Design-Analysis Environment (IDAE) for Nuclear Energy Advanced Modeling & Simulation grant has simplify and democratize advanced modeling and simulation in the nuclear energy industry that works on a range of nuclear engineering applications. It leverages millions of investment dollars from the Department of Energy's Office of Nuclear Energy for modeling and simulation of light water reactors and the Office of Nuclear Energy's research and development. The IDEA framework enhanced Kitware’s Computational Model Builder (CMB) while leveraging existing open-source toolkits and creating a graphical end-to-end umbrella guiding end-users and developers through the nuclear energy advanced modeling and simulation lifecycle. In addition, the work deliver strategic advancements in meshing and visualization for ensembles.

Materials for advanced power engineering 2010. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Lecomte-Beckers, Jacqueline; Contrepois, Quentin; Beck, Tilmann; Kuhn, Bernd (eds.)

2010-07-01

The 9th Liege Conference on ''Materials for Advanced Power Engineering'' presents the results of the materials related COST Actions 536 ''Alloy Development for Critical Components of Environmentally Friendly Power Plants'' and 538 ''High Temperature Plant Lifetime Extension''. In addition, the broad field of current materials research perspectives for high efficiency, low- and zero- emission power plants and new energy technologies for the next decades are reported. The Conference proceedings are structured as follows: 1. Materials for advanced steam power plants; 2. Gas turbine materials; 3. Materials for nuclear fission and fusion; 4. Solid oxide fuel cells; 5. Corrosion, thermomechanical fatigue and modelling; 6. Zero emission power plants.

Waste management in the nuclear engineering curriculum

International Nuclear Information System (INIS)

Tulenko, J.S.

1989-01-01

One of the most significant challenges facing the nuclear industry is to successfully close the nuclear fuel cycle and effectively demonstrate to the public that nuclear wastes do not present a health risk. This issue is currently viewed by many as the most important issue affecting public acceptance of nuclear power, and it is imperative that nuclear engineers be able to effectively address the question of nuclear waste from both a generation and disposal standpoint. To address the issue, the area of nuclear waste management has been made one of the fields of specialized study in the Department of Nuclear Engineering Sciences at the University of Florida. The study of radioactive waste management at the University of Florida is designed both for background for the general nuclear engineering student and for those wishing to specialize in it as a multidiscipline study area involving the Departments of Nuclear Engineering Sciences, Environmental Sciences, Material Science and Engineering, Geology, Civil Engineering, and Industrial Engineering

Advanced control room design for nuclear power plants

International Nuclear Information System (INIS)

Scarola, K.

1987-01-01

The power industry has seen a continuous growth of size and complexity of nuclear power plants. Accompanying these changes have been extensive regulatory requirements resulting in significant construction, operation and maintenance costs. In response to related concerns raised by industry members, Combustion Engineering developed the NUPLEX 80 Advanced Control Room. The goal of NUPLEX 80 TM is to: reduce design and construction costs; increase plant safety and availability through improvements in the man-machine interface; and reduce maintenance costs. This paper provides an overview of the NUPLEX 80 Advanced Control Room and explains how the stated goals are achieved. (author)

4+DTM Soft Power for Nuclear Systems Engineering

International Nuclear Information System (INIS)

Suh, Kune Y.

2006-01-01

Nuclear Power Plants (NPPs) of a bulky and complex structure consisting of hundreds of thousands of parts require huge volume of data during the design, construction, operation, maintenance and decommissioning stages. The systems engineering thus calls for a fully automated way of managing the information spanning their life cycle, i. e. from cradle to grave. In line with practice in disciplines of naval architecture, aerospace engineering, and automotive manufacturing, the paper proposes total digital systems engineering based on three-dimensional (3D) computer-aided design (CAD) models. The signature in the proposal lies with the four-plus-dimensional (4 + D) TM Soft Power engineering, a critical technology for digital management. The technology proposed in the 3D space and time plus cost coordinates, i. e. 4 + D TM coordinates, constitutes, the backbone of digital engineering in the nuclear systems design. This solution will help the preliminary simulation capability for NPP to supply the vital information not only for the design and management of the engineered structures but also for the online maintenance. NPP can be built utilizing the optimized construction schedule and the structural design. The efficiency of project management will also be improved by dynamically storing voluminous information in the advanced database. The 4 + D TM digital engineering will eventually lead to paperless design and construction planing in the global marker place

Nuclear industry will be short of engineers

International Nuclear Information System (INIS)

Yates, M.

1990-01-01

This article discusses the potential shortage of nuclear engineers due to reduction of educational and training facilities and difficulty in attracting minorities into nuclear engineering. The article reports on recommendations from the National Research Council Nuclear Education Study Committee on attracting minorities to nuclear engineering, increasing DOE fellowships, funding for research and development, involvement of utilities and vendors, and support of the American Nuclear Society's advocacy of nuclear engineering education

Current status of nuclear engineering education

International Nuclear Information System (INIS)

Palladino, N.J.

1975-01-01

The 65 colleges and universities offering undergraduate degrees in nuclear engineering and the 15 schools offering strong nuclear engineering options are, in general, doing a good job to meet the current spectrum of job opportunities. But, nuclear engineering programs are not producing enough graduates to meet growing demands. They currently receive little aid and support from their customers --industry and government--in the form of scholarships, grants, faculty research support, student thesis and project support, or student summer jobs. There is not enough interaction between industry and universities. Most nuclear engineering programs are geared too closely to the technology of the present family of reactors and too little to the future breeder reactors and controlled thermonuclear reactors. In addition, nuclear engineering programs attract too few women and members of minority ethnic groups. Further study of the reasons for this fact is needed so that effective corrective action can be taken. Faculty in nuclear engineering programs should assume greater initiative to provide attractive and objective nuclear energy electives for technical and nontechnical students in other disciplines to improve their technical understanding of the safety and environmental issues involved. More aggressive and persistent efforts must be made by nuclear engineering schools to obtain industry support and involvement in their programs

European Master of Science in Nuclear Engineering

International Nuclear Information System (INIS)

Moons, Frans; Safieh, Joseph; Giot, Michel; Mavko, Borut; Sehgal, Bal Raj; Schaefer, Anselm; Goethem, Georges van; D'Haeseleer, William

2005-01-01

architecture for higher education defining bachelors and masters degrees. The basic goal is to guarantee a high quality nuclear education in Europe by means of stimulating student and instructor exchange, through mutual checks of the quality of the programs offered, by close collaboration with renowned nuclear-research groups at universities and laboratories. The concept for a nuclear master program consists of a solid basket of recommended basic nuclear science and engineering courses, but also contains advanced courses as well as practical training. Some of the advanced courses also serve as part of the curricula for doctoral programs. A second important issue identified is Continued Professional Development. The design of corresponding training courses has to respond to the needs of industry and regulatory bodies, and a specific organisation has to be set up to manage the quality assessment and accreditation of the Continued Professional Development programs. In order to achieve the important objectives and practical goals described above, the ENEN Association, a non-profit association under French law, was formed. This international association can be considered as a step towards the creation of a virtual European Nuclear University symbolising the active collaboration between various national institutions pursuing nuclear education. Based on the concepts and strategy explained above, and with the full cooperation of the participating institutions, it may be stated that the intellectual erosion in the nuclear field can be reversed, and that high quality European education in nuclear sciences and technology can be guaranteed

Advanced Control Engineering

DEFF Research Database (Denmark)

Zhou, Jianjun

1999-01-01

This book is developed as a textbook for the course Advanced Control Engineering. The book is intended for students in mechanical engineering and its aim is to provide an understanding of modern control theory as well as methodologies and applications for state space modeling and design...

European master degree in nuclear engineering

International Nuclear Information System (INIS)

Ghitescu, Petre; Prisecaru, Ilie

2003-01-01

In order to preserve and to improve the quality of nuclear engineering education and training in Europe, as well to ensure the safe and economic operation of nuclear power plants, the European Nuclear Engineering Network Program (ENEN) started in 2002. It is a program aiming to establish and maintain a set of criteria for specific curricula of nuclear engineering education, in particular, for an European Master Degree in Nuclear Engineering (EMNE). The ENEN program is financed by the FP5 and has the wide support of IAEA, OECD and EU Commission departments dealing with the nuclear engineering knowledge management. The promising results up to now determined the creation of the Asian Nuclear Engineering Network (ANEN) in July 2003 and of the World Nuclear University (WNU) starting in September 2003. The paper presents the future structure of EMNE which will allow the harmonization of the curricula of the universities of Europe until the Bologna Convention will be fully accepted and operational in all European countries. The ENEN program has taken into consideration the curricula of 22 universities and research centres from 15 different European countries and proposed a feasible scheme which allows the undergraduates with a weak to strong nuclear background to continue their graduate education in the nuclear engineering field towards EMNE. As one of the contractors of this program, University 'Politehnica' of Bucharest brings its contribution and actively takes part in all activities establishing the EMNE. (author)

Introduction to nuclear facilities engineering

International Nuclear Information System (INIS)

Sapy, Georges

2012-06-01

Engineering, or 'engineer's art', aims at transforming simple principle schemes into operational facilities often complex especially when they concern the nuclear industry. This transformation requires various knowledge and skills: in nuclear sciences and technologies (nuclear physics, neutronics, thermal-hydraulics, material properties, radiation protection..), as well as in non-nuclear sciences and technologies (civil engineering, mechanics, electricity, computer sciences, instrumentation and control..), and in the regulatory, legal, contractual and financial domains. This book explains how this huge body of knowledge and skills must be organized and coordinated to create a reliable, exploitable, available, profitable and long-lasting facility, together with respecting extremely high safety, quality, and environmental impact requirements. Each aspect of the problem is approached through the commented presentation of nuclear engineering macro-processes: legal procedures and administrative authorizations, nuclear safety/radiation protection/security approach, design and detailed studies, purchase of equipments, on-site construction, bringing into operation, financing, legal, contractual and logistic aspects, all under the global control of a project management. The 'hyper-complexness' of such an approach leads to hard points and unexpected events. The author identifies the most common ones and proposes some possible solutions to avoid, mitigate or deal with them. In a more general way, he proposes some thoughts about the performance factors of a nuclear engineering process

Convergent engineering techniques for management of nuclear processes

International Nuclear Information System (INIS)

Carabulea, A.; Popa, I.

1995-01-01

The paper briefly presents the concept of convergent arhemo-systematical engineering, its advantages in comparison with classical methods of research, design, manufacture. The convergent engineering application supposes the usage of the advanced methods, techniques and equipment corresponding to the domain and specific for the corresponding branch of computer science. Starting from the convergent engineering principles and concept, the paper proposes two models applicable for new products and also for improving and optimizing the existing ones. The models are based on two levels of feedback corresponding to two levels of control and they assume the utilization of expert and robot-expert systems. The economical efficiency of the application of the convergent engineering method is evaluated for the case of a nuclear power plant by calculation the main technical and economical indicators. (Author) 2 Figs., 5 Refs

Advanced light water reactor program at ABB-Combustion Engineering Nuclear Power

International Nuclear Information System (INIS)

Cahn, H.

1990-01-01

To meet the needs of Electric Utilities ordering nuclear power plants in the 1990s, ABB-Combustion Engineering is developing two designs which will meet EPRI consensus requirements and new licensing issues. The System 80 Plus design is an evolutionary pressurized water reactor plant modelled after the successful System 80 design in operation in Palo Verde and under construction in Korea. System Plus is currently under review by the US Nuclear Regulatory Commission with final design approval expected in 1991 and design certification in 1992. The Safe Integral Reactor (SIR) plant is a smaller facility with passive safety features and modular construction intended for design certification in the late 1990s. (author)

Nuclear Engineering Academic Programs Survey, 2004

International Nuclear Information System (INIS)

Oak Ridge Institute for Science and Education

2005-01-01

This annual report details the number of nuclear engineering bachelor's, master's, and doctoral degrees awarded at a sampling of academic programs from 1998-2004. It also looks at nuclear engineering degrees by curriculum and the number of students enrolled in nuclear engineering degree programs at 31 U.S. universities in 2004

Review on the application of system engineer model in nuclear power plant

International Nuclear Information System (INIS)

Chen Guocai

2005-01-01

system engineer was adopted deeply and play important roles in nuclear power plants in United States and Canada, the plant performance indicates that system engineer mode is a good practice. Qinshan CANDU nuclear power plant, established the system engineer mode since commissioning, as a core, system engineer took charge of the preparation of commissioning procedures, organization, coordination and guidance of commissioning execution. Unit 1 was put into commercial operation 43 days in advance and 112 days ahead of schedule for Unit 2 with excellent quality. Commissioning period are just 10.5 and 7.8 months for both Units respectively. Which is the shortest record in the history of CANDU nuclear power plant commissioning up to now. During operation, systems engineer has strength in routine operating and units reliability improvement. Based on the practice of Qinshan CANDU nuclear power plant commissioning and production technical management, the main form of the article in the era of knowledge: its characteristics and advantage and operating mode of the system engineer mode. System engineer is different from project engineer, he act as the master of systems and takes full responsibility for systems technical management. System engineer should do many jobs and improvement schedule to ensure his system in health status. System health monitor is a basic tool in system management, which is useful for equipment performance improvement. At last, the author made a forecast and comment on the prospects for the system engineer in the future. (author)

Advanced Engineering Environment FY09/10 pilot project.

Energy Technology Data Exchange (ETDEWEB)

Lamph, Jane Ann; Kiba, Grant W.; Pomplun, Alan R.; Dutra, Edward G.; Sego, Abraham L.

2010-06-01

The Advanced Engineering Environment (AEE) project identifies emerging engineering environment tools and assesses their value to Sandia National Laboratories and our partners in the Nuclear Security Enterprise (NSE) by testing them in our design environment. This project accomplished several pilot activities, including: the preliminary definition of an engineering bill of materials (BOM) based product structure in the Windchill PDMLink 9.0 application; an evaluation of Mentor Graphics Data Management System (DMS) application for electrical computer-aided design (ECAD) library administration; and implementation and documentation of a Windchill 9.1 application upgrade. The project also supported the migration of legacy data from existing corporate product lifecycle management systems into new classified and unclassified Windchill PDMLink 9.0 systems. The project included two infrastructure modernization efforts: the replacement of two aging AEE development servers for reliable platforms for ongoing AEE project work; and the replacement of four critical application and license servers that support design and engineering work at the Sandia National Laboratories/California site.

Nuclear Explosion Monitoring Research and Engineering Program - Strategic Plan

Energy Technology Data Exchange (ETDEWEB)

Casey, Leslie A. [DOE/NNSA

2004-09-01

The Department of Energy (DOE)/National Nuclear Security Administration (NNSA) Nuclear Explosion Monitoring Research and Engineering (NEM R&E) Program is dedicated to providing knowledge, technical expertise, and products to US agencies responsible for monitoring nuclear explosions in all environments and is successful in turning scientific breakthroughs into tools for use by operational monitoring agencies. To effectively address the rapidly evolving state of affairs, the NNSA NEM R&E program is structured around three program elements described within this strategic plan: Integration of New Monitoring Assets, Advanced Event Characterization, and Next-Generation Monitoring Systems. How the Program fits into the National effort and historical accomplishments are also addressed.

Nuclear Power Engineering Education Program, University of Illinois

International Nuclear Information System (INIS)

Jones, B.G.

1993-01-01

The DOE/CECo Nuclear Power Engineering Education Program at the University of Illinois in its first year has significantly impacted the quality of the power education which our students receive. It has contributed to: the recently completed upgrade of the console of our Advanced TRIGA reactor which increases the reactor's utility for training, the procurement of new equipment to upgrade and refurbish several of the undergraduate laboratory set-ups, and the procurement of computational workstations in support of the instructional computing laboratory. In addition, smaller amounts of funds were used for the recruitment and retention of top quality graduate students, the support of faculty to visit other institutions to attract top students into the discipline, and to provide funds for faculty to participate in short courses to improve their skills and background in the power area. These items and activities have helped elevate in the student's perspective the role of nuclear power in the discipline. We feel this is having a favorable impact on student career selection and on ensuring the continued supply of well educated nuclear engineering graduates

Engineering and science education for nuclear power

International Nuclear Information System (INIS)

1986-01-01

The Guidebook contains detailed information on curricula which would provide the professional technical education qualifications which have been established for nuclear power programme personnel. The core of the Guidebook consists of model curricula in engineering and science, including relevant practical work. Curricula are provided for specialization, undergraduate, and postgraduate programmes in nuclear-oriented mechanical, chemical, electrical, and electronics engineering, as well as nuclear engineering and radiation health physics. Basic nuclear science and engineering laboratory work is presented together with a list of basic experiments and the nuclear equipment needed to perform them. Useful measures for implementing and improving engineering and science education and training capabilities for nuclear power personnel are presented. Valuable information on the national experiences of IAEA Member States in engineering and science education for nuclear power, as well as examples of such education from various Member States, have been included

Space nuclear power plant technology development philosophy for a ground engineering phase

International Nuclear Information System (INIS)

Buden, D.; Trapp, T.J.; Los Alamos National Lab., NM)

1985-01-01

The development of a space qualified nuclear power plant is proceeding from the technical assessment and advancement phase to the ground engineering phase. In this new phase, the selected concept will be matured by the completion of activities needed before protoflight units can be assembled and qualified for first flight applications. This paper addresses a possible philosophy to arrive at the activities to be performed during the ground engineering phase. The philosophy is derived from what we believe a potential user of nuclear power would like to see completed before commitment to a flight development phase. 5 references

Space nuclear power plant technology development philosophy for a ground engineering phase

International Nuclear Information System (INIS)

Buden, D.; Trapp, T.J.

1985-01-01

The development of a space qualified nuclear power plant is proceeding from the Technical Assessment and Advancement Phase to the Ground Engineering Phase. In this new phase, the selected concept will be matured by the completion of activities needed before protoflight units can be assembled and qualified for first flight applications. This paper addresses a possible philosophy to arrive at the activities to be performed during the Ground Engineering Phase. The philosophy is derived from what we believe a potential user of nuclear power would like to see completed before commitment to a flight development phase

Final Technical Report; NUCLEAR ENGINEERING RECRUITMENT EFFORT

Energy Technology Data Exchange (ETDEWEB)

Kerrick, Sharon S.; Vincent, Charles D.

2007-07-02

This report provides the summary of a project whose purpose was to support the costs of developing a nuclear engineering awareness program, an instruction program for teachers to integrate lessons on nuclear science and technology into their existing curricula, and web sites for the exchange of nuclear engineering career information and classroom materials. The specific objectives of the program were as follows: OBJECTIVE 1: INCREASE AWARENESS AND INTEREST OF NUCLEAR ENGINEERING; OBJECTIVE 2: INSTRUCT TEACHERS ON NUCLEAR TOPICS; OBJECTIVE 3: NUCLEAR EDUCATION PROGRAMS WEB-SITE; OBJECTIVE 4: SUPPORT TO UNIVERSITY/INDUSTRY MATCHING GRANTS AND REACTOR SHARING; OBJECTIVE 5: PILOT PROJECT; OBJECTIVE 6: NUCLEAR ENGINEERING ENROLLMENT SURVEY AT UNIVERSITIES

Educating nuclear engineers by nuclear science and technology master at UPM

Energy Technology Data Exchange (ETDEWEB)

Ahnert, C.; Minguez, E.; Perlado, M. [Universidad Politecnica de Madrid (Spain). Dept. de Ingenieria Nuclear; and others

2014-05-15

One of the main objectives of the Master on Nuclear Science and Technology implemented in the Universidad Politecnica de Madrid, is the training for the development of methodologies of simulation and advanced analysis necessary in research and in professional work in the nuclear field, for Fission Reactors and Nuclear Fusion, including fuel cycle and safety aspects. The students are able to use the current computational methodologies/codes for nuclear engineering that covers a difficult gap between nuclear reactor theory and simulations. Also they are able to use some facilities, as the Interactive Graphical Simulator of PWR power plant that is an optimal tool to transfer the knowledge of the physical phenomena that are involved in the nuclear power plants, from the nuclear reactor to the whole set of systems and equipment on a nuclear power plant. The new Internet reactor laboratory to be implemented will help to understand the Reactor Physics concepts. The experimental set-ups for neutron research and for coating fabrication offer new opportunities for training and research activities. All of them are relevant tools for motivation of the students, and to complete the theoretical lessons. They also follow the tendency recommended for the European Space for higher Education (Bologna) adapted studies. (orig.)

Educating nuclear engineers by nuclear science and technology master at UPM

International Nuclear Information System (INIS)

Ahnert, C.; Minguez, E.; Perlado, M.

2014-01-01

One of the main objectives of the Master on Nuclear Science and Technology implemented in the Universidad Politecnica de Madrid, is the training for the development of methodologies of simulation and advanced analysis necessary in research and in professional work in the nuclear field, for Fission Reactors and Nuclear Fusion, including fuel cycle and safety aspects. The students are able to use the current computational methodologies/codes for nuclear engineering that covers a difficult gap between nuclear reactor theory and simulations. Also they are able to use some facilities, as the Interactive Graphical Simulator of PWR power plant that is an optimal tool to transfer the knowledge of the physical phenomena that are involved in the nuclear power plants, from the nuclear reactor to the whole set of systems and equipment on a nuclear power plant. The new Internet reactor laboratory to be implemented will help to understand the Reactor Physics concepts. The experimental set-ups for neutron research and for coating fabrication offer new opportunities for training and research activities. All of them are relevant tools for motivation of the students, and to complete the theoretical lessons. They also follow the tendency recommended for the European Space for higher Education (Bologna) adapted studies. (orig.)

Final report to DOE: Matching Grant Program for the Penn State University Nuclear Engineering Program

International Nuclear Information System (INIS)

Jack S. Brenizer, Jr.

2003-01-01

The DOE/Industry Matching Grant Program is designed to encourage collaborative support for nuclear engineering education as well as research between the nation's nuclear industry and the U.S. Department of Energy (DOE). Despite a serious decline in student enrollments in the 1980s and 1990s, the discipline of nuclear engineering remained important to the advancement of the mission goals of DOE. The program is designed to ensure that academic programs in nuclear engineering are maintained and enhanced in universities throughout the U.S. At Penn State, the Matching Grant Program played a critical role in the survival of the Nuclear Engineering degree programs. Funds were used in a variety of ways to support both undergraduate and graduate students directly. Some of these included providing seed funding for new graduate research initiatives, funding the development of new course materials, supporting new teaching facilities, maintenance and purchase of teaching laboratory equipment, and providing undergraduate scholarships, graduate fellowships, and wage payroll positions for students

Advanced Control of Turbofan Engines

CERN Document Server

Richter, Hanz

2012-01-01

Advanced Control of Turbofan Engines describes the operational performance requirements of turbofan (commercial)engines from a controls systems perspective, covering industry-standard methods and research-edge advances. This book allows the reader to design controllers and produce realistic simulations using public-domain software like CMAPSS: Commercial Modular Aero-Propulsion System Simulation, whose versions are released to the public by NASA. The scope of the book is centered on the design of thrust controllers for both steady flight and transient maneuvers. Classical control theory is not dwelled on, but instead an introduction to general undergraduate control techniques is provided. This book also: Develops a thorough understanding of the challenges associated with engine operability from a control systems perspective, describing performance demands and operational constraints into the framework and language of modern control theory Presents solid theoretical support for classical and advanced engine co...

Advanced Technology for Engineering Education

Science.gov (United States)

Noor, Ahmed K. (Compiler); Malone, John B. (Compiler)

1998-01-01

This document contains the proceedings of the Workshop on Advanced Technology for Engineering Education, held at the Peninsula Graduate Engineering Center, Hampton, Virginia, February 24-25, 1998. The workshop was jointly sponsored by the University of Virginia's Center for Advanced Computational Technology and NASA. Workshop attendees came from NASA, other government agencies, industry and universities. The objectives of the workshop were to assess the status of advanced technologies for engineering education and to explore the possibility of forming a consortium of interested individuals/universities for curriculum reform and development using advanced technologies. The presentations covered novel delivery systems and several implementations of new technologies for engineering education. Certain materials and products are identified in this publication in order to specify adequately the materials and products that were investigated in the research effort. In no case does such identification imply recommendation or endorsement of products by NASA, nor does it imply that the materials and products are the only ones or the best ones available for this purpose. In many cases equivalent materials and products are available and would probably produce equivalent results.

Nuclear engineering in the National Polytechnic Institute

International Nuclear Information System (INIS)

Del Valle G, E.

2008-12-01

In the National Polytechnic Institute the bachelor degree in physics and mathematics, consists of 48 subjects in the common trunk. For the nuclear engineering option, from the fifth semester undergoing 9 specific areas within the Nuclear Engineering Department : introduction to nuclear engineering, power cycles thermodynamics, heat transfer, two courses of nuclear reactors theory, two of nuclear engineering, one course of laboratory and other of radiation protection. There is also a master in nuclear engineering aims train human resources in the area of power and research nuclear reactors to meet the needs of the nuclear industry in Mexico, as well as train highly qualified personnel in branches where are used equipment involving radiation and radioisotopes tale as Medicine, Agriculture and Industry. Among its compulsory subjects are: radiation interaction with the matter, measurements laboratory, reactor physics I and II, reactor engineering, reactor laboratory and thesis seminar. Optional, are: engineering of the radiation protection, computers in the nuclear engineering, nuclear systems dynamics, power plants safety, flow in two phases, reliability and risk analysis, nuclear power systems design, neutron transport theory. Many graduates of this degree have been and are involved in various phases of the nuclear project of Laguna Verde. The Nuclear Engineering Department has a subcritical nuclear reactor of light water and natural uranium and one isotopic source of Pu-Be neutrons of 5 Ci. It also has a multichannel analyzers, calibrated sources of alpha, beta and gamma radiation, a gamma spectrometer of high resolution and low background, a specialized library and one data processing center. In relation particularly to radiation protection, it is clear that there is a lack of specialists, as reflected in radiological control problems in areas such as medicine and industry. Given this situation, it is perceived to be required post-graduate studies at Master and Ph

Nuclear engineering in the linelight

International Nuclear Information System (INIS)

Blumentritt, G.; Schwaar, L.

1979-01-01

An insight is given into the state of art of nuclear engineering considering only essential problems. The subject is covered under the following headings: (1) the way to nuclear fission, (2) detectors for nuclear radiation, (3) measuring systems for nuclear radiation, (4) radioisotopes in industry, (5) aids in medicine, (6) radiation absorption and its utilization, (7) use of radioisotopes in research, (8) the chain reaction in a nuclear reactor, (9) power from nuclear power plants, (10) pressurized water reactors (PWR), (11) high-temperature reactors (HTGR), (12) fast breeder reactors (FBR), (13) nuclear energetics - a new branch of industry, (14) nuclear explosions, (15) nuclear research at Rossendorf, and (16) the energy of the future. An appendix includes definitions of terms used in nuclear engineering. The book is written for a wide circle of readers who are interested in the peaceful uses of nuclear energy

Nuclear industry - challenges in chemical engineering

International Nuclear Information System (INIS)

Sen, S.; Sunder Rajan, N.S.; Balu, K.; Garg, R.K.; Murthy, L.G.K.; Ramani, M.P.S.; Rao, M.K.; Sadhukhan, H.K.; Venkat Raj, V.

1978-01-01

As chemical engineering processes and operations are closely involved in many areas of nuclear industry, the chemical engineer has a vital role to play in its growth and development. An account of the major achievements of the Indian chemical engineers in this field is given with view of impressing upon the faculty members of the Indian universities the need for taking appropriate steps to prepare chemical engineers suitable for nuclear industry. Some of the major achievements of the Indian chemical engineers in this field are : (1) separation of useful minerals from beach sand, (2) preparation of thorium nitrate of nuclear purity from monazite, (3) processing of zircon sand to obtain nuclear grade zirconium and its separation from hafnium to obtain zirconium metal sponge, (4) recovery of uranium from copper tailings, (5) economic recovery of nuclear grade uranium from low grade uranium ores found in India, (6) fuel reprocessing, (7) chemical processing of both low and high level radioactive wastes. (M.G.B.)

Feasibility study of a contained pulsed nuclear propulsion engine

International Nuclear Information System (INIS)

Parlos, A.G.; Metzger, J.D.

1994-01-01

The result of a feasibility analysis of a contained pulsed nuclear propulsion (CPNP) engine concept utilizing the enormously dense energy generated by small nuclear detonations is presented in this article. This concept was initially proposed and studied in the 1950s and 1960s under the program name HELIOS. The current feasibility of the concept is based upon materials technology that has advanced to a state that allows the design of pressure vessels required to contain the blast associated with small nuclear detonations. The impulsive nature of the energy source provides the means for circumventing the materials thermal barriers that are inherent in steady-state nuclear propulsion concepts. The rapid energy transfer to the propellant results in high thrust levels for times less than 1 s following the detonation. The preliminary feasibility analysis using off-the-shelf materials technology appears to indicate that the CPNP concept can have thrust-to-weight ratios on the order of 1 or greater. Though the specific impulse is not a good indicator for impulsive engines, an operating-cycle averaged specific impulse of approximately 1000 or greater seconds was calculated. 16 refs

Do nuclear engineering educators have a special responsibility

International Nuclear Information System (INIS)

Weinberg, A.M.

1977-01-01

Each 1000 MW(e) reactor in equilibrium contains 15 x 10 9 Ci of radioactivity. To handle this material safety requires an extremely high level of expertise and commitment - in many respects, an expertise that goes beyond what is demanded of any other technology. If one grants that nuclear engineering is more demanding than other engineering because the price of failure is greater, one must ask how can we inculcate into the coming generations of nuclear engineers a full sense of the responsibility they bear in practising their profession. Clearly a first requirement is that all elements of the nuclear community -utility executives, equipment engineers, operating engineers, nuclear engineers, administrators - must recognize and accept the idea that nuclear energy is something special, and that therefore its practitioners must be special. This sense must be instilled into young nuclear engineers during their education. A special responsibility therefore devolves upon nuclear engineering educators: first, to recognize the special character of their profession, and second, to convey this sense to their students. The possibility of institutionalizing this sense of responsibility by establishing a nuclear Hippocratic Oath or special canon of ethics for nuclear engineers ought to be discussed within the nuclear community. (author)

Building an integrated nuclear engineering and nuclear science human resources pipeline at the Idaho National Engineering and Environmental Laboratory

International Nuclear Information System (INIS)

Sneed, A.; Sikorski, B.; Lineberry, M.; Jolly, J.

2004-01-01

Full text: In 2002, the US Department of Energy (US DOE) transferred sponsorship of the INEEL and ANL-W to the DOE Office of Nuclear Energy, Science and Technology and designated the INEEL and ANL-W as the nation's lead laboratories for nuclear reactor and nuclear fuel cycle research and development. This transfer acknowledged the laboratories' history, infrastructure, expertise and commitment to collaborate broadly in order to fulfill its assigned role as the nation's center for nuclear energy research and development. Key to this role is the availability of well-educated and trained nuclear engineers, professionals from other disciplines of engineering, nuclear scientists, and others with advanced degrees in supporting disciplines such as physics, chemistry, and math. In 2005 the INEEL and ANL-W will be combined into the Idaho National Laboratory (INL). One of US DOE's objectives for the INL will be for it to take a strong role in the revitalization of nuclear engineering and nuclear science education in the US. Responding to this objective for the INL and the national need to rejuvenate nuclear engineering and nuclear science research and education, ISU, University of Idaho (UI), Boise State University, the INEEL, and ANL-W are all supporting a new Institute of Nuclear Science and Engineering (INSE), initially proposed by and to be administered by ISU. The Institute will rely on the resources of both universities and the INL to create a US center for reactor and fuel cycle research to development and attract outstanding faculty and students to Idaho and to the INL. The Institute and other university based education development efforts represent only one component of a viable Human Resources Pipeline from university to leading edge laboratory researcher. Another critical component is the successful integration of new graduates into the laboratory research environment, the transfer of knowledge from senior researchers, and the development of these individuals into

Nuclear engineering vocabulary

International Nuclear Information System (INIS)

2006-01-01

The terms, expressions and definitions presented in this booklet come from the works carried out by the French specialized commission of nuclear engineering terminology and neology. This selection of terms cannot be found, in general, in classical dictionaries, or can be found but with a different meaning than the one used in nuclear engineering. All terms and expressions contained in this booklet have been already published in different issues of the Official Journal of the French Republic. This publication makes their use mandatory in replacement of foreign language equivalents inside all government services and public buildings. (J.S.)

Indian advanced nuclear reactors

International Nuclear Information System (INIS)

Saha, D.; Sinha, R.K.

2005-01-01

For sustainable development of nuclear energy, a number of important issues like safety, waste management, economics etc. are to be addressed. To do this, a number of advanced reactor designs as well as fuel cycle technologies are being pursued worldwide. The advanced reactors being developed in India are the AHWR and the CHTR. Both the reactors use thorium based fuel and have many passive features. This paper describes the Indian advanced reactors and gives a brief account of the international initiatives for the sustainable development of nuclear energy. (author)

Design of a requirements system for decommissioning of a nuclear power plant based on systems engineering

Energy Technology Data Exchange (ETDEWEB)

Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Choi, Jong won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

The nuclear industry has required an advanced system that can manage decommissioning information ever since the Korean government decide to decommission the Gori No.1 nuclear power plant. The D and D division at KAERI has been developing a system that can secure the reliability and sustainability of the decommissioning project based on the engineering system of the KRR-2 (Korean Research Reactor-2). To establish a decommissioning information system, a WBS that needs to be managed for the decommissioning of an NPP has been extracted, and requirements management research composed of system engineering technology has progressed. This paper propose a new type of system based on systems engineering technology. Even though a decommissioning engineering system was developed through the KRR-2, we are now developing an advanced decommissioning information system because it is not easy to apply this system to a commercial nuclear power plant. An NPP decommissioning is a project requiring a high degree of safety and economic feasibility. Therefore, we have to use a systematic project management at the initial phase of the decommissioning. An advanced system can manage the decommissioning information from preparation to remediation by applying a previous system to the systems engineering technology that has been widely used in large-scale government projects. The first phase of the system has progressed the requirements needed for a decommissioning project for a full life cycle. The defined requirements will be used in various types of documents during the decommissioning preparation phase.

US Nuclear Engineering Education: Status and prospects

International Nuclear Information System (INIS)

1990-01-01

This study, conducted under the auspices of the Energy Engineering Board of the National Research Council, examines the status of and outlook for nuclear engineering education in the United States. The study, as described in this report resulted from a widely felt concern about the downward trends in student enrollments in nuclear engineering, in both graduate and undergraduate programs. Concerns have also been expressed about the declining number of US university nuclear engineering departments and programs, the ageing of their faculties, the appropriateness of their curricula and research funding for industry and government needs, the availability of scholarships and research funding, and the increasing ratio of foreign to US graduate students. A fundamental issue is whether the supply of nuclear engineering graduates will be adequate for the future. Although such issues are more general, pertaining to all areas of US science and engineering education, they are especially acute for nuclear engineering education. 30 refs., 24 figs., 49 tabs

US nuclear engineering education: Status and prospects

Energy Technology Data Exchange (ETDEWEB)

1990-01-01

This study, conducted under the auspices of the Energy Engineering Board of the National Research Council, examines the status of and outlook for nuclear engineering education in the United States. The study resulted from a widely felt concern about the downward trends in student enrollments in nuclear engineering, in both graduate and undergraduate programs. Concerns have also been expressed about the declining number of US university nuclear engineering departments and programs, the aging of their faculties, the appropriateness of their curricula and research funding for industry and government needs, the availability of scholarships and research funding, and the increasing ratio of foreign to US graduate students. A fundamental issue is whether the supply of nuclear engineering graduates will be adequate for the future. Although such issues are more general, pertaining to all areas of US science and engineering education, they are especially acute for nuclear engineering education. 30 refs., 12 figs., 20 tabs.

Facts in nuclear engineering

International Nuclear Information System (INIS)

Buenemann, D.

1979-07-01

This compilation of facts has been published on behalf of Kerntechnische Gesellschaft (Society for Nuclear Engineering), as a basis for the discussion between promoters and opponents of nuclear power. It intends to make the nuclear discussion less emotional by providing relevant data material. (orig./HP) [de

Research-based learning for nuclear engineering education in Gadjah Mada University

International Nuclear Information System (INIS)

Putero, Susetyo Hario; Kusnanto; Harto, Andang Widi

2011-01-01

Nuclear engineering education in Gadjah Mada University has been operated since 1977 in order to prepare Indonesian people facing up nuclear era in Indonesia. Until 1995, most of the alumni work in National Nuclear Energy Board, but recently many of them have been taking advanced study abroad. To improve our quality of education, since the last 3 years Gadjah Mada University has implemented Research-Based Learning (RBL). RBL for nuclear engineering student is conducted by providing challenges to the student related to the critical issues in public acceptance of nuclear power plant (NPP) in Indonesia that is waste management. Students should join in a group to complete the assignment. Within the group, they discuss and produce new idea in order to manage radioactive waste of new generation NPP. So, they are stimulated to think the future based on the state of the art of waste technology. This method could increase student's knowledge and soft skills, simultaneously. Some students also continue to explore and to refine the task as their thesis topic. Therefore, implementation of RBL also succeeds in increasing student's efficiency study. (author)

Nuclear Engineering Education in Support of Thailand’s Nuclear Power Programme

International Nuclear Information System (INIS)

Chanyotha, S.; Pengvanich, P.; Nilsuwankosit, S.

2015-01-01

This paper aims to introduce the nuclear engineering education at the Department of Nuclear Engineering, Chulalongkon University, Bangkok Thailand. The department has been offering curriculum in nuclear engineering to support the national nuclear power programme since 1970s. It is the oldest established nuclear engineering educational programme in the South East Asia region. Nevertheless, since the nuclear power programme has been postponed several times due to various reasons, the educational programme at the department has been continuously adapted to meet the nation’s needs. Several areas of study have been introduced, including nuclear power engineering, industrial applications of radioisotope, nuclear instrumentation, radioisotope production, radiation processing, environment and safety, nuclear materials, as well as the newly created nuclear security and non-proliferation. With the renewed interest in using nuclear power in Thailand in 2007, the department has been actively assisting both the government and the electric utility in preparing human resources to support the nuclear power programme through various educational and training modules. Realizing the importance of establishing and balancing all 3 aspects of the nuclear 3S (safety, security and safeguard) in Thailand and in the Southeast Asian region. The new curriculum of nuclear security and safeguard programme has been offered since 2013. Since the establishment, the department has produced hundreds of graduates (Diploma, Master’s, and Ph.D. levels) to feed the continuously expanding Thai nuclear industry. The full paper will provide detailed information of the curriculum, the challenges and obstacles that the department has encountered, as well as the national and international linkages which have been established over the years. (author)

Integrated engineering system for nuclear facilities building

International Nuclear Information System (INIS)

Tomura, H.; Miyamoto, A.; Futami, F.; Yasuda, S.; Ohtomo, T.

1995-01-01

In the construction of buildings for nuclear facilities in Japan, construction companies are generally in charge of the building engineering work, coordinating with plant engineering. An integrated system for buildings (PROMOTE: PROductive MOdeling system for Total nuclear Engineering) described here is a building engineering system including the entire life cycle of buildings for nuclear facilities. A Three-dimensional (3D) building model (PRO-model) is to be in the core of the system (PROMOTE). Data sharing in the PROMOTE is also done with plant engineering systems. By providing these basic technical foundations, PROMOTE is oriented toward offering rational, highquality engineering for the projects. The aim of the system is to provide a technical foundation in building engineering. This paper discusses the characteristics of buildings for nuclear facilities and the outline of the PROMOTE. (author)

Nuclear rocket engine reactor

Energy Technology Data Exchange (ETDEWEB)

Lanin, Anatoly

2013-07-01

Covers a new technology of nuclear reactors and the related materials aspects. Integrates physics, materials science and engineering Serves as a basic book for nuclear engineers and nuclear physicists. The development of a nuclear rocket engine reactor (NRER) is presented in this book. The working capacity of an active zone NRER under mechanical and thermal load, intensive neutron fluxes, high energy generation (up to 30 MBT/l) in a working medium (hydrogen) at temperatures up to 3100 K is displayed. Design principles and bearing capacity of reactors area discussed on the basis of simulation experiments and test data of a prototype reactor. Property data of dense constructional, porous thermal insulating and fuel materials like carbide and uranium carbide compounds in the temperatures interval 300 - 3000 K are presented. Technological aspects of strength and thermal strength resistance of materials are considered. The design procedure of possible emergency processes in the NRER is developed and risks for their origination are evaluated. Prospects of the NRER development for pilotless space devices and piloted interplanetary ships are viewed.

Towards the European Nuclear Engineering Education Network

International Nuclear Information System (INIS)

Mavko, B.; Giot, M.; Sehgal, B.R.; Goethem, G. Van

2003-01-01

Current priorities of the scientific community regarding basic research lie elsewhere than in nuclear sciences. The situation today is significantly different than it was three to four decades ago when much of the present competence base in nuclear sciences was in fact generated. In addition, many of the highly competent engineers and scientists, who helped create the present nuclear industry, and its regulatory structure, are approaching retirement. To preserve nuclear knowledge and expertise through the higher nuclear engineering education in the 5 th framework program of the European Commission the project ENEN (European Nuclear Engineering Education Network) was launched, since the need to keep the university curricula in nuclear sciences and technology alive has been clearly recognized at European level. As the follow up of this project an international nuclear engineering education consortium of universities with partners from the nuclear sector is presently in process of being established This association called ENEN has as founding members: 14 universities and 8 research institutes from 17 European countries. (author)

Nuclear propulsion systems engineering

International Nuclear Information System (INIS)

Madsen, W.W.; Neuman, J.E.: Van Haaften, D.H.

1992-01-01

The Nuclear Energy for Rocket Vehicle Application (NERVA) program of the 1960's and early 1970's was dramatically successful, with no major failures during the entire testing program. This success was due in large part to the successful development of a systems engineering process. Systems engineering, properly implemented, involves all aspects of the system design and operation, and leads to optimization of theentire system: cost, schedule, performance, safety, reliability, function, requirements, etc. The process must be incorporated from the very first and continued to project completion. This paper will discuss major aspects of the NERVA systems engineering effort, and consider the implications for current nuclear propulsion efforts

Research and development on the application of advanced control technologies to advanced nuclear reactor systems: A US national perspective

International Nuclear Information System (INIS)

White, J.D.; Monson, L.R.; Carrol, D.G.; Dayal, Y.

1989-01-01

Control system designs for nuclear power plants are becoming more advanced through the use of digital technology and automation. This evolution is taking place because of: (1) the limitations in analog based control system performance and maintenance and availability and (2) the promise of significant improvement in plant operation and availability due to advances in digital and other control technologies. Digital retrofits of control systems in US nuclear plants are occurring now. Designs of control and protection systems for advanced LWRs are based on digital technology. The use of small inexpensive, fast, large-capacity computers in these designs is the first step of an evolutionary process described in this paper. Under the sponsorship of the US Department of Energy (DOE), Oak Ridge National Laboratory, Argonne National Laboratory, GE Nuclear Energy and several universities are performing research and development in the application of advances in control theory, software engineering, advanced computer architectures, artificial intelligence, and man-machine interface analysis to control system design. The target plant concept for the work described in this paper is the Power Reactor Inherently Safe Module reactor (PRISM), an advanced modular liquid metal reactor concept. This and other reactor designs which provide strong passive responses to operational upsets or accidents afford good opportunities to apply these advances in control technology. 18 refs., 5 figs

Advances in Computer Science and Engineering

CERN Document Server

Second International Conference on Advances in Computer Science and Engineering (CES 2012)

2012-01-01

This book includes the proceedings of the second International Conference on Advances in Computer Science and Engineering (CES 2012), which was held during January 13-14, 2012 in Sanya, China. The papers in these proceedings of CES 2012 focus on the researchers’ advanced works in their fields of Computer Science and Engineering mainly organized in four topics, (1) Software Engineering, (2) Intelligent Computing, (3) Computer Networks, and (4) Artificial Intelligence Software.

Thermal hydraulics in undergraduate nuclear engineering education

International Nuclear Information System (INIS)

Theofanous, T.G.

1986-01-01

The intense safety-related research efforts of the seventies in reactor thermal hydraulics have brought about the recognition of the subject as one of the cornerstones of nuclear engineering. Many nuclear engineering departments responded by building up research programs in this area, and mostly as a consequence, educational programs, too. Whether thermal hydraulics has fully permeated the conscience of nuclear engineering, however, remains yet to be seen. The lean years that lie immediately ahead will provide the test. The purpose of this presentation is to discuss the author's own educational activity in undergraduate nuclear engineering education over the past 10 yr or so. All this activity took place at Purdue's School of Nuclear Engineering. He was well satisfied with the results and expects to implement something similar at the University of California in Santa Barbara in the near future

Nuclear operations summary Engineering organization for Plowshare nuclear operations

Energy Technology Data Exchange (ETDEWEB)

Broadman, Gene A [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

1970-05-15

The availability of nuclear explosives for peaceful projects has given the engineer a new dimension in his thinking. He can now seek methods of adapting Plowshare to a variety of industrial applications. The full potential of the Plowshare Program can only be attained when industry begins to use nuclear explosives on a regular basis, for economically sound projects. It is the purpose of this paper to help the engineer familiarize himself with Plowshare technology to hasten the day when 'Plowsharee goes commercial'. An engineering project utilizing nuclear exposives ordinarily involves three main phases: Phase I (a) The theoretical and empirical analysis of effects. (b) Projected economic and/or scientific evaluation. (c) A safety analysis. Phase II (a) Field construction. (b) Safe detonation of the nuclear explosive. (c) Data acquisition. Phase III The evaluation and/or exploitation of the results. This paper will be restricted to Phase II, referred to collectively as the 'nuclear operation'.

The future of nuclear energy. Safety and nuclear power plants. Contribution of engineering companies

International Nuclear Information System (INIS)

Garcia Rodriguez, A.

1995-01-01

Risk, its consideration and its acceptance or rejection, are parameters which to a large extent are independent and sometimes difficult to interrelate. Nuclear energy, unlike motoring or civil aviation, has not gained sufficient public acceptance, this despite the fact that the risk to population is by far the least of the three. It is therefore necessary to continue with its improvement is an attempt to create the same confidence in the nuclear industry, as society has placed in civil aviation. Improvement in future nuclear power plants must be a combination of improved safety and a reduction in capital investment. This objective can only be reached through standardization and international cooperation. Engineering has a very important part to play in the standardization process. An increase in engineering input during the design, construction, operation and maintenance phases of future nuclear power plants, and the application of increasingly sophisticated analysis and management tools are anticipated. Nevertheless, the financial impact on the cost of each plant will fall as a result of increased input spread throughout the range of standard plants. Our current Advanced Reactor Power Plant Programme enables the Spanish industry to participate actively in the creation of future standards nuclear power plants. Having a presence in selected engineering activities, which guarantees access to the state of the art in this area, is one of our priorities, since it will facilitate the presence of the rest of the industry in future projects. If the objectives described above are to be reached, the present involvement of the spanish industry in this programme must be maintained in the medium and long term. (Author)

Infiltration of quality concepts in nuclear engineering education

International Nuclear Information System (INIS)

Woodall, D.M.

1993-01-01

The principles of total quality management (TQM) have been applied increasingly in the nuclear power industry over the last decade. The involvement of industrial professionals on the advisory boards of engineering colleges and departments has increasingly led in recent years to the recommendation that TQM be applied as appropriate to engineering education. This paper describes the concepts of TQM in their application to engineering education, specifically in the nuclear engineering area. A summary of the concerns expressed by nuclear engineering academics, as well as the record of successful implementation of TQM in the nuclear engineering education environment is provided in this paper

Reconstruction of nuclear engineering education in universities

International Nuclear Information System (INIS)

Kitamura, Masaharu; Tomota, Yo; Tanaka, Shunichi

2005-01-01

Nuclear engineering has become the area gradually loosing appeal to the young for these twenty years taking all the circumstances into consideration. However nuclear power is predicted to be primary energy of greatest importance even in the future and this needs highly motivated and excellent personnel in nuclear industry and society so as to develop and maintain nuclear power to a high degree. Under these circumstances discussions on how should be nuclear engineering research and education in the new era were presented from various viewpoints and they led to the direction of reconstruction of nuclear engineering education in universities and relevant organizations to train and ensure personnel. (T. Tanaka)

Broadening of nuclear engineering programs: An engineering physics approach at Rensselaer

International Nuclear Information System (INIS)

Malaviya, B.K.

1990-01-01

With the maturing of nuclear engineering as an academic discipline and the uncertainty surrounding the nuclear industry, attention is being increasingly turned to ways in which the base of traditional nuclear engineering programs in universities can be broadened to make them more attractively useful to a wider class of potential students and employers while maintaining the strengths in mainstream areas of nuclear technology. An approach that seems to provide a natural evolution combining the existing programmatic strengths, infrastructure, and resources with the trending needs of a broad segment of diversified industries is the development and initiation of an engineering physics degree program as an adjunct to an established nuclear engineering curriculum. In line with these developments, a new comprehensive academic program offering baccalaureate, master's, and doctoral degrees in engineering physics has been developed and formally instituted at Rensselaer Polytechnic Institute (RPI). It provides a valuable opportunity for students to pursue education and research that cuts across traditional disciplinary lines, leading to a wide variety of career opportunities in industry, government, national research and defense laboratories, and academia

Undergraduate education in nuclear engineering in the USA

International Nuclear Information System (INIS)

Martin, W.R.

1993-01-01

The discipline of nuclear engineering is described, giving some historical background to explain the structure of the curricula commonly found in nuclear engineering programs in the U.S. Typical curricula are described, along with a specific example given by the University of Michigan undergraduate program in nuclear engineering. The National Academy of Sciences report on U.S. nuclear engineering education is summarized, and the major findings are presented, including data on the number of programs, number of degrees, and enrollment trends. Some discussion is made of manpower trends and the degree to which nuclear programs can supply nuclear engineers to meet the anticipated demands of the current decade and into the next century. (author) 12 refs.; 2 figs.; 4 tabs

Nuclear engineering enrollments and degrees, 1994: Appendixes

International Nuclear Information System (INIS)

1995-05-01

This survey is designed to include those programs sponsored by the Department of Energy. The survey is designed to include those programs offering a major in nuclear engineering or course work equivalent to a major in other engineering disciplines that prepare the graduates to perform as nuclear engineers. This survey provides data on nuclear engineering enrollments and degrees for use in labor market analyses, information on education programs for students, and information on new graduates to employers, government agencies, academia and professional societies

Annual report of Nuclear Engineering Research Laboratory, University of Tokyo in fiscal 1990

International Nuclear Information System (INIS)

1991-01-01

In this annual report, the activities of research and education and the state of operation of the research facilities in this Laboratory in fiscal year 1990 are summarized. There are four large research facilities in this Laboratory, that is, the fast neutron source reactor 'Yayoi', the electron beam linear accelerator, the nuclear fusion reactor blanket experiment device and the heavy ion irradiation research facility. Those are used to execute research and education in the wide fields of atomic energy engineering, and put to the common utilization by universities in whole Japan. The results of the research with these facilities have been reported in the separate reports. The research aims at developing the most advanced and new fields in nuclear reactor engineering, and includes the engineering of the first wall and the fuel cycle for nuclear fusion reactors, electromagnetic structure engineering, AI and robotics, quantum beam engineering, the design of new type reactors, the basic process of radiochemistry and so on. The report on the course of the large scale facilities, research activities, the publication of research, education and the events in the Laboratory in the year are described. (K.I.)

Current challenges for education of nuclear engineers. Beyond nuclear basics

Energy Technology Data Exchange (ETDEWEB)

Schoenfelder, Christian [AREVA GmbH, Offenbach (Germany). Training Center

2014-07-15

In past decades, curricula for the education of nuclear engineers (either as a major or minor subject) have been well established all over the world. However, from the point of view of a nuclear supplier, recent experiences in large and complex new build as well as modernization projects have shown that important competences required in these projects were not addressed during the education of young graduates. Consequently, in the past nuclear industry has been obliged to either accept long periods for job familiarization, or to develop and implement various dedicated internal training measures. Although the topics normally addressed in nuclear engineering education (like neutron and reactor physics, nuclear materials or thermohydraulics and the associated calculation methods) build up important competences, this paper shows that the current status of nuclear applications requires adaptations of educational curricula. As a conclusion, when academic nuclear engineering curricula start taking into account current competence needs in nuclear industry, it will be for the benefit of the current and future generation of nuclear engineers. They will be better prepared for their future job positions and career perspectives, especially on an international level. The recommendations presented should not only be of importance for the nuclear fission field, but also for the fusion community. Here, the Horizon 2020 Roadmap to Fusion as published in 2012 now is focusing on ITER and on a longer-term development of fusion technology for a future demonstration reactor DEMO. The very challenging work program is leading to a strong need for exactly those skills that are described in this article.

Current challenges for education of nuclear engineers. Beyond nuclear basics

International Nuclear Information System (INIS)

Schoenfelder, Christian

2014-01-01

In past decades, curricula for the education of nuclear engineers (either as a major or minor subject) have been well established all over the world. However, from the point of view of a nuclear supplier, recent experiences in large and complex new build as well as modernization projects have shown that important competences required in these projects were not addressed during the education of young graduates. Consequently, in the past nuclear industry has been obliged to either accept long periods for job familiarization, or to develop and implement various dedicated internal training measures. Although the topics normally addressed in nuclear engineering education (like neutron and reactor physics, nuclear materials or thermohydraulics and the associated calculation methods) build up important competences, this paper shows that the current status of nuclear applications requires adaptations of educational curricula. As a conclusion, when academic nuclear engineering curricula start taking into account current competence needs in nuclear industry, it will be for the benefit of the current and future generation of nuclear engineers. They will be better prepared for their future job positions and career perspectives, especially on an international level. The recommendations presented should not only be of importance for the nuclear fission field, but also for the fusion community. Here, the Horizon 2020 Roadmap to Fusion as published in 2012 now is focusing on ITER and on a longer-term development of fusion technology for a future demonstration reactor DEMO. The very challenging work program is leading to a strong need for exactly those skills that are described in this article.

Proceedings of the Scientific Meeting in Nuclear Instrumentation Engineering

International Nuclear Information System (INIS)

Achmad Suntoro; Rony Djokorayono; Ferry Sujatno; Utaja

2010-11-01

The Proceeding of the Scientific Meeting in Nuclear Instrumentation Engineering held on Nov, 30, 2010 by the Centre for Nuclear Instrumentation Engineering - National Nuclear Energy Agency. The Proceedings of the Scientific Contains 40 papers Consist of Nuclear Instrumentation Engineering for Industry, Environment, and Nuclear Facilities. (PPIKSN)

Advanced Instrumentation and control techniques for nuclear power plants

International Nuclear Information System (INIS)

Mori, Nobuyuki; Makino, Maomi; Naito, Norio

1992-01-01

Toshiba has been promoting the development of an advanced instrumentation and control system for nuclear power plants to fulfill the requirements for increased reliability, improved functionality and maintainability, and more competitive economic performance. This system integrates state-of-the-art technologies such as those for the latest man-machine interface, digital processing, optical multiplexing signal transmission, human engineering, and artificial intelligence. Such development has been systematically accomplished based on a schematic view of integrated digital control and instrumentation systems, and the development of whole systems has now been completed. This paper describes the purpose, design philosophy, and contents of newly developed systems, then considers the future trends of advanced man-machine systems. (author)

Advanced scientific computational methods and their applications to nuclear technologies. (3) Introduction of continuum simulation methods and their applications (3)

International Nuclear Information System (INIS)

Satake, Shin-ichi; Kunugi, Tomoaki

2006-01-01

Scientific computational methods have advanced remarkably with the progress of nuclear development. They have played the role of weft connecting each realm of nuclear engineering and then an introductory course of advanced scientific computational methods and their applications to nuclear technologies were prepared in serial form. This is the third issue showing the introduction of continuum simulation methods and their applications. Spectral methods and multi-interface calculation methods in fluid dynamics are reviewed. (T. Tanaka)

Engineering thermal engine rocket adventurer for space nuclear application

International Nuclear Information System (INIS)

Nam, Seung H.; Suh, Kune Y.; Kang, Seong G.

2008-01-01

The conceptual design for the first-of-a-kind engineering of Thermal Engine Rocket Adventure (TERA) is described. TERA comprising the Battery Omnibus Reactor Integral System (BORIS) as the heat resource and the Space Propulsion Reactor Integral System (SPRIS) as the propulsion system, is one of the advanced Nuclear Thermal Rocket (NTR) engine utilizing hydrogen (H 2 ) propellant being developed at present time. BORIS in this application is an open cycle high temperature gas cooled reactor that has eighteen fuel elements for propulsion and one fuel element for electricity generation and propellant pumping. Each fuel element for propulsion has its own small nozzle. The nineteen fuel elements are arranged into hexagonal prism shape in the core and surrounded by outer Be reflector. The TERA maximum power is 1,000 MW th , specific impulse 1,000 s, thrust 250,000 N, and the total mass is 550 kg including the reactor, turbo pump and auxiliaries. Each fuel element comprises the fuel assembly, moderators, pressure tube and small nozzle. The TERA fuel assembly is fabricated of 93% enriched 1.5 mm (U, Zr, Nb)C wafers in 25.3% voided Square Lattice Honeycomb (SLHC). The H 2 propellant passes through these flow channels. This study is concerned with thermohydrodynamic analysis of the fuel element for propulsion with hypothetical axial power distribution because nuclear analysis of TERA has not been performed yet. As a result, when the power distribution of INSPI's M-SLHC is applied to the fuel assembly, the local heat concentration of fuel is more serious and the pressure of the initial inlet H 2 is higher than those of constant average power distribution applied. This means the fuel assembly geometry of 1.5 mm fuel wafers and 25.3% voided SLHC needs to be changed in order to reduce thermal and mechanical shocks. (author)

Nuclear Medicine Engineering

International Nuclear Information System (INIS)

Mateescu, Gheorghe; Craciunescu, Teddy

2000-01-01

'An image is more valuable than a thousand words' - this is the thought that underlies the authors' vision about the field of nuclear medicine. The monograph starts with a review of some theoretical and engineering notions that grounds the field of nuclear medicine: nuclear radiation, interaction of radiation with matter, radiation detection and measurement, numerical analysis. Products and methods needed for the implementation of diagnostic and research procedures in nuclear medicine are presented: radioisotopes and radiopharmaceuticals, equipment for in-vitro (radioimmunoassay, liquid scintillation counting) and in-vivo investigations (thyroid uptake, renography, dynamic studies, imaging). A special attention is focused on medical imaging theory and practice as a source of clinical information (morphological and functional). The large variety of parameters, components, biological structures and specific properties of live matter determines the practical use of three-dimensional tomographic techniques based on diverse physical principles: single-photon emission, positron emission, X-rays transmission, nuclear magnetic resonance, ultrasounds transmission and reflection, electrical impedance measurement. The fundamental reconstruction algorithms i.e., algorithms based on the projection theorem and Fourier filtering, algebraic reconstruction techniques and the algorithms based on statistical principles: maximum entropy, maximum likelihood, Monte Carlo algorithms, are depicted in details. A method based on the use of the measured point spread function is suggested. Some classical but often used techniques like linear scintigraphy and Anger gamma camera imaging are also presented together with some image enhancement techniques like Wiener filtering and blind deconvolution. The topic of the book is illustrated with some clinical samples obtained with nuclear medicine devices developed in the Nuclear Medicine Laboratory of the National Institute of Nuclear Physics and

Welding in nuclear engineering

International Nuclear Information System (INIS)

1982-01-01

The 3rd international conference 'Welding in nuclear engineering', organized in 1978 by the Deutscher Verband fuer Schweisstechnik e.V., was, like the two foregoing conferences in 1970 and 1974, an absolute success. The noteworthy echo to this meeting in the international technical world - the number of 650 participants from 26 countries is self-evidence - and this fact, was for the Deutscher Verband fuer Schweisstechnik e.V. occasion and at the same time an obligation now to follow in the same way, the meeting that was started 12 years ago, by organizing the international conference 'Welding in nuclear engineering'. The conference this year offers in addition to the two plenary session lectures, 34 short reports and a further 28 single contributions in the form of two poster-sessions. Unfortunately, it was again not possible to accept all the papers submitted because the conference was limited to 2 days only. Nevertheless, the papers will offer a representative cross-section through the total range of welding engineering. In particular, the poster session, which take place for the first time within the scope of a meeting organized by the Working Group 'Welding in Nuclear Engineering', should contribute to the aim that this time again the discussions will form the main point of the conference. (orig./RW) [de

Nuclear imaging: Advances and trends

International Nuclear Information System (INIS)

Herk, G. van

1986-01-01

In this article, nuclear imaging instruments that are likely to be of interest to the nuclear medicine community of developing countries are emphasized. The advances, trends, developments, and future directions in the field of nuclear imaging are mentioned

Romanian knowledge transfer network in nuclear physics and engineering - REFIN

International Nuclear Information System (INIS)

Ghitescu, Petre; Prisecaru, Ilie

2007-01-01

According to the requirements of the Romanian Nuclear Programme regarding the education and training of the skilled personnel for the nuclear facilities, a knowledge transfer network named REFIN (in Romanian: Retea Educationala in Fizica si Ingineria Nucleara) was developed since 2005. The knowledge target field is nuclear physics and engineering. The main objective of this network is to develop an effective, flexible and modern educational system in the nuclear physics and engineering area which could meet the requirements of all known types of nuclear facilities and therewith be redundant with the perspectives of the European Research Area (FP7, EURATOM). A global strategy was proposed in order to harmonize the curricula between the network facilities to implement pilot modern teaching programs (courses/modules), to introduce advanced learning methods (as Systematic Approach to Training, e-learning and distance-learning), to strengthen and better use the existing research infrastructures of the research institutes in network. The education and training strategy is divided into several topics: university engineering , master, post-graduate, Ph.D. degree, post-doctoral activity, training for industry, improvement. For the first time in our country, a modular scheme is used allowing staff with different technical background to participate at different levels. In this respect, the European system with transferable credits (ECTS) is used. Based on this strategy, courses in 'Radioactive Waste Management' and 'Numerical and Experimental Methods in Reactor Physics' for both MS students and for industry. This way the training activity which a student attends will allow him or her to be involved, depending on specific professional needs, into a flexible educational scheme. This scheme will ensure competence and enhancement and also the possibility of qualification development and a better mobility on labour market. This kind of activity is already in progress in the

Developing engineering capabilities as a support to a nuclear program

International Nuclear Information System (INIS)

Rodriguez, A.G.

1986-04-01

The performance of a nuclear program needs a quite substantial and diversified volume of technological resources. Its integrated management is one of the basic aspects to be settled. In this regard, the creation of strong engineering organizations with the ability to develop management of the project technical activities as a whole has had success in various countries. These organizations should be provided with suitable means to rapidly assimilate the technology and should serve as a channel and support to local industry in general. The development of a nuclear program also requires the collaboration of other institutions, such as universities and research and development centers. In this sense, engineer and technician training necessities are important both in number and technological qualification, as is the availability of capacities in such different areas as simulation and advanced calculation, geology and soil mechanics, materials, fabrication processes, test laboratories, etc. The volume of technological activities to be developed in relation to a stable, although not necessarily large, nuclear program justifies in itself the assigning of important resources to all the above mentioned activities. However, it should be noted that it has been proved that the nuclear industry is completely pervious as regards other fields of activity. In fact, the more stringent quality requirements are quickly transmitted to other industrial processes, and the engineers trained in this area undergo a far from contemptible turnover towards non-nuclear activities. The basic research area in the nuclear field is not in itself a requirement that has to be in parallel with the development of a nuclear program. However, on medium and long-term bases, it may be interesting for a well balanced commercial program that research activities be established realistically and sensibly, even though short-term practical applications are not necessarily derived from this

Ceramic Technology for Advanced Heat Engines Project

Energy Technology Data Exchange (ETDEWEB)

1990-08-01

The Ceramic Technology For Advanced Heat Engines Project was developed by the Department of Energy's Office of Transportation Systems (OTS) in Conservation and Renewable Energy. This project, part of the OTS's Advanced Materials Development Program, was developed to meet the ceramic technology requirements of the OTS's automotive technology programs. Significant accomplishments in fabricating ceramic components for the Department of Energy (DOE), National Aeronautics and Space Administration (NASA), and Department of Defense (DOD) advanced heat engine programs have provided evidence that the operation of ceramic parts in high-temperature engine environments is feasible. However, these programs have also demonstrated that additional research is needed in materials and processing development, design methodology, and data base and life prediction before industry will have a sufficient technology base from which to produce reliable cost-effective ceramic engine components commercially. An assessment of needs was completed, and a five year project plan was developed with extensive input from private industry. The objective of the project is to develop the industrial technology base required for reliable ceramics for application in advanced automotive heat engines. The project approach includes determining the mechanisms controlling reliability, improving processes for fabricating existing ceramics, developing new materials with increased reliability, and testing these materials in simulated engine environments to confirm reliability. Although this is a generic materials project, the focus is on structural ceramics for advanced gas turbine and diesel engines, ceramic hearings and attachments, and ceramic coatings for thermal barrier and wear applications in these engines.

Nuclear Engineering Enrollments and Degrees Survey, 2005 Data

International Nuclear Information System (INIS)

Oak Ridge Institute for Science and Education

2006-01-01

This annual report details the number of nuclear engineering bachelor's, master's, and doctoral degrees awarded at a sampling of academic programs from 1998-2005. it also looks at nuclear engineering degrees by curriculum and the number of students enrolled in nuclear engineering degree programs at 30 U.S. universities in 2005

A nuclear power plant system engineering workstation

International Nuclear Information System (INIS)

Mason, J.H.; Crosby, J.W.

1989-01-01

System engineers offer an approach for effective technical support for operation and maintenance of nuclear power plants. System engineer groups are being set up by most utilities in the United States. Institute of Nuclear Power operations (INPO) and U.S. Nuclear Regulatory Commission (NRC) have endorsed the concept. The INPO Good Practice and a survey of system engineer programs in the southeastern United States provide descriptions of system engineering programs. The purpose of this paper is to describe a process for developing a design for a department-level information network of workstations for system engineering groups. The process includes the following: (1) application of a formal information engineering methodology, (2) analysis of system engineer functions and activities; (3) use of Electric Power Research Institute (EPRI) Plant Information Network (PIN) data; (4) application of the Information Engineering Workbench. The resulting design for this system engineer workstation can provide a reference for design of plant-specific systems

Construction and engineering report for advanced nuclear fuel development facility

International Nuclear Information System (INIS)

Cho, S. W.; Park, J. S.; Kwon, S.J.; Lee, K. W.; Kim, I. J.; Yu, C. H.

2003-09-01

The design and construction of the fuel technology development facility was aimed to accommodate general nuclear fuel research and development for the HANARO fuel fabrication and advanced fuel researches. 1. Building size and room function 1) Building total area : approx. 3,618m 2 , basement 1st floor, ground 3th floor 2) Room function : basement floor(machine room, electrical room, radioactive waste tank room), 1st floor(research reactor fuel fabrication facility, pyroprocess lab., metal fuel lab., nondestructive lab., pellet processing lab., access control room, sintering lab., etc), 2nd floor(thermal properties measurement lab., pellet characterization lab., powder analysis lab., microstructure analysis lab., etc), 3rd floor(AHU and ACU Room) 2. Special facility equipment 1) Environmental pollution protection equipment : ACU(2sets), 2) Emergency operating system : diesel generator(1set), 3) Nuclear material handle, storage and transport system : overhead crane(3sets), monorail hoist(1set), jib crane(2sets), tank(1set) 4) Air conditioning unit facility : AHU(3sets), packaged air conditioning unit(5sets), 5) Automatic control system and fire protection system : central control equipment(1set), lon device(1set), fire hose cabinet(3sets), fire pump(3sets) etc

Summary of aerospace and nuclear engineering activities

Science.gov (United States)

1988-01-01

The Texas A&M Nuclear and Aerospace engineering departments have worked on five different projects for the NASA/USRA Advanced Design Program during the 1987/88 year. The aerospace department worked on two types of lunar tunnelers that would create habitable space. The first design used a heated cone to melt the lunar regolith, and the second used a conventional drill to bore its way through the crust. Both used a dump truck to get rid of waste heat from the reactor as well as excess regolith from the tunneling operation. The nuclear engineering department worked on three separate projects. The NEPTUNE system is a manned, outer-planetary explorer designed with Jupiter exploration as the baseline mission. The lifetime requirement for both reactor and power-conversion systems was twenty years. The second project undertaken for the power supply was a Mars Sample Return Mission power supply. This was designed to produce 2 kW of electrical power for seven years. The design consisted of a General Purpose Heat Source (GPHS) utilizing a Stirling engine as the power conversion unit. A mass optimization was performed to aid in overall design. The last design was a reactor to provide power for propulsion to Mars and power on the surface. The requirements of 300 kW of electrical power output and a mass of less than 10,000 Rg were set. This allowed the reactor and power conversion unit to fit within the Space Shuttle cargo bay.

Inherently safe nuclear-driven internal combustion engines

International Nuclear Information System (INIS)

Alesso, P.; Chow, Tze-Show; Condit, R.; Heidrich, J.; Pettibone, J.; Streit, R.

1991-01-01

A family of nuclear driven engines is described in which nuclear energy released by fissioning of uranium or plutonium in a prompt critical assembly is used to heat a working gas. Engine performance is modeled using a code that calculates hydrodynamics, fission energy production, and neutron transport self-consistently. Results are given demonstrating a large negative temperature coefficient that produces self-shutoff of energy production. Reduced fission product inventory and the self-shutoff provide inherent nuclear safety. It is expected that nuclear engine reactor units could be scaled from 100 MW on up. 7 refs., 3 figs

Advances in biomedical engineering

CERN Document Server

Brown, J H U

1976-01-01

Advances in Biomedical Engineering, Volume 5, is a collection of papers that deals with application of the principles and practices of engineering to basic and applied biomedical research, development, and the delivery of health care. The papers also describe breakthroughs in health improvements, as well as basic research that have been accomplished through clinical applications. One paper examines engineering principles and practices that can be applied in developing therapeutic systems by a controlled delivery system in drug dosage. Another paper examines the physiological and materials vari

Virginia power nuclear power station engineer training program

International Nuclear Information System (INIS)

Williams, T.M.; Haberstroh-Timpano, S.

1987-01-01

In response to the Institute of Nuclear Power Operations (INPO) accreditation requirements for technical staff and manager, Virginia Power developed the Nuclear Power Station Engineer Training Programs (NPSETP). The NPSETP is directed toward enhancing the specific knowledge and skills of company engineers, especially newly hired engineers. The specific goals of the program are to promote safe and reliable plant operation by providing engineers and appropriate engineering technicians with (1) station-specific basic skills; (2) station-specific specialized skills in the areas of surveillance and test, plant engineering, nuclear safety, and in-service inspection. The training is designed to develop, maintain, and document through demonstration the required knowledge and skills of the engineers in the identified groups at North Anna and Surry Power Stations. The program responds to American National Standards Institute, INPO, and US Nuclear Regulatory Commission standards

Neutrons and Nuclear Engineering

International Nuclear Information System (INIS)

Ekkebus, Allen E.

2007-01-01

Oak Ridge National Laboratory hosted two workshops in April 2007 relevant to nuclear engineering education. In the Neutron Stress, Texture, and Phase Transformation for Industry workshop (http://neutrons.ornl.gov/workshops/nst2/), several invited speakers gave examples of neutron stress mapping for nuclear engineering applications. These included John Root of National Research Council of Canada, Mike Fitzpatrick of the UK's Open University, and Yan Gao of GE Global Research on their experiences with industrial and academic uses of neutron diffraction. Xun-Li Wang and Camden Hubbard described the new instruments at ORNL that can be used for such studies. This was preceded by the Neutrons for Materials Science and Engineering educational symposium (http://neutrons.ornl.gov/workshops/edsym2007). It was directed to the broad materials science and engineering community based in universities, industry and laboratories who wish to learn what the neutron sources in the US can provide for enhancing the understanding of materials behavior, processing and joining. Of particular interest was the presentation of Donald Brown of Los Alamos about using 'Neutron diffraction measurements of strain and texture to study mechanical behavior of structural materials.' At both workshops, the ORNL neutron scattering instruments relevant to nuclear engineering studies were described. The Neutron Residual Stress Mapping Facility (NRSF2) is currently in operation at the High Flux Isotope Reactor; the VULCAN Engineering Materials Diffractometer will begin commissioning in 2008 at the Spallation Neutron Source. For characteristics of these instruments, as well as details of other workshops, meetings, capabilities, and research proposal submissions, please visit http://neutrons.ornl.gov. To submit user proposals for time on NRSF2 contact Hubbard at hubbardcratornl.gov

Civil engineering challenge with nuclear waste

International Nuclear Information System (INIS)

Day, D.

1985-01-01

The civil engineer can help to solve the problems in disposing of nuclear waste in a deep geologic formation. The site for a nuclear waste repository must be carefully selected so that the geology provides the natural barrier between the waste and the accessible environment specified by the NRC and the EPA. This engineer is familiar with the needed structure and conditions of the host and surrounding rocks, and also the hydraulic mechanisms for limiting the migration of water in the rocks. To dispose of the nuclear waste underground requires stable and long-lasting shafts and tunnels such as civil engineers have designed and constructed for many other uses. The planning, design and construction of the ground surface facilities for a nuclear waste repository involves civil engineering in many ways. The transporation of heavy, metal shielded casks requires special attention to the system of highways and railroads accessing the repository. Structures for handling the shipping casks and transferring the waste onsite and into the deep geologic formation need special considerations. The structures must provide the NRC required containment, including hot cells for remote handling. Therefore, structural design strives for buildings, ventilation structures, shaft headframes, etc., to be earthquake and tornado-proof. These important design bases and considerations for the civil engineer working on a nuclear waste repository are discussed in this paper

Robot vision for nuclear advanced robot

International Nuclear Information System (INIS)

Nakayama, Ryoichi; Okano, Hideharu; Kuno, Yoshinori; Miyazawa, Tatsuo; Shimada, Hideo; Okada, Satoshi; Kawamura, Astuo

1991-01-01

This paper describes Robot Vision and Operation System for Nuclear Advanced Robot. This Robot Vision consists of robot position detection, obstacle detection and object recognition. With these vision techniques, a mobile robot can make a path and move autonomously along the planned path. The authors implemented the above robot vision system on the 'Advanced Robot for Nuclear Power Plant' and tested in an environment mocked up as nuclear power plant facilities. Since the operation system for this robot consists of operator's console and a large stereo monitor, this system can be easily operated by one person. Experimental tests were made using the Advanced Robot (nuclear robot). Results indicate that the proposed operation system is very useful, and can be operate by only person. (author)

Status of the Tidal Regenerator Engine for nuclear circulatory support systems

International Nuclear Information System (INIS)

Watelet, R.P.; Ruggles, A.E.; Torti, V.

1976-01-01

Based on the annular version of the Tidal Regenerator Engine, a packaged energy system for nuclear powered circulatory support systems was developed. Net power output of approximately 3 watts is delivered using a 33-watt heat source for an engine module volume of 0.7 liter and a weight of 1.6 kg. A higher efficiency dual cycle version of the annular engine using a Dowtherm A topping cycle on the basic steam cycle is also under development. Projected system output using this advanced engine is 5 watts for the same sized heat source. Life testing of critical components has demonstrated substantial reliability improvement over earlier designs. Of particular significance is the continuing operation of a complete implantable engine system after 1200 hours. Component life testing is continuing with over five thousand hours accumulated on two pump actuators employing welded metal bellows

Final Technical Report and management: NUCLEAR ENGINEERING RECRUITMENT EFFORT

International Nuclear Information System (INIS)

Kerrick, Sharon S.; Vincent, Charles D.

2007-01-01

This report provides the summary of a project whose purpose was to support the costs of developing a nuclear engineering awareness program, an instruction program for teachers to integrate lessons on nuclear science and technology into their existing curricula, and web sites for the exchange of nuclear engineering career information and classroom materials. The specific objectives of the program were as follows: Objective 1--Increase awareness and interest of nuclear engineering; Objective 2--Instruct Teachers on nuclear topics; Objective 3--Nuclear education programs web-site; Objective 4--Support to university/industry matching grants and reactor sharing; Objective 5--Pilot project; and Objective 6--Nuclear engineering enrollment survey at universities

Study of advanced professional educational requirements relative to nuclear fuel cycle engineering in industry and government. Final report

International Nuclear Information System (INIS)

Jur, T.A.; Huhns, M.N.; Keating, D.A.; Orloff, D.I.; Rhodes, C.A.; Stanford, T.G.; Stephens, L.M.; Tatterson, G.B.; Van Brunt, V.

1978-12-01

Under contract with the U.S. Department of Energy, the College of Engineering at the University of South Carolina has conducted an assessment of educational needs among engineers working in nuclear fuel cycle related areas. The study was initiated as a regional effort focusing on the concentration of nuclear industry in the Southeast. Educational needs addressed were those at the post-baccalaureate professional level. The project was envisioned as providing base line information for the eventual implementation of a program in line with the needs of the Southeast's nuclear community. Specific objectives were to establish the content of such a program and to determine those specialized features which would make the program most attractive and useful

Study of advanced professional educational requirements relative to nuclear fuel cycle engineering in industry and government. Final report

Energy Technology Data Exchange (ETDEWEB)

Jur, T.A.; Huhns, M.N.; Keating, D.A.; Orloff, D.I.; Rhodes, C.A.; Stanford, T.G.; Stephens, L.M.; Tatterson, G.B.; Van Brunt, V.

1978-12-01

Under contract with the U.S. Department of Energy, the College of Engineering at the University of South Carolina has conducted an assessment of educational needs among engineers working in nuclear fuel cycle related areas. The study was initiated as a regional effort focusing on the concentration of nuclear industry in the Southeast. Educational needs addressed were those at the post-baccalaureate professional level. The project was envisioned as providing base line information for the eventual implementation of a program in line with the needs of the Southeast's nuclear community. Specific objectives were to establish the content of such a program and to determine those specialized features which would make the program most attractive and useful.

Applying system engineering methods to site characterization research for nuclear waste repositories

International Nuclear Information System (INIS)

Woods, T.W.

1985-01-01

Nuclear research and engineering projects can benefit from the use of system engineering methods. This paper is brief overview illustrating how system engineering methods could be applied in structuring a site characterization effort for a candidate nuclear waste repository. System engineering is simply an orderly process that has been widely used to transform a recognized need into a fully defined system. Such a system may be physical or abstract, natural or man-made, hardware or procedural, as is appropriate to the system's need or objective. It is a way of mentally visualizing all the constituent elements and their relationships necessary to fulfill a need, and doing so compliant with all constraining requirements attendant to that need. Such a system approach provides completeness, order, clarity, and direction. Admittedly, system engineering can be burdensome and inappropriate for those project objectives having simple and familiar solutions that are easily held and controlled mentally. However, some type of documented and structured approach is needed for those objectives that dictate extensive, unique, or complex programs, and/or creation of state-of-the-art machines and facilities. System engineering methods have been used extensively and successfully in these cases. The scientific methods has served well in ordering countless technical undertakings that address a specific question. Similarly, conventional construction and engineering job methods will continue to be quite adequate to organize routine building projects. Nuclear waste repository site characterization projects involve multiple complex research questions and regulatory requirements that interface with each other and with advanced engineering and subsurface construction techniques. There is little doubt that system engineering is an appropriate orchestrating process to structure such diverse elements into a cohesive, well defied project

Human Factors Engineering (HFE) insights for advanced reactors based upon operating experience

International Nuclear Information System (INIS)

Higgins, J.; Nasta, K.

1997-01-01

The NRC Human Factors Engineering Program Review Model (HFE PRM, NUREG-0711) was developed to support a design process review for advanced reactor design certification under 10CFR52. The HFE PRM defines ten fundamental elements of a human factors engineering program. An Operating Experience Review (OER) is one of these elements. The main purpose of an OER is to identify potential safety issues from operating plant experience and ensure that they are addressed in a new design. Broad-based experience reviews have typically been performed in the past by reactor designers. For the HFE PRM the intent is to have a more focussed OER that concentrates on HFE issues or experience that would be relevant to the human-system interface (HSI) design process for new advanced reactors. This document provides a detailed list of HFE-relevant operating experience pertinent to the HSI design process for advanced nuclear power plants. This document is intended to be used by NRC reviewers as part of the HFE PRM review process in determining the completeness of an OER performed by an applicant for advanced reactor design certification. 49 refs

Lifecycle management for nuclear engineering project documents

International Nuclear Information System (INIS)

Zhang Li; Zhang Ming; Zhang Ling

2010-01-01

The nuclear engineering project documents with great quantity and various types of data, in which the relationships of each document are complex, the edition of document update frequently, are managed difficultly. While the safety of project even the nuclear safety is threatened seriously by the false documents and mistakes. In order to ensure the integrality, veracity and validity of project documents, the lifecycle theory of document is applied to build documents center, record center, structure and database of document lifecycle management system. And the lifecycle management is used to the documents of nuclear engineering projects from the production to pigeonhole, to satisfy the quality requirement of nuclear engineering projects. (authors)

2009 UK/US Nuclear Engineering Workshop Report

Energy Technology Data Exchange (ETDEWEB)

Richard Rankin

2009-04-01

This report summarizes the 2009 UK/US Nuclear Engineering Workshop held April 20-21, 2010, in Washington, D.C. to discuss opportunities for nuclear engineering collaboration between researchers in the United States and the United Kingdom.

Ceramic Technology For Advanced Heat Engines Project

Energy Technology Data Exchange (ETDEWEB)

1990-12-01

Significant accomplishments in fabricating ceramic components for the Department of Energy (DOE), National Aeronautics and Space Administration (NASA), and Department of Defense (DoD) advanced heat engine programs have provided evidence that the operation of ceramic parts in high-temperature engine environments is feasible. However, these programs have also demonstrated that additional research is needed in materials and processing development, design methodology, and data base and life prediction before industry will have a sufficient technology base from which to produce reliable cost-effective ceramic engine components commercially. The objective of the project is to develop the industrial technology base required for reliable ceramics for application in advanced automotive heat engines. The project approach includes determining the mechanisms controlling reliability, improving processes for fabricating existing ceramics, developing new materials with increased reliability, and testing these materials in simulated engine environments to confirm reliability. Although this is a generic materials project, the focus is on the structural ceramics for advanced gas turbine and diesel engines, ceramic bearings and attachments, and ceramic coatings for thermal barrier and wear applications in these engines. This advanced materials technology is being developed in parallel and close coordination with the ongoing DOE and industry proof of concept engine development programs. To facilitate the rapid transfer of this technology to U.S. industry, the major portion of the work is being done in the ceramic industry, with technological support from government laboratories, other industrial laboratories, and universities. Abstracts prepared for appropriate papers.

Introduction to nuclear engineering

International Nuclear Information System (INIS)

Gylys, J.

1997-01-01

The textbook, which is the first book in Lithuanian on this subject generalises information on key aspects of nuclear engineering. Specialists in nuclear power for Ignalina NPP and for the infrastructure of nuclear energy sector of Lithuania are prepared at Kaunas University of Technology. The textbooks the students and lecturers have been using to-date were mostly in other languages than Lithuanian and they have not been adapted for teaching in Lithuania's higher educational establishments. This textbook is useful also to anyone who is interested in the issues and future prospects of nuclear power. It contains the chapters on nuclear reactions, theory of nuclear reactors, nuclear reactors kinetics, neutronic analysis, thermalhydraulic calculations of nuclear reactors operation and description of the construction of Ignalina NPP. (author)

GE's advanced nuclear reactor designs

International Nuclear Information System (INIS)

Berglund, R.C.

1993-01-01

The excess of US electrical generating capacity which has existed for the past 15 years is coming to an end as we enter the 1990s. Environmental and energy security issues associated with fossil fuels are kindling renewed interest in the nuclear option. The importance of these issues are underscored by the National Energy Strategy (NES) which calls for actions which open-quotes are designed to ensure that the nuclear power option is available to utilities.close quotes Utilities, utility associations, and nuclear suppliers, under the leadership of the Nuclear Power Oversight Committee (NPOC), have jointly developed a 14-point strategic plan aimed at establishing a predictable regulatory environment, standardized and pre-licensed Advanced Light Water Reactor (ALWR) nuclear plants, resolving the long-term waste management issue, and other open-quotes enabling conditions.close quotes GE is participating in this national effort and GE's family of advanced nuclear power plants feature two reactor designs, developed on a common technology base, aimed at providing a new generation of nuclear plants to provide safe, clean, economical electricity to the world's utilities in the 1990s and beyond. Together, the large-size (1300 MWe) Advanced Boiling Water Reactor (ABWR) and the small-size (600 MWe) Simplified Boiling Water Reactor (SBWR) are innovative, near-term candidates for expanding electrical generating capacity in the US and worldwide. Both possess the features necessary to do so safety, reliably, and economically

Non-proliferation and advances in nuclear science

International Nuclear Information System (INIS)

Iyengar, P.K.

1995-01-01

So far, the non-proliferation treaty (NPT) has concentrated on safeguard regimes based on technologies relating to the production of uranium and plutonium in nuclear reactors, and on their potential diversion for use in nuclear weapons. As nuclear science advances, however, nuclear technology both peaceful and for weapons will change, and for the NPT to remain relevant, it must reflect these changes. At this juncture, when the NPT is coming up for review in a year's time, it is important for physicists to take a fresh look at recent advances in nuclear science, and inform the policy-makers and the public at large about their potential for impacting nuclear technology in the future. In this article a few such advances are highlighted and their implications for the NPT are considered. (author). 4 refs

Advanced stratified charge rotary aircraft engine design study

Science.gov (United States)

Badgley, P.; Berkowitz, M.; Jones, C.; Myers, D.; Norwood, E.; Pratt, W. B.; Ellis, D. R.; Huggins, G.; Mueller, A.; Hembrey, J. H.

1982-01-01

A technology base of new developments which offered potential benefits to a general aviation engine was compiled and ranked. Using design approaches selected from the ranked list, conceptual design studies were performed of an advanced and a highly advanced engine sized to provide 186/250 shaft Kw/HP under cruise conditions at 7620/25,000 m/ft altitude. These are turbocharged, direct-injected stratified charge engines intended for commercial introduction in the early 1990's. The engine descriptive data includes tables, curves, and drawings depicting configuration, performance, weights and sizes, heat rejection, ignition and fuel injection system descriptions, maintenance requirements, and scaling data for varying power. An engine-airframe integration study of the resulting engines in advanced airframes was performed on a comparative basis with current production type engines. The results show airplane performance, costs, noise & installation factors. The rotary-engined airplanes display substantial improvements over the baseline, including 30 to 35% lower fuel usage.

Accreditation of nuclear engineering programs

International Nuclear Information System (INIS)

Williamson, T.G.

1989-01-01

The American Nuclear Society (ANS) Professional Development and Accreditation Committee (PDAC) has the responsibility for accreditation of engineering and technology programs for nuclear and similarly named programs. This committee provides society liaison with the Accreditation Board for Engineering and Technology (ABET), is responsible for the appointment and training of accreditation visitors, nomination of members for the ABET Board and Accreditation Commissions, and review of the criteria for accreditation of nuclear-related programs. The committee is composed of 21 members representing academia and industry. The ABET consists of 19 participating bodies, primarily professional societies, and 4 affiliate bodies. Representation on ABET is determined by the size of the professional society and the number of programs accredited. The ANS, as a participating body, has one member on the ABET board, two members on the Engineering Accreditation Commission, and one on the Technology Accreditation Commission. The ABET board sets ABET policy and the commissions are responsible for accreditation visits

Advanced Engineering Environments for Space Transportation System Development

Science.gov (United States)

Thomas, L. Dale; Smith, Charles A.; Beveridge, James

2000-01-01

There are significant challenges facing today's launch vehicle industry. Global competition, more complex products, geographically-distributed design teams, demands for lower cost, higher reliability and safer vehicles, and the need to incorporate the latest technologies quicker, all face the developer of a space transportation system. Within NASA, multiple technology development and demonstration projects are underway toward the objectives of safe, reliable, and affordable access to space. New information technologies offer promising opportunities to develop advanced engineering environments to meet these challenges. Significant advances in the state-of-the-art of aerospace engineering practice are envisioned in the areas of engineering design and analytical tools, cost and risk tools, collaborative engineering, and high-fidelity simulations early in the development cycle. At the Marshall Space Flight Center, work has begun on development of an advanced engineering environment specifically to support the design, modeling, and analysis of space transportation systems. This paper will give an overview of the challenges of developing space transportation systems in today's environment and subsequently discuss the advanced engineering environment and its anticipated benefits.

Environmental and waste disposal options in nuclear engineering curricula

International Nuclear Information System (INIS)

Elleman, T.S.; Gilligan, J.G.

1991-01-01

The strong national emphasis on waste and environmental issues has prompted increasing interest among nuclear engineering students in study options that will prepare them for careers in these areas. Student interest appears to focus principally on health physics, radioactive waste disposal, and environmental interactions with radionuclides. One motivation for this interest appears to be the growing national programs in environmental restoration and waste remediation that have produced fellowship support for nuclear engineering students as well as employment opportunities. Also, the recent National Academy of sciences study on nuclear engineering education specifically emphasized the importance of expanding nuclear engineering curricula and research programs to include a greater emphasis on radioactive waste and environmental issues. The North Carolina State University (NCSU) Department of Nuclear Engineering is attempting to respond to these needs through the development of course options that will allow students to acquire background in environmental subjects as a complement to the traditional nuclear engineering education

Fuzzy systems and soft computing in nuclear engineering

International Nuclear Information System (INIS)

Ruan, D.

2000-01-01

This book is an organized edited collection of twenty-one contributed chapters covering nuclear engineering applications of fuzzy systems, neural networks, genetic algorithms and other soft computing techniques. All chapters are either updated review or original contributions by leading researchers written exclusively for this volume. The volume highlights the advantages of applying fuzzy systems and soft computing in nuclear engineering, which can be viewed as complementary to traditional methods. As a result, fuzzy sets and soft computing provide a powerful tool for solving intricate problems pertaining in nuclear engineering. Each chapter of the book is self-contained and also indicates the future research direction on this topic of applications of fuzzy systems and soft computing in nuclear engineering. (orig.)

Ceramic Technology for Advanced Heat Engines Project

Energy Technology Data Exchange (ETDEWEB)

1989-08-01

The Ceramic Technology for Advanced Heat Engines Project was developed by the Department of Energy's Office of Transportation Systems (OTS) in Conservation and Renewable Energy. This project, part of the OTS's Advanced Materials Development Program, was developed to meet the ceramic technology requirements of the OTS's automotive technology programs. Significant accomplishments in fabricating ceramic components for the Department of Energy (DOE), National Aeronautics and Space Administration (NASA), and Department of Defense (DoD) advanced heat engine programs have provided evidence that the operation of ceramic parts in high-temperature engine environments is feasible. However, these programs have also demonstrated that additional research is needed in materials and processing development, design methodology, and data base and life prediction before industry will have a sufficient technology base from which to produce reliable cost-effective ceramic engine components commercially.

Nuclear engineering education initiative at Ibaraki University

International Nuclear Information System (INIS)

Matsumura, Kunihito; Kanto, Yasuhiro; Tanaka, Nobuatsu; Saigusa, Mikio; Kurumada, Akira; Kikuchi, Kenji

2015-01-01

With the help of a grant from the Ministry of Education, Culture, Sports, Science and Technology, Ibaraki University has been engaging for six years in the development and preparation of educational environment on nuclear engineering for each of graduate and undergraduate. Core faculty conducts general services including the design and implementation of curriculum, operational improvement, and implementation of lectures. 'Beginner-friendly introduction for nuclear power education' is provided at the Faculty of Engineering, and 'nuclear engineering education program' at the Graduate School of Science and Engineering. All the students who have interest or concern in the accidents at nuclear power plants or the future of nuclear power engineering have opportunities to learn actively. This university participates in the alliance or association with other universities, builds industry - government - academia cooperation with neighboring institutions such as the Japan Atomic Energy Agency, and makes efforts to promote the learning and development of applied skills related to nuclear engineering through training and study tours at each facility. For example, it established the Frontier Applied Atomic Science Center to analyze the structure and function of materials using the strong neutron source of J-PARC. As the efforts after the earthquake accident, it carried out a radiation survey work in Fukushima Prefecture. In addition, it proposed and practiced the projects such as 'development of methods for the evaluation of transfer/fixation properties and decontamination of radioactive substances,' and 'structure analysis of radioactive substances remaining in soil, litter, and polluted water and its application to the decontamination.' (A.O.)

Academic nuclear engineering education - the Dutch way

International Nuclear Information System (INIS)

Wallerbos, E.J.M.; Geemert, R. van

1997-01-01

The academic nuclear engineering educational program in the Netherlands aims not only to give students a thorough knowledge of reactor physics but also to train them in practical skills and presentation techniques. These three aspects are important to become a successful nuclear engineer. (author)

Application of nuclear photon engines for deep-space exploration

International Nuclear Information System (INIS)

Gulevich, Andrey V.; Ivanov, Eugeny A.; Kukharchuk, Oleg F.; Poupko, Victor Ya.; Zrodnikov, Anatoly V.

2001-01-01

Conception of using the nuclear photon rocket engines for deep space exploration is proposed. Some analytical estimations have been made to illustrate the possibility to travel to 100-10000 AU using a small thrust photon engine. Concepts of high temperature nuclear reactors for the nuclear photon engines are also discussed

FY 2007 Progress Report for Advanced Combustion Engine Technologies

Energy Technology Data Exchange (ETDEWEB)

None, None

2007-12-01

Advanced combustion engines have great potential for achieving dramatic energy efficiency improvements in light-duty vehicle applications, where it is suited to both conventional and hybrid- electric powertrain configurations. Light-duty vehicles with advanced combustion engines can compete directly with gasoline engine hybrid vehicles in terms of fuel economy and consumer-friendly driving characteristics; also, they are projected to have energy efficiencies that are competitive with hydrogen fuel cell vehicles when used in hybrid applications.Advanced engine technologies being researched and developed by the Advanced Combustion Engine R&D Sub-Program will also allow the use of hydrogen as a fuel in ICEs and will provide an energy-efficient interim hydrogen-based powertrain technology during the transition to hydrogen/fuelcell-powered transportation vehicles.

Education of nuclear engineering in Japan

International Nuclear Information System (INIS)

Ozawa, Yasutomo; Yamamuro, Nobuhiro

1979-01-01

The research Committee of Nuclear Engineering Education has two working groups. One group has carried out surveyes on the curriculums of nuclear engineering course of universities in Japan and the activities of graduates in the industrial worlds. The other group conducted an investigation on the present status of energy education in senior high schools. This is an interim report on the activity of the research committee. (author)

Advanced Materials Development Program: Ceramic Technology for Advanced Heat Engines program plan, 1983--1993

Energy Technology Data Exchange (ETDEWEB)

1990-07-01

The purpose of the Ceramic Technology for Advanced Heat Engines (CTAHE) Project is the development of an industrial technology base capable of providing reliable and cost-effective high temperature ceramic components for application in advanced heat engines. There is a deliberate emphasis on industrial'' in the purpose statement. The project is intended to support the US ceramic and engine industries by providing the needed ceramic materials technology. The heat engine programs have goals of component development and proof-of-concept. The CTAHE Project is aimed at developing generic basic ceramic technology and does not involve specific engine designs and components. The materials research and development efforts in the CTAHE Project are focused on the needs and general requirements of the advanced gas turbine and low heat rejection diesel engines. The CTAHE Project supports the DOE Office of Transportation Systems' heat engine programs, Advanced Turbine Technology Applications (ATTAP) and Heavy Duty Transport (HDT) by providing the basic technology required for development of reliable and cost-effective ceramic components. The heat engine programs provide the iterative component design, fabrication, and test development logic. 103 refs., 18 figs., 11 tabs.

Labor market trends for nuclear engineers through 2005

International Nuclear Information System (INIS)

Seltzer, N.; Blair, L.M.

1996-10-01

Between 1983 and 1989, employment of nuclear engineers in the nuclear energy field increased almost 40 percent while the annual number of nuclear engineering degrees awarded decreased by almost one-fourth. There were, on average, more job openings for new graduates than there were new graduates available to fill the jobs during the 1980s. This trend reversed in the l990s as nuclear engineering employment in the nuclear energy field decreased from 11,500 in 1991 to 9,400 in 1995. During roughly the same period, the annual number of nuclear engineering degrees increased by 11 percent. As a result, from 1990 through 1995, the number of new graduate nuclear engineers available in the labor supply far exceeded the number of job openings for new graduates in the nuclear energy field. This oversupply of new graduates was particularly acute for 1993 through 1995. During 1996--1997, a relative improvement is expected in job opportunities in the nuclear energy field for new graduates; however, a large oversupply is still expected (almost twice as many graduates available for employment as there are job openings). For 1998 through 2000, some improvement is expected in the relative number of job opportunities for new graduates in the nuclear energy field. Nuclear engineering jobs in the nuclear energy field are expected to decrease only slightly (by less than 150) during this period. Also a 10--15% decrease in the annual number of degrees and available supply of new graduates is expected. Overall, an oversupply is expected (140 graduates available per 100 job openings for new graduates in the nuclear energy field), but this is still a substantial improvement over the current period. For 2001 through 2005, if enrollments and degrees continue to decline, the labor market for new graduates is expected to be approximately balanced. This assumes, however, that the number of degrees and the available supply of new graduates will decrease by 25% from 1995 levels

Application of complex engineering solutions through advanced composite innovation (for repair of degraded buried pipe at Vandellos II Nuclear Power Plant); Reparacion de tuberias de un sistema de servicios no esenciales con recubrimiento interno de fibra de carbono

Energy Technology Data Exchange (ETDEWEB)

Bueno, J. M.; Raji, B. B.

2011-07-01

This technical presentation is focused on introducing an engineering solution approach and identification of sensitivity of applications of advanced carbon fiber in a pressurized wet environment: Engineering design, quality assurance of installation, inspection, and a comprehensive testing program to validate and bench mark the design data and compliance with code requirements in nuclear power plants.

Finally, nuclear engineering textbooks with a Canadian flavour!

International Nuclear Information System (INIS)

Bonin, H.W.

2002-01-01

The need for nuclear engineering textbooks more appropriate to the Canadian nuclear industry context and the CANDU nuclear reactor program has long been felt not only among the universities offering nuclear engineering programs at the graduate level, but also within the Canadian nuclear industry itself. Coverage of the CANDU reactor system in the textbooks presently supporting teaching is limited to a brief description of the concept. Course instructors usually complement these textbooks with course notes written from their personal experience from past employment within the nuclear industry and from their research interests In the last ten years, the Canadian nuclear industry has been involved on an increasing basis with the issue of the technology transfer to foreign countries which have purchased CANDU reactors or have been in the process of purchasing one or several CANDUs. For some of these countries, the 'turn key' approach is required, in which the Canadian nuclear industry looks after everything up to the commissioning of the nuclear power plant, including the education and training of local nuclear engineers and plant personnel. Atomic Energy of Canada Limited (AECL) in particular has dispatched some personnel tasked to prepare and give short courses on some specific aspects of CANDU design and operation, but a lack of consistency was observed as different persons prepared and gave the courses rather independently. To address the many problems tied with nuclear engineering education, the CANTEACH program was set up involving major partners of the Canadian nuclear industry. Parts of the activities foreseen by CANTEACH consist in the writing of nuclear engineering textbooks and associated computer-based pedagogical material. The present paper discusses the main parts of two textbooks being produced, one in reactor physics at steady state and the other on nuclear fuel management. (author)

Advanced nuclear systems. Review study

International Nuclear Information System (INIS)

Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph; Baehr, Roland; Hahn, Lothar

1999-04-01

The task of this review study is to from provide an overview of the developments in the field of the various advanced nuclear systems, and to create the basis for more comprehensive studies of technology assessment. In an overview the concepts for advanced nuclear systems pursued worldwide are subdivided into eight subgroups. A coarse examination raster (set pattern) is developed to enable a detailed examination of the selected systems. In addition to a focus on enhanced safety features, further aspects are also taken into consideration, like the lowering of the proliferation risk, the enhancement of the economic competitiveness of the facilities and new usage possibilities (for instance concerning the relaxation of the waste disposal problem or the usage of alternative fuels to uranium). The question about the expected time span for realization and the discussion about the obstacles on the way to a commercially usable reactor also play a substantial role as well as disposal requirements as far as they can be presently recognized. In the central chapter of this study, the documentation of the representatively selected concepts is evaluated as well as existing technology assessment studies and expert opinions. In a few cases where this appears to be necessary, according technical literature, further policy advisory reports, expert statements as well as other relevant sources are taken into account. Contradictions, different assessments and dissents in the literature as well as a few unsettled questions are thus indicated. The potential of advanced nuclear systems with respect to economical and societal as well as environmental objectives cannot exclusively be measured by the corresponding intrinsic or in comparison remarkable technical improvements. The acceptability of novel or improved systems in nuclear technology will have to be judged by their convincing solutions for the crucial questions of safety, nuclear waste and risk of proliferation of nuclear weapons

Training in nuclear engineering companies

International Nuclear Information System (INIS)

Perezagua, R. L.

2013-01-01

The importance of training is growing in all business areas and fields and especially in hi-tech companies like engineering firms. Nuclear projects are highly multidisciplinary and, even in the initial awarding and pre-construction phases, need to be staffed with personnel that is well-prepared and highly-qualified in areas that, in most cases, are not covered by university studies. This article examines the variables that influence the design of specific training for nuclear projects in engineering firms, along with new training technologies (e-learning) and new regulatory aspects (IS-12). (Author)

Prevent recurrence of nuclear disaster (3). Agenda on nuclear safety from earthquake engineering

International Nuclear Information System (INIS)

Kameda, Hiroyuki; Takada, Tsuyoshi; Ebisawa, Katsumi; Nakamura, Susumu

2012-01-01

Based on results of activities of committee on seismic safety of nuclear power plants (NPPs) of Japan Association for Earthquake Engineering, which started activities after Chuetsu-oki earthquake and then experienced Great East Japan Earthquake, (under close collaboration with the committee of Atomic Energy Society of Japan started activities simultaneously), and taking account of further development of concept, agenda on nuclear safety were proposed from earthquake engineering. In order to prevent recurrence of nuclear disaster, individual technical issues of earthquake engineering and comprehensive issues of integration technology, multidisciplinary collaboration and establishment of technology governance based on them were of prime importance. This article described important problems to be solved; (1) technical issues and mission of seismic safety of NPPs, (2) decision making based on risk assessment - basis of technical governance, (3) framework of risk, design and regulation - framework of required technology governance, (4) technical issues of earthquake engineering for nuclear safety, (5) role of earthquake engineering in nuclear power risk communication and (6) importance of multidisciplinary collaboration. Responsibility of engineering would be attributed to establishment of technology governance, cultivation of individual technology and integration technology, and social communications. (T. Tanaka)

A nuclear engineering curriculum for Asia-Pacific

International Nuclear Information System (INIS)

Bereznai, G.; Sumitra, T.; Chankow, N.; Chanyotha, S.

1996-01-01

This paper describes the nuclear engineering education and professional development curricula that are being developed at Chulalongkorn University in Bangkok, Thailand. The program was initiated in response to the Thai Government's policy to keep the option of nuclear electric generation available as the country responds to the rapid growth of industrialization and increased standard of living, and the accompanying increase in electricity consumption. The program has three main thrusts: university education, professional development, and public education. Although this paper concentrates on the university curriculum, it is shown how the university program is integrated with the development of industry professionals. The Nuclear Engineering Curricula being developed and implemented at Chulalongkorn University will offer programs at the Bachelor, Master and Doctorate levels. The curricula are designed to provide comprehensive education and training for engineers and scientists planning careers in the peaceful use of nuclear energy, with emphasis on the applications to industry and for nuclear electric generation. The Project of Human Resource Development in the Nuclear Engineering field is the result of a cooperative effort between agencies of the Thai and Canadian Governments, including the Electricity Generating Authority of Thailand, the Office of Atomic Energy for Peace, Chulalongkorn University and several other Thai Universities; Atomic Energy of Canada Limited, the Canadian International Development Agency, several Canadian Universities as well as members of the Canadian Nuclear Industry. (author)

Nuclear Engine System Simulation (NESS). Version 2.0: Program user's guide. Final Report

International Nuclear Information System (INIS)

Pelaccio, D.G.; Scheil, C.M.; Petrosky, L.

1993-03-01

This Program User's Guide discusses the Nuclear Thermal Propulsion (NTP) engine system design features and capabilities modeled in the Nuclear Engine System Simulation (NESS): Version 2.0 program (referred to as NESS throughout the remainder of this document), as well as its operation. NESS was upgraded to include many new modeling capabilities not available in the original version delivered to NASA LeRC in Dec. 1991, NESS's new features include the following: (1) an improved input format; (2) an advanced solid-core NERVA-type reactor system model (ENABLER 2); (3) a bleed-cycle engine system option; (4) an axial-turbopump design option; (5) an automated pump-out turbopump assembly sizing option; (6) an off-design gas generator engine cycle design option; (7) updated hydrogen properties; (8) an improved output formnd (9) personal computer operation capability. Sample design cases are presented in the user's guide that demonstrate many of the new features associated with this upgraded version of NESS, as well as design modeling features associated with the original version of NESS

Identification of advanced human factors engineering analysis, design and evaluation methods

International Nuclear Information System (INIS)

Plott, C.; Ronan, A. M.; Laux, L.; Bzostek, J.; Milanski, J.; Scheff, S.

2006-01-01

NUREG-0711 Rev.2, 'Human Factors Engineering Program Review Model,' provides comprehensive guidance to the Nuclear Regulatory Commission (NRC) in assessing the human factors practices employed by license applicants for Nuclear Power Plant control room designs. As software based human-system interface (HSI) technologies supplant traditional hardware-based technologies, the NRC may encounter new HSI technologies or seemingly unconventional approaches to human factors design, analysis, and evaluation methods which NUREG-0711 does not anticipate. A comprehensive survey was performed to identify advanced human factors engineering analysis, design and evaluation methods, tools, and technologies that the NRC may encounter in near term future licensee applications. A review was conducted to identify human factors methods, tools, and technologies relevant to each review element of NUREG-0711. Additionally emerging trends in technology which have the potential to impact review elements, such as Augmented Cognition, and various wireless tools and technologies were identified. The purpose of this paper is to provide an overview of the survey results and to highlight issues that could be revised or adapted to meet with emerging trends. (authors)

Nuclear engineering questions: power, reprocessing, waste, decontamination, fusion

International Nuclear Information System (INIS)

Walton, R.D. Jr.

1979-01-01

This volume contains papers presented at the chemical engineering symposium on nuclear questions. Specific questions addressed by the speakers included: nuclear power - why and how; commercial reprocessing - permanent death or resurrection; long-term management of commercial high-level wastes; long-term management of defense high-level waste; decontamination and decommissioning of nuclear facilities, engineering aspects of laser fusion I; and engineering aspects of laser fusion II. Individual papers have been input to the Energy Data Base previously

Study on the evolution of nuclear engineering professions

International Nuclear Information System (INIS)

2008-01-01

Based on interviews of experts belonging to different companies and institutions (EDF, AREVA, CEA, ASN, IRSN, INSTN), subcontractors, engineers and technicians of the nuclear sector, persons in charge of education, pupils and students, this study gives a synthetic vision of the general context of the needs for nuclear engineering professionals, at the world scale, in the French context, the perceived difficulties faced by this sector, the use of subcontracting, the recruitment needs, the educational profile of engineers and technicians, their revenues, their opinion about their work, the adequacy between education and employment in this sector. It gives estimated figures for engineer and technician recruitment needs for different abilities in the French nuclear engineering

Establishment of professional nuclear power architectural engineering company

International Nuclear Information System (INIS)

Guo Dongli; Chen Hua

2006-01-01

The rapid development of nuclear power industry in China requires specialized management for the nuclear power engineering projects. It is necessary to establish the nuclear power architectural engineering company to meet the increasing market needs by providing the owner with specialized nuclear engineering project management and overall contracting services. It is imperative that the purpose of establishing the corporation and enterprise core competitiveness should be clearly identified when it is established. Its organizational structure should be geared to the enterprise operation management and development to facilitate the intensified project management and control, and improve its risk-proof ability. (authors)

Advanced control systems to improve nuclear power plant reliability and efficiency

International Nuclear Information System (INIS)

1997-07-01

The TECDOC is the result of a series of an advisory and consultants meetings held by the IAEA in 1995-1996 in Vienna (March 1995), in Erlangen Germany (December 1995), in Garching, Germany (June 1996) and in Vienna (November 1996). It was prepared with the participation and contributions of experts from Austria, Canada, Finland, France, Germany, the Republic of Korea, Norway, the Russian Federation, the United Kingdom and the United States of America. The publication not only describes advanced control systems for the improvement of nuclear power plant reliability and efficiency, but also provides a road map to guide interested readers to plan and execute an advanced instrumentation and control project. The subjects include: identification of needs and requirements, justification for safety and user acceptance, and the development of an engineering process. The report should be of interest to nuclear power plant staff, I and C system designers and integrators as well as regulators and researchers. Refs, figs, tabs

Advanced control systems to improve nuclear power plant reliability and efficiency

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

The TECDOC is the result of a series of an advisory and consultants meetings held by the IAEA in 1995-1996 in Vienna (March 1995), in Erlangen Germany (December 1995), in Garching, Germany (June 1996) and in Vienna (November 1996). It was prepared with the participation and contributions of experts from Austria, Canada, Finland, France, Germany, the Republic of Korea, Norway, the Russian Federation, the United Kingdom and the United States of America. The publication not only describes advanced control systems for the improvement of nuclear power plant reliability and efficiency, but also provides a road map to guide interested readers to plan and execute an advanced instrumentation and control project. The subjects include: identification of needs and requirements, justification for safety and user acceptance, and the development of an engineering process. The report should be of interest to nuclear power plant staff, I and C system designers and integrators as well as regulators and researchers. Refs, figs, tabs.

Engineering and science education for nuclear power

International Nuclear Information System (INIS)

Mautner-Markhof, F.

1988-01-01

Experience has shown that one of the critical conditions for the successful introduction of a nuclear power programme is the availability of sufficient numbers of personnel having the required education and experience qualifications. For this reason, the introduction of nuclear power should be preceded by a thorough assessment of the relevant capabilities of the industrial and education/training infrastructures of the country involved. The IAEA assists its Member States in a variety of ways in the development of infrastructures and capabilities for engineering and science education for nuclear power. Types of assistance provided by the IAEA to Member States include: Providing information in connection with the establishment or upgrading of academic and non-academic engineering and science education programmes for nuclear power (on the basis of curricula recommended in the Agency's Guidebook on engineering and science education for nuclear power); Expert assistance in setting up or upgrading laboratories and other teaching facilities; Assessing the capabilities and interest of Member States and their institutions/organizations for technical co-operation among countries, especially developing ones, in engineering and science education, as well as its feasibility and usefulness; Preparing and conducting nuclear specialization courses (e.g. on radiation protection) in various Member States

A comprehensive program of nuclear engineering and science education

International Nuclear Information System (INIS)

Bereznai, G.; Lewis, B.

2014-01-01

The University of Ontario Institute of Technology offers undergraduate degrees in nuclear engineering, nuclear power, health physics and radiation science, graduate degrees (masters as well as doctorate) in nuclear engineering, and graduate diplomas that encompass a wide range of nuclear engineering and technology topics. Professional development programs tailored to specific utility needs are also offered, and the sharing of course material between the professional development and university education courses has strengthened both approaches to ensuring the high qualification levels required of professionals in the nuclear industry. (author)

Genetically Engineered Immunotherapy for Advanced Cancer

Science.gov (United States)

In this trial, doctors will collect T lymphocytes from patients with advanced mesothelin-expressing cancer and genetically engineer them to recognize mesothelin. The gene-engineered cells will be multiplied and infused into the patient to fight the cancer

Advanced Control Considerations for Turbofan Engine Design

Science.gov (United States)

Connolly, Joseph W.; Csank, Jeffrey T.; Chicatelli, Amy

2016-01-01

This paper covers the application of a model-based engine control (MBEC) methodology featuring a self tuning on-board model for an aircraft turbofan engine simulation. The nonlinear engine model is capable of modeling realistic engine performance, allowing for a verification of the advanced control methodology over a wide range of operating points and life cycle conditions. The on-board model is a piece-wise linear model derived from the nonlinear engine model and updated using an optimal tuner Kalman Filter estimation routine, which enables the on-board model to self-tune to account for engine performance variations. MBEC is used here to show how advanced control architectures can improve efficiency during the design phase of a turbofan engine by reducing conservative operability margins. The operability margins that can be reduced, such as stall margin, can expand the engine design space and offer potential for efficiency improvements. Application of MBEC architecture to a nonlinear engine simulation is shown to reduce the thrust specific fuel consumption by approximately 1% over the baseline design, while maintaining safe operation of the engine across the flight envelope.

Human factors survey of advanced instrumentation and controls technologies in nuclear plants

International Nuclear Information System (INIS)

Carter, R.J.

1992-01-01

A survey of advanced instrumentation and controls (I ampersand C) technologies and associated human factors issues in the US and Canadian nuclear industries was carried out by a team from Oak Ridge national laboratory to provide background for the development of regulatory policy, criteria, and guides for review of advanced I ampersand C systems as well as human engineering guidelines for evaluating these systems. The survey found those components of the US nuclear industry surveyed to be quite interested in advanced I ampersand C, but very cautious in implementing such systems in nuclear facilities and power plants. The trend in the facilities surveyed is to experiment cautiously when there is an intuitive advantage or short-term payoff. In the control room, the usual practice is direct substitution of digital and microprocessor-based instruments or systems that are functionally identical to the analog instruments or systems being replaced. The most advanced I ampersand C systems were found in the Canadian CANDU plants, where the newest plant has digital system in almost 100% of its control systems and in over 70% of its plant protection system. The hypothesis that properly 'introducing digital systems increases safety' is supported by the Canadian experience. The performance of these digital systems was achieved using an appropriate quality assurance program for the software development. The ability of digital systems to detect impending failures and initiate a fail-safe action, is a significant safety issue that should be of special interest to every US utility as well as to the US Nuclear Regulatory Commission. (orig.)

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1970-01-01

Advances in Nuclear Science and Technology, Volume 5 presents the underlying principles and theory, as well as the practical applications of the advances in the nuclear field. This book reviews the specialized applications to such fields as space propulsion.Organized into six chapters, this volume begins with an overview of the design and objective of the Fast Flux Test Facility to provide fast flux irradiation testing facilities. This text then examines the problem in the design of nuclear reactors, which is the analysis of the spatial and temporal behavior of the neutron and temperature dist

Advances in nuclear science and technology

CERN Document Server

Greebler, Paul

1966-01-01

Advances in Nuclear Science and Technology, Volume 3 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book presents the advances in the atomic energy field.Organized into six chapters, this volume begins with an overview of the use of pulsed neutron sources for the determination of the thermalization and diffusion properties of moderating as well as multiplying media. This text then examines the effect of nuclear radiation on electronic circuitry and its components. Other chapters consider radiation effects in various inorganic solids, with empha

Nuclear engine system simulation (NESS) program update

International Nuclear Information System (INIS)

Scheil, C.M.; Pelaccio, D.G.; Petrosky, L.J.

1993-01-01

The second phase of development of a Nuclear Thermal Propulsion (NTP) engine system design analysis code has been completed. The standalone, versatile Nuclear Engine System Simulation (NESS) code provides an accurate, detailed assessment of engine system operating performance, weight, and sizes. The critical information is required to support ongoing and future engine system and stage design study efforts. This recent development effort included incorporation of an updated solid-core nuclear thermal reactor model that yields a reduced core weight and higher fuel power density when compared to a NERVA type reactor. NESS can now analyze expander, gas generator, and bleed cycles, along with multi-redundant propellant pump feed systems. Performance and weight of efficient multi-stage axial turbopump can now be determined, in addition to the traditional centrifugal pump

Ignition timing advance in the bi-fuel engine

Directory of Open Access Journals (Sweden)

Marek FLEKIEWICZ

2009-01-01

Full Text Available The influence of ignition timing on CNG combustion process has been presented in this paper. A 1.6 liter SI engine has been tested in the special program. For selected engine operating conditions, following data were acquired: in cylinder pressure, crank angle, fuel mass consumption and exhaust gases temperatures. For the timing advance correction varying between 0 to 15 deg crank angle, the internal temperature of combustion chamber, as well as the charge combustion ratio and ratio of heat release has been estimated. With the help of the mathematical model, emissions of NO, CO and CO2 were additionally estimated. Obtained results made it possible to compare the influence of ignition timing advance on natural gas combustion in the SI engine. The engine torque and in-cylinder pressure were used for determination of the optimum engine timing advance.

Handbook of nuclear engineering: vol 1: nuclear engineering fundamentals; vol 2: reactor design; vol 3: reactor analysis; vol 4: reactors of waste disposal and safeguards

CERN Document Server

2013-01-01

The Handbook of Nuclear Engineering is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all academic levels, this five volume set provides the latest findings in nuclear data and experimental techniques, reactor physics, kinetics, dynamics and control. Readers will also find a detailed description of data assimilation, model validation and calibration, sensitivity and uncertainty analysis, fuel management and cycles, nuclear reactor types and radiation shielding. A discussion of radioactive waste disposal, safeguards and non-proliferation, and fuel processing with partitioning and transmutation is also included. As nuclear technology becomes an important resource of non-polluting sustainable energy in the future, The Handbook of Nuclear Engineering is an excellent reference for practicing engineers, researchers and professionals.

Impact of quality concepts on nuclear engineering accreditation

International Nuclear Information System (INIS)

Woodall, D.M.

1993-01-01

This paper is an update of the accreditation process for nuclear engineering education at the undergraduate and graduate level in U.S. universities and colleges. The Engineering Accreditation Commission (EAC) of the Accreditation Board for Engineering and Technology (ABET) has made a number of major changes in the process for engineering accreditation in recent years. This paper identifies those changes that have taken place, discusses the rationale for those changes, and encourages U.S. universities with nuclear engineering programs to respond

Frontiers of advanced engineering materials (faem-06)

International Nuclear Information System (INIS)

Alam, S.; Mirza, J.A.

2006-01-01

The second international conference on Frontiers of Advanced Engineering Materials was held on 04-06 December 2006 in Lahore, Pakistan. At a time of the rapid expending enormous potential for the wide spread development and usage of Advanced Engineering Materials. About 121 papers were presented by engineers and scientists from 30 organizations, academic institutions and foreign experts from six countries. on the recommendation of a panel after review, only 72 papers were included in this conference proceedings. The main areas of interest which remained under focus during the conference were structure property relationship, surface Modifications, Nano Technology, Super and semi conductors, Magnetic Materials, Materials Proceeding, Glass and Ceramics, Composite Materials. This Conference open a way to help in strengthening the bounds between our foreign guests local and delegates. The participants showed their keen interest in the poster sessions. Fruitful conclusions of these presentations will be helpful to give rise to new topics of research in the fields of advanced engineering Materials. (A.B.)

Advanced Engineering Environments: Implications for Aerospace Manufacturing

Science.gov (United States)

Thomas, D.

2001-01-01

There are significant challenges facing today's aerospace industry. Global competition, more complex products, geographically-distributed design teams, demands for lower cost, higher reliability and safer vehicles, and the need to incorporate the latest technologies quicker all face the developer of aerospace systems. New information technologies offer promising opportunities to develop advanced engineering environments (AEEs) to meet these challenges. Significant advances in the state-of-the-art of aerospace engineering practice are envisioned in the areas of engineering design and analytical tools, cost and risk tools, collaborative engineering, and high-fidelity simulations early in the development cycle. These advances will enable modeling and simulation of manufacturing methods, which will in turn allow manufacturing considerations to be included much earlier in the system development cycle. Significant cost savings, increased quality, and decreased manufacturing cycle time are expected to result. This paper will give an overview of the NASA's Intelligent Synthesis Environment, the agency initiative to develop an AEE, with a focus on the anticipated benefits in aerospace manufacturing.

Career Development in Nuclear Engineering

International Nuclear Information System (INIS)

Sibbens, G.

2015-01-01

In the eighties it was not common for girls to study engineering. But a few young girls have always been fascinated by science and technical applications and dared to go for a gender untypical education. What are these female engineers doing today? This paper describes the career development of a woman, who completed her Master of Science in Nuclear Engineering, found first a job in an international company as cooperator in the research group of radiation physics and later as head of technical support and quality assurance of medical systems and then succeeded in a competition to be recruited at the European Commission (EC). There she started as an assistant for the primary standardisation of radionuclides and high-resolution alpha-particle spectrometry including the preparation of radioactive sources in the radionuclide metrology sector at the Institute for Reference Materials and Measurements of the European Commission’s Joint Research Centre and consequently published her work in scientific journals. Today, 29 years later, I am the laboratory responsible for the preparation and characterisation of nuclear targets at EC-JRC-IRMM, leading a team that has unique know-how in the preparation of thin film deposits (called targets) tailor-made for nuclear physics measurements at the EC–JRC–IRMM and international accelerator sites. High quality measurements of nuclear data and materials are being asked for in the context of nuclear safety, minimisation of high level nuclear waste and safeguards and security. The different steps of my career development and the repeated process of managing learning, work, family and leisure are presented. The career path across different jobs and responsibilities and the career progress via a certification training programme are also explained to encourage the next generation of female professionals to continue playing a vital role in nuclear science and technology. (author)

To all of you who continue supporting Japanese Nuclear Power. A letter from nuclear engineer

International Nuclear Information System (INIS)

Sato, Satoshi

2012-01-01

Fukushima accident could not justify nuclear power and obliged nuclear engineers to accept public opinion such as 'nuclear power phase out' in 2030s. During the 'phase out' period, selected nuclear power plants would be restarted taking account of safety and accident effects with reinforced safety countermeasures against Fukushima accident, while shutdown reactor decommissioning with best technologies and intermediate storage of spent fuels before final disposal would be implemented. At the completion of 'phase out', Japanese nuclear power would end. However, renewable energy could not make such progress as expected and consumption of fossil energy would not decrease, which worsened environment and climate in Japan terribly and the public might think wrong decision of 'phase out' in 2012 and again request nuclear power. This nuclear power should be based on 'most advanced safety in the world', whose principle should be discussed and related R and D should be conducted beforehand. Such reactor would be developed to prevent core meltdown or assure containment integrity with 100% passive phenomena without any external power or human works against any cause's accidents, while spent fuels with not containing significant amount of long-life radioactive materials should be stored within artificial structures so as to reduce radioactivity level equivalent to outer environment. (T. Tanaka)

Advances in biomedical engineering

CERN Document Server

Brown, J H U

1973-01-01

Advances in Biomedical Engineering, Volume 2, is a collection of papers that discusses the basic sciences, the applied sciences of engineering, the medical sciences, and the delivery of health services. One paper discusses the models of adrenal cortical control, including the secretion and metabolism of cortisol (the controlled process), as well as the initiation and modulation of secretion of ACTH (the controller). Another paper discusses hospital computer systems-application problems, objective evaluation of technology, and multiple pathways for future hospital computer applications. The pos

Advanced Natural Gas Reciprocating Engine(s)

Energy Technology Data Exchange (ETDEWEB)

Kwok, Doris; Boucher, Cheryl

2009-09-30

Energy independence and fuel savings are hallmarks of the nation’s energy strategy. The advancement of natural gas reciprocating engine power generation technology is critical to the nation’s future. A new engine platform that meets the efficiency, emissions, fuel flexibility, cost and reliability/maintainability targets will enable American manufacturers to have highly competitive products that provide substantial environmental and economic benefits in the US and in international markets. Along with Cummins and Waukesha, Caterpillar participated in a multiyear cooperative agreement with the Department of Energy to create a 50% efficiency natural gas powered reciprocating engine system with a 95% reduction in NOx emissions by the year 2013. This platform developed under this agreement will be a significant contributor to the US energy strategy and will enable gas engine technology to remain a highly competitive choice, meeting customer cost of electricity targets, and regulatory environmental standard. Engine development under the Advanced Reciprocating Engine System (ARES) program was divided into phases, with the ultimate goal being approached in a series of incremental steps. This incremental approach would promote the commercialization of ARES technologies as soon as they emerged from development and would provide a technical and commercial foundation of later-developing technologies. Demonstrations of the Phase I and Phase II technology were completed in 2004 and 2008, respectively. Program tasks in Phase III included component and system development and testing from 2009-2012. Two advanced ignition technology evaluations were investigated under the ARES program: laser ignition and distributed ignition (DIGN). In collaboration with Colorado State University (CSU), a laser ignition system was developed to provide ignition at lean burn and high boost conditions. Much work has been performed in Caterpillar’s DIGN program under the ARES program. This work

Introduction to nuclear engineering

International Nuclear Information System (INIS)

Bouchard, J.; Deffain, J.P.; Gouchet, A.

2007-01-01

This book is an introductory course to the technology of nuclear reactors, it is based on lectures given to students engaged in nuclear engineering curricula. A brief historical account of nuclear power is given in which Three Miles Island and Chernobyl accidents appear to be the main milestones because of their big impacts on the way to apprehend the safety in the design of a reactor for the first and on the public controversy of nuclear energy for the second. All the concepts and knowledge required to understand the design of a reactor and how it operates, are described: radioactivity, nuclear safety, irradiation effects on materials, uranium enrichment, reactor kinetics, fission products poisoning,... This book is made up of 4 parts: 1) nuclear power, 2) types of power nuclear reactors (PWR, BWR and fast reactors), 3) the fuel cycle, and 4) neutronics basics. (A.C.)

Public information and acceptance of nuclear engineering studies at the faculty of nuclear sciences and physical engineering of CTU Prague

Energy Technology Data Exchange (ETDEWEB)

Musilek, Ladislav; Matejka, Karel [Czech Technical University in Prague, Faculty of Nuclear Sciences and Physical Engineering, Brehova 7, 115 19 Prague 1 (Czech Republic)

1993-07-01

The Faculty of Nuclear Sciences and Physical Engineering was founded in 1955, when the nuclear program in Czechoslovakia has been launched. In approximately the same time also some nuclear research institutes were founded, as, e.g., the Institute of Nuclear Research and the Research Institute of Nuclear Instruments, etc., extensive plans of development of nuclear power production were drafted, and everybody was very enthusiastic for this new branch of science and technology. The present status of nuclear technology and the new trends in applied hard sciences have resulted in widening the profile of the Faculty, because the staff has intended to preserve it as a modern and advanced part of the University. It means that now nuclear sciences represent about one third of the programme and the structure of its responsibilities. What is the public acceptance of the Faculty nowadays? Two unfavourable trends act against the interest to enrol at the Faculty. The first one is general - a decreasing interest of the young in engineering, given probably by both higher work-load in comparison with, e.g., social sciences, and a not very high social status of engineering graduates in the former socialist society. The second trend is given by a strong antinuclear opposition and campaigns in the past few years, relatively latent between the Chernobyl accident and 1989, because the former regime had not allow any discussions about this subject, and clearly apparent after the 1989 November revolution. These antinuclear tendencies were also fuelled by the effective Greenpeace campaign in 1990, imported mostly from Austria, and, unfortunately, unfounded from the scientific point of view. How can the Faculty resist this ebb of interest? First of all this can be achieved by suitable modification of curricula towards 'computerisation' and {sup e}cologisation{sup .} Among other activities priority is given to cooperation with mass media as the press, TV etc. Direct contacts with high and

Public information and acceptance of nuclear engineering studies at the faculty of nuclear sciences and physical engineering of CTU Prague

International Nuclear Information System (INIS)

Musilek, Ladislav; Matejka, Karel

1993-01-01

The Faculty of Nuclear Sciences and Physical Engineering was founded in 1955, when the nuclear program in Czechoslovakia has been launched. In approximately the same time also some nuclear research institutes were founded, as, e.g., the Institute of Nuclear Research and the Research Institute of Nuclear Instruments, etc., extensive plans of development of nuclear power production were drafted, and everybody was very enthusiastic for this new branch of science and technology. The present status of nuclear technology and the new trends in applied hard sciences have resulted in widening the profile of the Faculty, because the staff has intended to preserve it as a modern and advanced part of the University. It means that now nuclear sciences represent about one third of the programme and the structure of its responsibilities. What is the public acceptance of the Faculty nowadays? Two unfavourable trends act against the interest to enrol at the Faculty. The first one is general - a decreasing interest of the young in engineering, given probably by both higher work-load in comparison with, e.g., social sciences, and a not very high social status of engineering graduates in the former socialist society. The second trend is given by a strong antinuclear opposition and campaigns in the past few years, relatively latent between the Chernobyl accident and 1989, because the former regime had not allow any discussions about this subject, and clearly apparent after the 1989 November revolution. These antinuclear tendencies were also fuelled by the effective Greenpeace campaign in 1990, imported mostly from Austria, and, unfortunately, unfounded from the scientific point of view. How can the Faculty resist this ebb of interest? First of all this can be achieved by suitable modification of curricula towards 'computerisation' and e cologisation . Among other activities priority is given to cooperation with mass media as the press, TV etc. Direct contacts with high and grammar

Status report on research on advanced fundamental engineering in 1999

International Nuclear Information System (INIS)

2000-07-01

JNC (Japan Nuclear Cycle Development Institute) has been promoting the cooperative research program on advanced fundamental engineering with the Japanese Universities. It is the 5th year of this program on 1999. JNC has been calling for the research themes of utilizing the equipment and facilities of JNC, which must be the leading research for the JNC projects. The expert committee has selected the issues from the applications of the universities; This report includes the list of the researches and individual summaries implemented in 1999, in which total 49 issues are categorized in the three fields, these are, fast breeder reactor, nuclear fuel cycle, and environment technology. The 26 issues are included in the field of fast breeder reactor. Topics in this area are neutron beam technology to measure voids, laser technology to detect failed fuel, ultra-sonic velocity meter to estimate passive cooling characteristics, behavior of sodium coolant in accidents, physics on TRU fuel, and mechanical and/or chemical characteristics on irradiated solid metals, ceramics and liquids. The 9 issues are included in the field of nuclear fuel cycle. Topics in this area are chemical erosion of material, computerized simulation on actinide by molecular orbit model, chemical stability on advanced reprocessing, laser technology to measure fuel particles, decomposition of fluoride oil, advanced dose evaluation. The 9 issues are included in the field of environment technology. Topics in this area are behavior of underground water, radioactivity ecology of plants, biochemical activities of microbes in deep bedrock. The individual report describes the title, related personnel, its time schedule, objectives, facilities, status, and references in the prearranged format. (Tanaka, T.)

Advanced scientific computational methods and their applications of nuclear technologies. (1) Overview of scientific computational methods, introduction of continuum simulation methods and their applications (1)

International Nuclear Information System (INIS)

Oka, Yoshiaki; Okuda, Hiroshi

2006-01-01

Scientific computational methods have advanced remarkably with the progress of nuclear development. They have played the role of weft connecting each realm of nuclear engineering and then an introductory course of advanced scientific computational methods and their applications to nuclear technologies were prepared in serial form. This is the first issue showing their overview and introduction of continuum simulation methods. Finite element method as their applications is also reviewed. (T. Tanaka)

Symposium on engineering with nuclear explosives. Proceedings. Volume 2

International Nuclear Information System (INIS)

1970-05-01

This symposium on 'Engineering with Nuclear Explosives' reports to the Plowshare community, both national and international, the progress achieved since April 1964, the date of the Third Plowshare Symposium. In structuring the technical presentations, contributions of broadest interest were placed at the beginning, thus forming a common base of current information and applied science understanding developed in support of Plowshare technology. Sessions of speciality or pertaining to specific areas of application and engineering follow logically in the program. The Plenary Session reviewed the current status of the Plowshare Program from the technical, government, and industrial points of view. The 112 papers presented at 15 technical sessions covered all technical aspects of the Plowshare Program. The conference summary reviewed principal themes, areas of significant advance, and subjects requiring further attention that emerged during the technical conference. This proceedings is the record of the symposium

Symposium on engineering with nuclear explosives. Proceedings. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1970-05-01

This symposium on 'Engineering with Nuclear Explosives' reports to the Plowshare community, both national and international, the progress achieved since April 1964, the date of the Third Plowshare Symposium. In structuring the technical presentations, contributions of broadest interest were placed at the beginning, thus forming a common base of current information and applied science understanding developed in support of Plowshare technology. Sessions of speciality or pertaining to specific areas of application and engineering follow logically in the program. The Plenary Session reviewed the current status of the Plowshare Program from the technical, government, and industrial points of view. The 112 papers presented at 15 technical sessions covered all technical aspects of the Plowshare Program. The conference summary reviewed principal themes, areas of significant advance, and subjects requiring further attention that emerged during the technical conference. These proceedings are the record of the symposium.

Symposium on engineering with nuclear explosives. Proceedings. Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1970-05-15

This symposium on 'Engineering with Nuclear Explosives' reports to the Plowshare community, both national and international, the progress achieved since April 1964, the date of the Third Plowshare Symposium. In structuring the technical presentations, contributions of broadest interest were placed at the beginning, thus forming a common base of current information and applied science understanding developed in support of Plowshare technology. Sessions of speciality or pertaining to specific areas of application and engineering follow logically in the program. The Plenary Session reviewed the current status of the Plowshare Program from the technical, government, and industrial points of view. The 112 papers presented at 15 technical sessions covered all technical aspects of the Plowshare Program. The conference summary reviewed principal themes, areas of significant advance, and subjects requiring further attention that emerged during the technical conference. This proceedings is the record of the symposium.

Symposium on engineering with nuclear explosives. Proceedings. Vol. 1

International Nuclear Information System (INIS)

1970-05-01

This symposium on 'Engineering with Nuclear Explosives' reports to the Plowshare community, both national and international, the progress achieved since April 1964, the date of the Third Plowshare Symposium. In structuring the technical presentations, contributions of broadest interest were placed at the beginning, thus forming a common base of current information and applied science understanding developed in support of Plowshare technology. Sessions of speciality or pertaining to specific areas of application and engineering follow logically in the program. The Plenary Session reviewed the current status of the Plowshare Program from the technical, government, and industrial points of view. The 112 papers presented at 15 technical sessions covered all technical aspects of the Plowshare Program. The conference summary reviewed principal themes, areas of significant advance, and subjects requiring further attention that emerged during the technical conference. These proceedings are the record of the symposium

Past, Present and Future of Nuclear Power Engineering in the Republic of Kazakhstan

International Nuclear Information System (INIS)

Shkolnik, V.S.

2000-01-01

The main goal of Kazakhstan Strategy of Development till 2030 is to improve the well-being of the Society based on sustainable development of the market economy. Nowadays nuclear power engineering became an important integral part of world power production, allowing to rack up power production and assisting in solving global and regional ecological issues at the same time. However, choice of power source for a certain country or a certain region depends upon a set of different factors.Natural, social and economic conditions of Kazakhstan make it reasonable to establish and develop national nuclear power engineering that would become a basic component of power supply industry in the state. Currently, the Ministry of Power Engineering, Industry and Trade is working out a project of a State program entitled 'Development of Nuclear Power and Uranium Industry in the Republic of Kazakhstan' that will be submitted for consideration to the RK Government next December. Construction of Balkhash Atomic Power Plant planned under the Program would allow solving the problem of power supply for the southern part of the Republic. Construction and commissioning of nuclear power plants in Almaty, Astana and Ust-Kamenogorsk would provide steady and reliable heat supply in these largest cities of the Republic for a long period of time. Would the Government agree upon the State Program, we would have all the reasons to believe that in the near future the Republic of Kazakhstan will become a state with advanced nuclear power engineering based on use of up-to-date power technologies in combination with principles of cost efficiency guaranteed for general and environmental safety

Advances in biomedical engineering

CERN Document Server

Brown, J H U

1976-01-01

Advances in Biomedical Engineering, Volume 6, is a collection of papers that discusses the role of integrated electronics in medical systems and the usage of biological mathematical models in biological systems. Other papers deal with the health care systems, the problems and methods of approach toward rehabilitation, as well as the future of biomedical engineering. One paper discusses the use of system identification as it applies to biological systems to estimate the values of a number of parameters (for example, resistance, diffusion coefficients) by indirect means. More particularly, the i

FY2014 Advanced Combustion Engine Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

None

2015-03-01

The Advanced Combustion Engine research and development (R&D) subprogram within the DOE Vehicle Technologies Office (VTO) provides support and guidance for many cutting-edge automotive technologies under development. Research focuses on addressing critical barriers to commercializing higher efficiency, very low emissions advanced internal combustion engines for passenger and commercial vehicles.

FY2016 Advanced Combustion Engine Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

None, None

2017-07-01

The Advanced Combustion Engine research and development (R&D) subprogram within the DOE Vehicle Technologies Office (VTO) provides support and guidance for many cutting-edge automotive technologies under development. Research focuses on addressing critical barriers to commercializing higher efficiency, very low emissions advanced internal combustion engines for passenger and commercial vehicles.

FY2015 Advanced Combustion Engine Annual Progress Report

Energy Technology Data Exchange (ETDEWEB)

Singh, Gurpreet [Vehicle Technologies Office, Washington, DC (United States); Gravel, Roland M. [Vehicle Technologies Office, Washington, DC (United States); Howden, Kenneth C. [Vehicle Technologies Office, Washington, DC (United States); Breton, Leo [Vehicle Technologies Office, Washington, DC (United States)

2016-03-25

The Advanced Combustion Engine research and development (R&D) subprogram within the DOE Vehicle Technologies Office (VTO) provides support and guidance for many cutting-edge automotive technologies under development. Research focuses on addressing critical barriers to commercializing higher efficiency, very low emissions advanced internal combustion engines for passenger and commercial vehicles.

Nuclear industry - challenges in chemical engineering

International Nuclear Information System (INIS)

Sen, S.; Sunder Rajan, N.S.; Balu, K.; Garg, R.K.; Murthy, L.G.K.; Ramani, M.P.S.; Rao, M.K.; Sadhukhan, H.K.; Venkat Raj, V.

1978-01-01

Chemical engineering processes and operations are closely involved in every step of the nuclear fuel cycle. Starting from mining and milling of the ore through the production of fuel and other materials and their use in nuclear reactors, fuel reprocessing, fissile material recycle and treatment and disposal of fission product wastes, each step presents a challenge to the chemical engineer to evolve and innovate processes and techniques for more efficient utilization of the energy in the atom. The requirement of high recovery of the desired components at high purity levels is in itself a challenge. ''Nuclear Grade'' specifications for materials put a requirement which very few industries can satisfy. Recovery of uranium and thorium from low grade ores, of heavy water from raw water, etc. are examples. Economical and large scale separation of isotopes particularly those of heavy elements is a task for which processess are under various stages of development. Further design of chemical plants such as fuel reprocessing plants and high level waste treatment plants, which are to be operated and maintained remotely due to the high levels of radio-activity call for engineering skills which are being continually evolved. In the reactor, analysis of the fluid mechanics and optimum design of heat removal system are other examples where a chemical engineer can play a useful role. In addition to the above, the activities in the nuclear industry cover a very wide range of chemical engineering applications, such as desalination and other energy intensive processes, radioisotope and radiation applications in industry, medicine and agriculture. (auth.)

HIGH SERVE '90 - nuclear engineering services

International Nuclear Information System (INIS)

Bauer, K.G.

1991-01-01

Nuclear engineering services do not start only with maintenance or repair, but already with the early detection of imminent problems long before they become problems. Services concerning the decommissioning of plants also belong to it. A selection of the extraordinary services rendered nowadays is presented in more than 20 papers in this booklet. These papers may roughly be divided into three groups of subjects: monitoring and operational management; maintenance, repair and improvements; radioactive waste treatment and management. The first group of subjects, in particular, covers papers dealing with early detection, monitoring and diagnosing systems, using highly advanced hard- and software technologies. Modernization of instrumentation and control systems and exchange of process computer systems is another task this service has to accomplish. Process computers of the past have developed into high performance process information systems. (orig./DG) [de

Thermohydraulic Design Analysis Modeling for Korea Advanced NUclear Thermal Engine Rocket for Space Application

Energy Technology Data Exchange (ETDEWEB)

Nam, Seung Hyun; Choi, Jae Young; Venneria, Paolo F.; Jeong, Yong Hoon; Chang, Soon Heung [KAIST, Daejeon (Korea, Republic of)

2015-05-15

Space exploration is a realistic and profitable goal for long-term humanity survival, although the harsh space environment imposes lots of severe challenges to space pioneers. To date, almost all space programs have relied upon Chemical Rockets (CRs) rating superior thrust level to transit from the Earth's surface to its orbit. However, CRs inherently have insurmountable barrier to carry out deep space missions beyond Earth's orbit due to its low propellant efficiency, and ensuing enormous propellant requirement and launch costs. Meanwhile, nuclear rockets typically offer at least two times the propellant efficiency of a CR and thus notably reduce the propellant demand. Particularly, a Nuclear Thermal Rocket (NTR) is a leading candidate for near-term manned missions to Mars and beyond because it satisfies a relatively high thrust as well as a high efficiency. The superior efficiency of NTRs is due to both high energy density of nuclear fuel and the low molecular weight propellant of Hydrogen (H{sub 2}) over the chemical reaction by-products. A NTR uses thermal energy released from a nuclear fission reactor to heat the H{sub 2} propellant and then exhausted the highly heated propellant through a propelling nozzle to produce thrust. A propellant efficiency parameter of rocket engines is specific impulse (I{sub s}p) which represents the ratio of the thrust over the propellant consumption rate. If the average exhaust H{sub 2} temperature of a NTR is around 3,000 K, the I{sub s}p can be achieved as high as 1,000 s as compared with only 450 - 500 s of the best CRs. For this reason, NTRs are favored for various space applications such as orbital tugs, lunar transports, and manned missions to Mars and beyond. The best known NTR development effort was conducted from 1955 to1974 under the ROVER and NERVA programs in the USA. These programs had successfully designed and tested many different reactors and engines. After these projects, the researches on NERVA derived

INIS as an information and knowledge resource for advanced nuclear technology studies

International Nuclear Information System (INIS)

Rashkova, N.

2009-01-01

INIS is, at present, the leading reference database for scientific literature on the peaceful uses of nuclear science and technology. It operates at the IAEA - INIS and NKM Section and coordinates nuclear information management activities: maintains INIS database and the access to the database, prepares the IAEA input; controls the input from the Member States and assists them in establishing information centers and exchanging nuclear information. The INIS DB covers all types of literature, published worldwide: journal articles, conference proceedings, legal documents, scientific and technical documents etc. The non-conventional collection (NCL) contains more than 200 000 full text documents. INIS provides free access to the bibliographic database for registered users and other information resources, such as database on CD-ROM, topical CDs, full text database, links to other databases, web pages, authority list etc. INIS database offers structured and easy searchable information. The information is grouped in subject categories, under the INIS-ETDE subject classification scheme, which is periodically updated to reflect the new developments in the specific area. The main INIS areas are: nuclear physics, reactor physics and engineering, material science, nuclear fuels, plasma physics and fusion technology, particle accelerators radiation protection, nuclear medicine. The database grows rapidly - currently contains over 3 million records. The material science, reactor design and engineering, new reactor technologies and plasma applications are among the most rapidly growing subject categories. INIS database offers different search options, depending on the needs of the user: simple search; advanced search in abstract, author, place and date of publication, source, document type, subject, descriptors etc.; search by descriptors and predefined queries; combining queries by logical operators. The export from the database is available in html, text, formatted text; XML

Nuclear engineering enrollments and degrees, 1981

International Nuclear Information System (INIS)

Little, J.R.; Shirley, D.L.

1982-05-01

This report presents data on the number of students enrolled and the degrees awarded in academic year 1980-81 from 73 US institutions offering degree programs in nuclear engineering or nuclear options within other engineering fields. Presented here are historical data for the last decade, which provide information such as trends by degree level, foreign national student participation, female and minority student participation, and placement of graduates. Also included is a listing of the universities by type of program and number of students

Study of advanced rotary combustion engines for commuter aircraft

Science.gov (United States)

Berkowitz, M.; Jones, C.; Myers, D.

1983-01-01

Performance, weight, size, and maintenance data for advanced rotary aircraft engines suitable for comparative commuter aircraft system evaluation studies of alternate engine candidates are provided. These are turbocharged, turbocompounded, direct injected, stratified charge rotary engines. Hypothetical engines were defined (an RC4-74 at 895 kW and an RC6-87 at 1490 kW) based on the technologies and design approaches used in the highly advanced engine of a study of advanced general aviation rotary engines. The data covers the size range of shaft power from 597 kW (800 hp) to 1865 kW (2500 hp) and is in the form of drawings, tables, curves and written text. These include data on internal geometry and configuration, installation information, turbocharging and turbocompounding arrangements, design features and technologies, engine cooling, fuels, scaling for weight size BSFC and heat rejection for varying horsepower, engine operating and performance data, and TBO and maintenance requirements. The basic combustion system was developed and demonstrated; however the projected power densities and performance efficiencies require increases in engine internal pressures, thermal loading, and rotative speed.

Training of engineers for Czechoslovak nuclear programme at Czech Technical University in Prague

International Nuclear Information System (INIS)

Klik, F.; Stoll, I.

1983-01-01

Between the year 1959 and the 1970's specialists for the Czechoslovak nuclear programme were only educated at the Faculty of Nuclar and Physics Engineering. In the early 1970's instruction and research related to nuclear power generation was introduced at the mechanical engineering and electrical engineering faculties. The specialization ''Nuclear power facilities'' was introduced within the study field ''Thermal and nuclear machines and equipment'' at the mechanical engineering faculty, and the electrical engineering faculty opened the study course ''Nuclear power plants'' in the study year 1975/1976. Most specialists for the nuclear programme are educated at the Faculty of Nuclear and Physics Engineering in the field ''Nuclear chemical engineering'' and in specializations ''Theory and technology of nuclear reactors'', ''Dosimetry and application of ionizing radiation'' in the study field ''Nuclear engineering''. The Faculty of Nuclear and Physics Engineering also trains specialists in the field ''Structure and materials properties'', the study courses ''Measuring technology'' and ''Control technology'' are run at the electrical engineering faculty and at the mechanical engineering faculty were introduced study courses of ''Applied mechanics'' and ''Mechanical engineering technology''. Graduates of all said study courses may be employed in the nuclear programme. (E.S.)

Experience with performance based training of nuclear criticality safety engineers

International Nuclear Information System (INIS)

Taylor, R.G.

1993-01-01

For non-reactor nuclear facilities, the U.S. Department of Energy (DOE) does not require that nuclear criticality safety engineers demonstrate qualification for their job. It is likely, however, that more formalism will be required in the future. Current DOE requirements for those positions which do have to demonstrate qualification indicate that qualification should be achieved by using a systematic approach such as performance based training (PBT). Assuming that PBT would be an acceptable mechanism for nuclear criticality safety engineer training in a more formal environment, a site-specific analysis of the nuclear criticality safety engineer job was performed. Based on this analysis, classes are being developed and delivered to a target audience of newer nuclear criticality safety engineers. Because current interest is in developing training for selected aspects of the nuclear criticality safety engineer job, the analysis is incompletely developed in some areas

Nuclear engineering education in the United States

International Nuclear Information System (INIS)

Williamson, T.G.

1982-01-01

In discussing nuclear engineering education in the United States it is shown that the most critical issue facing the nuclear engineering education community today is enrolment in a time of increasing demand for graduate engineers. Related to the issue of enrolment is support for graduate students, whether it be fellowships, traineeships, or research assistantships. Other issues are those of maintaining a vital faculty in the face of a competitive job market, of maintaining research facilities and developing new ones, and of determining the directions of educational efforts in the future. (U.K.)

Research on application of knowledge engineering to nuclear power stations

International Nuclear Information System (INIS)

Umeda, Takeo; Kiyohashi, Satoshi

1990-01-01

Recently, the research on the software and hardware regarding knowledge engineering has been advanced eagerly. Especially the applicability of expert systems is high. When expert systems are introduced into nuclear power stations, it is necessary to make the plan for introduction based on the detailed knowledge on the works in nuclear power stations, and to improve the system repeatedly by adopting the opinion and request of those in charge upon the trial use. Tohoku Electric Power Co. was able to develop the expert system of practically usable scale 'Supporting system for deciding fuel movement procedure'. The survey and analysis of the works in nuclear power stations, the selection of the system to be developed and so on are reported. In No. 1 plant of Onagawa Nuclear Power Station of BWR type, up to 1/3 of the fuel is replaced at the time of the regular inspection. Some fuel must be taken to outside for ensuring the working space. The works of deciding fuel movement procedure, the development of the system and its evaluation are described. (K.I.)

Advances in nuclear fuel technology. 3. Development of advanced nuclear fuel recycle systems

International Nuclear Information System (INIS)

Arie, Kazuo; Abe, Tomoyuki; Arai, Yasuo

2002-01-01

Fast breeder reactor (FBR) cycle technology has a technical characteristics flexibly easy to apply to diverse fuel compositions such as plutonium, minor actinides, and so on and fuel configurations. By using this characteristics, various feasibilities on effective application of uranium resources based on breeding of uranium of plutonium for original mission of FBR, contribution to radioactive wastes problems based on amounts reduction of transuranium elements (TRU) in high level radioactive wastes, upgrading of nuclear diffusion resistance, extremely upgrading of economical efficiency, and so on. In this paper, were introduced from these viewpoints, on practice strategy survey study on FBR cycle performed by cooperation of the Japan Nuclear Cycle Development Institute (JNC) with electric business companies and so on, and on technical development on advanced nuclear fuel recycle systems carried out at the Central Research Institute of Electric Power Industry, Japan Atomic Energy Research Institute, and so on. Here were explained under a vision on new type of fuels such as nitride fuels, metal fuels, and so on as well as oxide fuels, a new recycle system making possible to use actinides except uranium and plutonium, an 'advanced nuclear fuel cycle technology', containing improvement of conventional wet Purex method reprocessing technology, fuel manufacturing technology, and so on. (G.K.)

Social engineering awareness in Nuclear Malaysia

International Nuclear Information System (INIS)

Mohd Dzul Aiman bin Aslan; Mohamad Safuan bin Sulaiman; Abdul Muin bin Abdul Rahman

2010-01-01

Social engineering is the best tools to infiltrate an organization weakness. It can go bypass the best fire wall or Intrusion Detection System (IDS) the organization ever had, effectively. Nuclear Malaysia staffs should aware of this technique as information protection it is not only depends on paper and computer. This paper consist a few test cases including e mail, dump ster diving, phishing, malicious web content, and impersonation to acknowledge all Nuclear Malaysia staffs about the method, effect and prevention of social engineering. (author)

Targeted initiatives. Support for nuclear engineering education in the USA

International Nuclear Information System (INIS)

Gutteridge, John

2001-01-01

Recruitment and education of a new generation of nuclear engineers stands to benefit in the USA from a range of programmes involving governmental bodies, universities, and industry groups. They are part of efforts to attract more students to consider and prepare for careers in the nuclear industry, and to provide financial support for nuclear research and education. Career prospects in the nuclear field are brightening. The demand for nuclear engineers and nuclear trained personnel is on the rise as the new century opens. During the past year several studies were completed in an attempt to ascertain the problems in nuclear engineering education and define initiatives to address these problems

Design of compact nuclear power marine engineering simulator

International Nuclear Information System (INIS)

Gao Jinghui; Xing Hongchuan; Zhang Ronghua; Yang Yanhua; Xu Jijun

2004-01-01

The essentiality of compact nuclear power marine engineering simulator (NPMES) is discussed. The technology of nuclear power plant engineering simulator (NPPES) for NPMES development is introduced, and the function design, general design and model design are given in details. A compact NPMES based on the nuclear power marine of 'Mutsu' is developed. The design can help the development of NPMES, which will improve operation safety and management efficiency of marine. (authors)

Development of Advanced Small Hydrogen Engines

Energy Technology Data Exchange (ETDEWEB)

Sapru, Krishna; Tan, Zhaosheng; Chao, Ben

2010-09-30

The main objective of the project is to develop advanced, low cost conversions of small (< 25 hp) gasoline internal combustion engines (ICEs) to run on hydrogen fuel while maintaining the same performance and durability. This final technical report summarizes the results of i) the details of the conversion of several small gasoline ICEs to run on hydrogen, ii) the durability test of a converted hydrogen engine and iii) the demonstration of a prototype bundled canister solid hydrogen storage system. Peak power of the hydrogen engine achieves 60% of the power output of the gasoline counterpart. The efforts to boost the engine power with various options including installing the over-sized turbocharger, retrofit of custom-made pistons with high compression ratio, an advanced ignition system, and various types of fuel injection systems are not realized. A converted Honda GC160 engine with ACS system to run with hydrogen fuel is successful. Total accumulative runtime is 785 hours. A prototype bundled canister solid hydrogen storage system having nominal capacity of 1.2 kg is designed, constructed and demonstrated. It is capable of supporting a wide range of output load of a hydrogen generator.

Advanced Gasoline Turbocharged Direction Injection (GTDI) Engine Development

Energy Technology Data Exchange (ETDEWEB)

Wagner, Terrance [Ford Motor Co., Dearborn, MI (United States)

2015-12-31

This program was undertaken in response to US Department of Energy Solicitation DE-FOA-0000079, resulting in a cooperative agreement with Ford and MTU to demonstrate improvement of fuel efficiency in a vehicle equipped with an advanced GTDI engine. Ford Motor Company has invested significantly in GTDI engine technology as a cost effective, high volume, fuel economy solution, marketed globally as EcoBoost technology. Ford envisions additional fuel economy improvement in the medium and long term by further advancing EcoBoost technology. The approach for the project was to engineer a comprehensive suite of gasoline engine systems technologies to achieve the project objectives, and to progressively demonstrate the objectives via concept analysis / computer modeling, single-cylinder and multi-cylinder engine testing on engine dynamometer, and vehicle level testing on chassis rolls.

Advanced computational approaches to biomedical engineering

CERN Document Server

Saha, Punam K; Basu, Subhadip

2014-01-01

There has been rapid growth in biomedical engineering in recent decades, given advancements in medical imaging and physiological modelling and sensing systems, coupled with immense growth in computational and network technology, analytic approaches, visualization and virtual-reality, man-machine interaction and automation. Biomedical engineering involves applying engineering principles to the medical and biological sciences and it comprises several topics including biomedicine, medical imaging, physiological modelling and sensing, instrumentation, real-time systems, automation and control, sig

MITI project on advanced man-machine system for nuclear power plants

International Nuclear Information System (INIS)

Kato, Kanji; Watanabe, Takao; Hayakawa, Hiroyasu; Naito, Norio; Masui, Takao; Ogino, Takamichi.

1988-01-01

A computerized operator support system (COSS) against abnormal plant conditions was developed as a five-year project from 1980 to 1984, under the sponsorship of the Ministry of International Trade and Industry. The main purpose of the COSS development was to implement the lessons learned from the Three Mile Island accident. The main nuclear industries in Japan participated in the project. The design concept of the operator support functions and the method to implement it were established, and the prototype systems of the COSS for BWR and PWR plants were developed. After the completion of the COSS development, the above participant group once again joined for the work on an advanced man-machine system for nuclear power plants (MMS-NPP). This eight-year project aims at realizing an advanced operator support system by applying artificial intelligence, especially knowledge engineering, and sophisticated man-machine interface devices. Its main objectives are shown. This system configuration, operating method decision system, man-machine communication system, operation and maintenance support functions and so on are described. (Kako, I.)

Software engineers and nuclear engineers: teaming up to do testing

International Nuclear Information System (INIS)

Kelly, D.; Cote, N.; Shepard, T.

2007-01-01

The software engineering community has traditionally paid little attention to the specific needs of engineers and scientists who develop their own software. Recently there has been increased recognition that specific software engineering techniques need to be found for this group of developers. In this case study, a software engineering group teamed with a nuclear engineering group to develop a software testing strategy. This work examines the types of testing that proved to be useful and examines what each discipline brings to the table to improve the quality of the software product. (author)

Enterprise SRS: Leveraging Ongoing Operations To Advance Nuclear Fuel Cycles Research And Development Programs

International Nuclear Information System (INIS)

Murray, Alice M.; Marra, John E.; Wilmarth, William R.; Mcguire, Patrick W.; Wheeler, Vickie B.

2013-01-01

The Savannah River Site (SRS) is repurposing its vast array of assets to solve future national issues regarding environmental stewardship, national security, and clean energy. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for ''all things nuclear'' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into facilities in conjunction with on-going missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, The Department of Energy, Savannah River Operations Office, Savannah River Nuclear Solutions, the Savannah River National Laboratory (SRNL) have established a center for applied nuclear materials processing and engineering research (hereafter referred to as the Center). The key proposition of this initiative is to bridge the gap between promising transformational nuclear fuel cycle processing discoveries and large commercial-scale-technology deployment by leveraging SRS assets as facilities for those critical engineering-scale demonstrations necessary to assure the successful deployment of new technologies. The Center will coordinate the demonstration of R&D technologies and serve as the interface between the engineering-scale demonstration and the R&D programs, essentially providing cradle-to-grave support to the research team during the demonstration. While the initial focus of the Center will be on the effective use of SRS assets for these demonstrations, the Center also will work with research teams to identify opportunities to perform research demonstrations at other facilities. Unique to this approach is the fact that these SRS

Using gasoline in an advanced compression ignition engine

Energy Technology Data Exchange (ETDEWEB)

Cracknell, R.F.; Ariztegui, J.; Dubois, T.; Hamje, H.D.C.; Pellegrini, L.; Rickeard, D.J.; Rose, K.D. [CONCAWE, Brussels (Belgium); Heuser, B. [RWTH Aachen Univ. (Germany). Inst. for Combustion Engines; Schnorbus, T.; Kolbeck, A.F. [FEV GmbH, Aachen (Germany)

2013-06-01

Future vehicles will be required to improve their efficiency, reduce both regulated and CO{sub 2} emissions, and maintain acceptable driveability, safety, and noise. To achieve this overall performance, they will be configured with more advanced hardware, sensors, and control technologies that will also enable their operation on a broader range of fuel properties. Fuel flexibility has already been demonstrated in previous studies on a compression ignition bench engine and a demonstration vehicle equipped with an advanced engine management system, closed-loop combustion control, and air-path control strategies. An unresolved question is whether engines of this sort can also operate on market gasoline while achieving diesel-like efficiency and acceptable emissions and noise levels. In this study, a compression ignition bench engine having a higher compression ratio, optimised valve timing, advanced engine management system, and flexible fuel injection could be operated on a European gasoline over full to medium part loads. The combustion was sensitive to EGR rates, however, and optimising all emissions and combustion noise was a considerable challenge at lower loads. (orig.)

Midwest Nuclear Science and Engineering Consortium

International Nuclear Information System (INIS)

Volkert, Wynn; Kumar, Arvind; Becker, Bryan; Schwinke, Victor; Gonzalez, Angel; McGregor, Douglas

2010-01-01

The objective of the Midwest Nuclear Science and Engineering Consortium (MNSEC) is to enhance the scope, quality and integration of educational and research capabilities of nuclear sciences and engineering (NS/E) programs at partner schools in support of the U.S. nuclear industry (including DOE laboratories). With INIE support, MNSEC had a productive seven years and made impressive progress in achieving these goals. Since the past three years have been no-cost-extension periods, limited -- but notable -- progress has been made in FY10. Existing programs continue to be strengthened and broadened at Consortium partner institutions. The enthusiasm generated by the academic, state, federal, and industrial communities for the MNSEC activities is reflected in the significant leveraging that has occurred for our programs.

Midwest Nuclear Science and Engineering Consortium

Energy Technology Data Exchange (ETDEWEB)

Dr. Wynn Volkert; Dr. Arvind Kumar; Dr. Bryan Becker; Dr. Victor Schwinke; Dr. Angel Gonzalez; Dr. DOuglas McGregor

2010-12-08

The objective of the Midwest Nuclear Science and Engineering Consortium (MNSEC) is to enhance the scope, quality and integration of educational and research capabilities of nuclear sciences and engineering (NS/E) programs at partner schools in support of the U.S. nuclear industry (including DOE laboratories). With INIE support, MNSEC had a productive seven years and made impressive progress in achieving these goals. Since the past three years have been no-cost-extension periods, limited -- but notable -- progress has been made in FY10. Existing programs continue to be strengthened and broadened at Consortium partner institutions. The enthusiasm generated by the academic, state, federal, and industrial communities for the MNSEC activities is reflected in the significant leveraging that has occurred for our programs.

Nuclear engineering. Stable industry for bright minds

International Nuclear Information System (INIS)

Geisler, Maja

2009-01-01

The Deutsches Atomforum (DAtF) invited 35 students and graduate students for 'colloquies for professional orientation' to Luenen on March 8-11, 2009. Another 39 students were guests in Speyer between March 15 and 18 this year. Participants included graduates in physics, chemistry, radiation protection, and mechanical engineering as well as students of process engineering, electrical engineering and environmental technology. The colloquies for professional orientation are a service provided by the Informationskreis Kernenergie (IK) to member firms of DAtF. At the same time, the IK in this way fulfils its duty to promote young scientists and engineers within the framework of the DAtF's basic public relations activities. After all, nuclear technology in Germany is not about to end its life. Firms with international activities are in urgent need of highly qualified young staff members. Personnel is needed for a variety of activities ranging from nuclear power plant construction to fuel fabrication to waste management and the demolition and disposal of nuclear power plants. All these areas are in need of new qualified staff. Some 750 students so far have attended the DAtF colloquies for professional orientation since 2002. Many participants were hired by industries straight away or were given opportunities as trainees or students preparing their diploma theses in the nuclear industry. These contacts with the nuclear industry should not remain a one-off experience for the students. For this reason, the IK invites the participants in colloquies again this year to attend the Annual Meeting on Nuclear Technology in Dresden on May 12-14, 2009. (orig.)

Supplement 1: Advanced nuclear turbojet powerplant characteristics summary for supersonic aircraft

International Nuclear Information System (INIS)

Larson, John W.

1959-01-01

The powerplant characteristics previously described in PWAC-275 were based on the use of low compressor pressure ratio nuclear turbojet engines equipped with interburners but without afterburners. The performance of an afterburning version of the same engine is presented in Section B of this supplement. The engine selection for the previous report and for Section B of this supplement was based on best engine performance at Mach No. 3 on nuclear heat alone. For this reason a low compression turbojet engine was selected. However, it is desirable that the nuclear data in report PWAC-275 be useful for both subsonic and supersonic missions. Therefore, the engine performance has been computed for a nuclear conversion of the Pratt & Whitney Aircraft J-58 turbojet engine which has a higher compressor pressure ratio. The performance of this engine is outlined in Section C of this supplement.

Expertise preservation in nuclear technology - the new master course ''nuclear safety engineering'' at the RWTH Aachen

International Nuclear Information System (INIS)

Backus, Sabine; Heuters, Michael

2011-01-01

The energy concept of the German federal Government in 2010 emphasizes the importance of nuclear energy within the energy policy. The lifetime extension of German nuclear power plants and the long-term safety of radioactive waste storage is the new challenge with respect to the expertise preservation in Germany. The owners of nuclear utilities have started to assist new research programs in the field of nuclear engineering at the German universities. RWE Power and ThyssenKrupp have signed a cooperation contract in 2007 with the RWTH Aachen. The companies bear the expenses for professorships ''nuclear fuel cycle'', ''simulation in nuclear engineering'' and ''reactor safety and engineering''. An elongation of the contract is planned. A master course ''nuclear safety engineering'' over 4 semesters covers the complete fuel cycle. The authors discuss issues concerning the information of students, experiences with the expectations of students concerning their future employment, acceptance of nuclear energy and related topics.

IEEE [Institute of Electrical and Electronics Engineers] standards and nuclear software quality engineering

International Nuclear Information System (INIS)

Daughtrey, T.

1988-01-01

Significant new nuclear-specific software standards have recently been adopted under the sponsorship of the American Nuclear Society and the American Society of Mechanical Engineers. The interest of the US Nuclear Regulatory Commission has also been expressed through their issuance of NUREG/CR-4640. These efforts all indicate a growing awareness of the need for thorough, referenceable expressions of the way to build in and evaluate quality in nuclear software. A broader professional perspective can be seen in the growing number of software engineering standards sponsored by the Institute of Electrical and Electronics Engineers (IEEE) Computer Society. This family of standards represents a systematic effort to capture professional consensus on quality practices throughout the software development life cycle. The only omission-the implementation phase-is treated by accepted American National Standards Institute or de facto standards for programming languages

Radiological Engineering: A graduate engineering - based curriculum for radiation protection

International Nuclear Information System (INIS)

Kearfott, K.J.; Wepfer, W.J.

1994-01-01

Several U.S. universities maintain formal graduate health physics curricula within their Colleges of Engineering. The term radiological engineering was coined to describe the discipline of applying engineering principles to the radiation protection aspects of nuclear technology. Radiological engineering programmes may require a specific core group of courses such as radiation biology, radiation protection practice, nuclear physics, radiation detectors, and radiation dosimetry. Students then might specialist in environmental, nuclear facilities or medical applications areas by selecting advanced courses and graduate design or research projects. In some instances the master's degree may be completed through remotely-delivered lectures. Such programmes promise to assist in educating a new group of engineering professionals dedicated to the safe utilisation of nuclear technology. The Georgis Institute of Technology's programme will serve as the specific example for this report. 8 refs., 1 fig

Conceptual Engine System Design for NERVA derived 66.7KN and 111.2KN Thrust Nuclear Thermal Rockets

International Nuclear Information System (INIS)

Fittje, James E.; Buehrle, Robert J.

2006-01-01

The Nuclear Thermal Rocket concept is being evaluated as an advanced propulsion concept for missions to the moon and Mars. A tremendous effort was undertaken during the 1960's and 1970's to develop and test NERVA derived Nuclear Thermal Rockets in the 111.2 KN to 1112 KN pound thrust class. NASA GRC is leveraging this past NTR investment in their vehicle concepts and mission analysis studies, and has been evaluating NERVA derived engines in the 66.7 KN to the 111.2 KN thrust range. The liquid hydrogen propellant feed system, including the turbopumps, is an essential component of the overall operation of this system. The NASA GRC team is evaluating numerous propellant feed system designs with both single and twin turbopumps. The Nuclear Engine System Simulation code is being exercised to analyze thermodynamic cycle points for these selected concepts. This paper will present propellant feed system concepts and the corresponding thermodynamic cycle points for 66.7 KN and 111.2 KN thrust NTR engine systems. A pump out condition for a twin turbopump concept will also be evaluated, and the NESS code will be assessed against the Small Nuclear Rocket Engine preliminary thermodynamic data

IMPULSE---an advanced, high performance nuclear thermal propulsion system

International Nuclear Information System (INIS)

Petrosky, L.J.; Disney, R.K.; Mangus, J.D.; Gunn, S.A.; Zweig, H.R.

1993-01-01

IMPULSE is an advanced nuclear propulsion engine for future space missions based on a novel conical fuel. Fuel assemblies are formed by stacking a series of truncated (U, Zr)C cones with non-fueled lips. Hydrogen flows radially inward between the cones to a central plenum connected to a high performance bell nozzle. The reference IMPULSE engine rated at 75,000 lb thrust and 1800 MWt weighs 1360 kg and is 3.65 meters in height and 81 cm in diameter. Specific impulse is estimated to be 1000 for a 15 minute life at full power. If longer life times are required, the operating temperature can be reduced with a concomitant decrease in specific impulse. Advantages of this concept include: well defined coolant paths without outlet flow restrictions; redundant orificing; very low thermal gradients and hence, thermal stresses, across the fuel elements; and reduced thermal stresses because of the truncated conical shape of the fuel elements

NUKEM. Innovative solutions for nuclear engineering

International Nuclear Information System (INIS)

Scheffler, Beate

2011-01-01

Management of radioactive waste, handling spent fuel elements, decommissioning of nuclear facilities, and engineering and consulting activities are services associated with the name of NUKEM all over the world. The company's scientists and engineers develop solution concepts combining the latest technologies with proven techniques and many years of experience. The company;s history and the services offered to the nuclear industry began more than 5 decades ago. The predecessor, NUKEM Nuklear-Chemie-Metallurgie, was founded in 1960 as one of the earliest nuclear companies in Germany. Originally, the firm produced fuel elements for a variety of reactor lines. As early as in the 1970s, logical extensions of these business activities were nuclear engineering and plant construction. In the meantime, NUKEM Technologies GmbH has developed a worldwide reputation for its activities. Numerous reference projects bear witness to optimum project management and customer satisfaction. Since 2009, NUKEM Technologies has been a wholly owned subsidiary of the Russian Atomstroyexport. NUKEM Technologies operates sales and project offices outside Germany, e.g. in Russia, China, Lithuania, France, and Bulgaria. In this way, the company is present in its target markets of Russia, Western and Eastern Europe as well as Asia, offering customers and partners fast and direct contacts. (orig.)

Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems

International Nuclear Information System (INIS)

2007-01-01

In keeping with the 12-year history of this conference, GLOBAL 2007 focuses on future nuclear energy systems and fuel cycles. With the increasing public acceptance and political endorsement of nuclear energy, it is a pivotal time for nuclear energy research. Significant advances have been made in development of advanced nuclear fuels and materials, reactor designs, partitioning, transmutation and reprocessing technologies, and waste management strategies. In concert with the technological advances, it is more important than ever to develop sensible nuclear proliferation policies, to promote sustainability, and to continue to increase international collaboration. To further these aims, GLOBAL 2007 highlights recent developments in the following areas: advanced integrated fuel cycle concepts, spent nuclear fuel reprocessing, advanced reprocessing technology, advanced fuels and materials, advanced waste management technology, novel concepts for waste disposal and repository development, advanced reactors, partitioning and transmutation, developments in nuclear non-proliferation technology, policy, and implementation, sustainability and expanded global utilization of nuclear energy, and international collaboration on nuclear energy

A new undergraduate course: Problems in nuclear engineering

International Nuclear Information System (INIS)

Larsen, Edward W.

2011-01-01

During the past five years, a new third-year undergraduate nuclear engineering course has been developed and taught at the University of Michigan. The course was created to correct certain deficiencies in the undergraduate nuclear engineering curriculum. Here we discuss the origins of the new course and our experience with it. (author)

Certain aspects of the environmental impact of nuclear power engineering and thermal power engineering

Energy Technology Data Exchange (ETDEWEB)

Malenchenko, A F [AN Belorusskoj SSR, Minsk. Inst. Yadernoj Ehnergetiki

1979-01-01

A review is made of the both environmental impact and hazard to man resulting from nuclear power engineering as compared with those of thermal power engineering. At present, in addition to such criteria, as physical-chemical characteristic of energy sources, their efficiency and accessibility for exploitation, new requirements were substantiated in relation to safety of their utilization for environment. So, one of essential problems of nuclear power engineering development consists in assessment and prediction of radioecological consequence. The analysis and operating experience of more than 1000 reactor/years with no accidents and harm for pupulation show, that in respect to impact on environment and man nuclear power engineering is much more safe in comparison with energy sources using tradidional fossile fuel.

Labor market trends for nuclear engineers through 2000

International Nuclear Information System (INIS)

Seltzer, N.; Blair, L.M.; Baker, J.G.

1995-01-01

Throughout most of the 1980s, both private organizations and government agencies were concerned about the availability of an adequate supply of qualified nuclear engineers. This concern was primarily the result of a number of nuclear engineering academic programs being eliminated coupled with a continuous decline in graduate and undergraduate enrollments and degrees. By the early 1990s, the number of degrees and available supply had declined to new lows, but cutbacks in funding for the nuclear weapons program and nuclear energy R ampersand D, and in hiring by the electric utility industry, offset in large measure the declining supply. Recently, concerns about environment and waste management and about nuclear safety have again generated questions about the adequacy of supply of qualified personnel for nuclear energy activities. This report briefly examines the nuclear engineering labor market. Trends in employment, new graduates, job openings, and salaries are reviewed as a basis for understanding the current labor market. This review is then used as a basis for assessing future employment needs and new graduate supply to provide an outlook for future labor market conditions through 2000

Developing Curriculum of Nuclear Civil Engineering Degree Programme at Graduate Level

International Nuclear Information System (INIS)

Iqbal, J.

2016-01-01

Full text: The paper suggests the introduction of a new degree, namely nuclear civil engineering at graduate level for better utilization of civil engineers in nuclear power plant (NPP) design and construction. At present, both nuclear engineering and civil engineering degrees are offered at undergraduate and graduate levels in numerous renowned universities of the world. However, when a civil engineer, even after completion of nuclear engineering at postgraduate level, undertakes an assignment related to NPP design, he comes across various problems which are not covered in the present curricula. For instance, NPPs’ siting issues, design of pre-stressed concrete containment against loads of loss of coolant accident (LOCA), various impulsive and impactive loads (e.g., detonations, aircraft crash analysis, etc.) and shielding calculations are some of the core issues during nuclear power plant design. The paper highlights the importance of introduction of nuclear civil engineering degree at the graduate level. Besides, the contents of the proposed course work have also been discussed. Keeping in view the fact that, currently, no such degree is offered in any university of the world, the paper explores useful avenues to human resource development for introducing and expanding nuclear power programmes. (author

Status of nuclear engineering education in the United States

International Nuclear Information System (INIS)

Brown, G.J.

2000-01-01

Nuclear engineering education in the United States is reflective of the perceived health of the nuclear electric power industry within the country. Just as new commercial reactor orders have vanished and some power plants have shut down, so too have university enrollments shrunk and research reactors closed. This decline in nuclear trained specialists and the disappearance of the nuclear infrastructure is a trend that must be arrested and reversed if the United States is to have a workforce capable of caring for a nuclear power industry to not only meet future electric demand but to ensure that the over 100 existing plants, their supporting facilities and their legacy in the form of high level waste and facility clean-up are addressed. Additionally, the United States has an obligation to support and maintain its nuclear navy and other defence needs. And, lastly, if the United States is to have a meaningful role in the international use of nuclear power with regard to safety, non-proliferation and the environment, then it is imperative that the country continues to produce world-class nuclear engineers and scientists by supporting nuclear engineering education at its universities. The continued support of the federal government. and industry for university nuclear engineering and nuclear energy research and development is essential to sustain the nuclear infrastructure in the United States. Even with this support, and the continued excellent operation of the existing fleet of nuclear electric power plants, it is conceivable that nuclear engineering as an academic discipline may fall victim to poor communications and a tarnished public image. What is needed is a combination of federal and industrial support along with the creativity of the universities to expand their offerings to include more than power production. The objective is a positive message on careers in nuclear related fields, and recognition of the important role of nuclear energy in meeting the country

Advanced nonlinear engine speed control systems

DEFF Research Database (Denmark)

Vesterholm, Thomas; Hendricks, Elbert

1994-01-01

Several subsidiary control problems have turned out to be important for improving driveability and fuel consumption in modern spark ignition (SI) engine cars. Among these are idle speed control and cruise control. In this paper the idle speed and cruise control problems will be treated as one......: accurately tracking of a desired engine speed in the presence of model uncertainties and severe load disturbances. This is accomplished by using advanced nonlinear control techniques such as input/output-linearization and sliding mode control. These techniques take advantage of a nonlinear model...... of the engine dynamics, a mean value engine model....

Nuclear industry prepares fore shortage of engineers

International Nuclear Information System (INIS)

Gauker, Lynn.

1991-01-01

It is predicted that the Canadian nuclear industry will experience a shortage of qualified personnel within the next five to ten years. The reasons for this prediction are as follows: enrollment in engineering courses, particularly five courses in nuclear engineering has been declining; immigration can no longer be expected to fill the gap; the workforce is aging. Solutions may include promotional campaigns, student employment programs, and educating workers to a professional level

Advances in communication systems and electrical engineering

CERN Document Server

Huang, Xu

2008-01-01

This volume contains contributions from participants in the 2007 International Multiconference of Engineers and Computer Scientists Topics covered include communications theory, communications protocols, network management, wireless networks, telecommunication, electronics, power engineering, control engineering, signal processing, and industrial applications. The book will offer the states of arts of tremendous advances in communication systems and electrical engineering and also serve as an excellent reference work for researchers and graduate students working with/on communication systems a

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1962-01-01

Advances in Nuclear Science and Technology, Volume 1 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book covers a variety of topics, including nuclear power stations, graft polymerization, diffusion in uranium alloys, and conventional power plants.Organized into seven chapters, this volume begins with an overview of the three stages of the operation of a power plant, either nuclear or conventionally fueled. This text then examines the major problems that face the successful development of commercial nuclear power plants. Other chapters consider

Nuclear engineering education: A competence based approach to curricula development

International Nuclear Information System (INIS)

2014-01-01

Maintaining nuclear competencies in the nuclear industry is a one of the most critical challenges in the near future. With the development of a number of nuclear engineering educational programmes in several States, this publication provides guidance to decision makers in Member States on a competence based approach to curricula development, presenting the established practices and associated requirements for educational programmes in this field. It is a consolidation of best practices that will ensure sustainable, effective nuclear engineering programmes, contributing to the safe, efficient and economic operation of nuclear power plants. The information presented is drawn from a variety of recognized nuclear engineering programmes around the world and contributes to the main areas that are needed to ensure a viable and robust nuclear industry

Advanced nuclear plant design options to cope with external events

International Nuclear Information System (INIS)

2006-02-01

With the stagnation period of nuclear power apparently coming to an end, there is a renewed interest in many Member States in the development and application of nuclear power plants (NPPs) with advanced reactors. Decisions on the construction of several NPPs with evolutionary light water reactors have been made (e.g. EPR Finland for Finland and France) and more are under consideration. There is a noticeable progress in the development and demonstration of innovative high temperature gas cooled reactors, for example, in China, South Africa and Japan. The Generation IV International Forum has defined the International Near Term Deployment programme and, for a more distant perspective, six innovative nuclear energy systems have been selected and certain R and D started by several participating countries. National efforts on design and technology development for NPPs with advanced reactors, both evolutionary and innovative, are ongoing in many Member States. Advanced NPPs have an opportunity to be built at many sites around the world, with very broad siting conditions. There are special concerns that safety of these advanced reactors may be challenged by external events following new scenarios and failure modes, different from those well known for the currently operated reactors. Therefore, the engineering community identified the need to assess the proposed design configurations in relation to external scenarios at the earliest stages of the design development. It appears that an early design optimization in relation to external events is a necessary requirement to achieve safe and economical advanced nuclear power plants. Reflecting on these developments, the IAEA has planned the preparation of a report to define design options for protection from external event impacts in NPPs with evolutionary and innovative reactors. The objective of this publication is to present the state-of-the-art in design approaches for the protection of NPPs with evolutionary and innovative

Advanced structural wind engineering

CERN Document Server

Kareem, Ahsan

2013-01-01

This book serves as a textbook for advanced courses as it introduces state-of-the-art information and the latest research results on diverse problems in the structural wind engineering field. The topics include wind climates, design wind speed estimation, bluff body aerodynamics and applications, wind-induced building responses, wind, gust factor approach, wind loads on components and cladding, debris impacts, wind loading codes and standards, computational tools and computational fluid dynamics techniques, habitability to building vibrations, damping in buildings, and suppression of wind-induced vibrations. Graduate students and expert engineers will find the book especially interesting and relevant to their research and work.

New perspectives for advanced automobile diesel engines

Science.gov (United States)

Tozzi, L.; Sekar, R.; Kamo, R.; Wood, J. C.

1983-01-01

Computer simulation results are presented for advanced automobile diesel engine performance. Four critical factors for performance enhancement were identified: (1) part load preheating and exhaust gas energy recovery, (2) fast heat release combustion process, (3) reduction in friction, and (4) air handling system efficiency. Four different technology levels were considered in the analysis. Simulation results are compared in terms of brake specific fuel consumption and vehicle fuel economy in km/liter (miles per gallon). Major critical performance sensitivity areas are: (1) combustion process, (2) expander and compressor efficiency, and (3) part load preheating and compound system. When compared to the state of the art direct injection, cooled, automobile diesel engine, the advanced adiabatic compound engine concept showed the unique potential of doubling the fuel economy. Other important performance criteria such as acceleration, emissions, reliability, durability and multifuel capability are comparable to or better than current passenger car diesel engines.

Space Nuclear Reactor Engineering

Energy Technology Data Exchange (ETDEWEB)

Poston, David Irvin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-03-06

We needed to find a space reactor concept that could be attractive to NASA for flight and proven with a rapid turnaround, low-cost nuclear test. Heat-pipe-cooled reactors coupled to Stirling engines long identified as the easiest path to near-term, low-cost concept.

The mathematics of nuclear engineering

International Nuclear Information System (INIS)

Lewins, J.D.

1982-01-01

The mathematics of nuclear engineering is considered with especial reference to the problems of; the representation of the transformation of matter at the nuclear level by radioactive decay and neutron transmutation, the problem of the distribution of neutrons and other particles as a transport theory problem including some of the approximation methods used in this problem, particularly diffusion theory with particular emphasis on steady-state problems, time-dependent reactor kinetic and control, and the longer term changes involved with the nuclear fuel cycle both within and without the reactor itself. (U.K.)

On the safety performance of the advanced nuclear energy systems

International Nuclear Information System (INIS)

Li Shounan

1999-01-01

Some features on the safety performances of the Advanced Nuclear Energy Systems are discussed. The advantages and some peculiar problems on the safety of Advanced Nuclear Energy Systems with subcritical nuclear reactor driven by external neutron sources are also pointed out in comparison with conventional nuclear reactors

Nuclear power engineering: Public understanding and public opinion

International Nuclear Information System (INIS)

Kryshev, A.I.; Sazykina, T.G.

1998-01-01

Subjective and objective reasons for the formation of public opinion about nuclear power engineering of Russia were analyzed. Some methodological errors in work with the Russian public on the problems of nuclear energy and possible methods of their correction were discussed. The social groups of the general public, which are of greatest importance in forming the attitude towards nuclear power engineering were indicated. The conclusion was reached that opinion of the ordinary population is often indicative of real drawbacks in the work of specialists in the nuclear fuel cycle. Consequently, careful surveys of public opinion about the problems of the nuclear industry should be very useful in organizing research work properly and improving the radiation safety. (author)

Education in nuclear engineering in Slovakia

International Nuclear Information System (INIS)

Slugen, V.

2005-01-01

Slovak University of Technology is the largest and also the oldest university of technology in Slovakia. Surely more than 50% of high-educated technicians who work nowadays in nuclear industry have graduated from this university. The Department of Nuclear Physics and Technology of the Faculty of Electrical Engineering and Information Technology as a one of seven faculties of this University feels responsibility for proper engineering education and training for Slovak NPP operating staff. The education process is realised via undergraduate (Bc.), graduate (MSc.) and postgraduate (PhD..) study as well as via specialised training courses in a frame of continuous education system. (author)

Artificial intelligence in nuclear engineering: developments, lesson learned and future directions

Energy Technology Data Exchange (ETDEWEB)

Ruan, Da [The Belgian Nuclear Research Centre (SCK.CEN), Mol (Belgium)]. E-mail: druan@sckcen.be

2005-07-01

Full text of publication follows: In this lecture, an overview on artificial intelligence (AI) from control to decision making in nuclear engineering will be given mainly based on the 10 years progress of the FLINS forum (Fuzzy Logic and Intelligent Technology in Nuclear Science). Some FLINS concrete examples on nuclear reactor operation, nuclear safeguards information management, and cost estimation under uncertainty for a large nuclear project will be illustrated for the potential use of AI in nuclear engineering. Recommendations and future research directions on AI in nuclear engineering will be suggested from a practical point of view. (author)

Artificial intelligence in nuclear engineering: developments, lesson learned and future directions

International Nuclear Information System (INIS)

Ruan, Da

2005-01-01

Full text of publication follows: In this lecture, an overview on artificial intelligence (AI) from control to decision making in nuclear engineering will be given mainly based on the 10 years progress of the FLINS forum (Fuzzy Logic and Intelligent Technology in Nuclear Science). Some FLINS concrete examples on nuclear reactor operation, nuclear safeguards information management, and cost estimation under uncertainty for a large nuclear project will be illustrated for the potential use of AI in nuclear engineering. Recommendations and future research directions on AI in nuclear engineering will be suggested from a practical point of view. (author)

Advanced I and C systems for nuclear power plants feedback of experience

International Nuclear Information System (INIS)

Prehler Heinz Josef

2001-01-01

Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Additionally specific requirements arising from nuclear qualification have to be fulfilled. To meet both subjects adequately in the future, Siemens has developed advanced I and C technology consisting of the two complementary I and C systems TELEPERM XP and TELEPERM XS. TELEPERM XP is primarily oriented to automation of the non safety related part of the power plant process. Such applications involve extensive open and closed loop control systems and encompass all tasks required for process control via the man-machine interface. Therefore the TELEPERM XP system consists of the AS 620 automation system, the OM 690 process control and management system, the ES 680 engineering system, the DS 670 diagnostic system and the SIMATIC NET bus system. Three versions of automation systems are available: for standard automation, for fail safe automation of safety related tasks and for turbine automation. TELEPERM XS is designed to meet all the requirements on I and C important to safety in nuclear power plants. Typical applications include reactor protection (RPS) and Engineered Safety Features Actuation System functions (ESFAS). TELEPERM XS has been rapidly accepted by the market and has accumulated an extensive operational experience. The expected advantages, namely, reduced space requirements, consistent documentation, improved ergonomics, reduced testing effort, less repair have been confirmed by the operation. The new possibilities to apply intelligent diagnostic methods have been only applied in few cases. Very good service records from a broad field of safety application prove that it is right to use digital I and C systems for safety tasks. The expected advantages such as reduced space requirements, less repairs and less effort for periodic tests, have been confirmed by practical experience. For the future, use of digital I and C systems for safety

Labor supply of engineers and scientists for nuclear electric utilities, 1987-1992

International Nuclear Information System (INIS)

Blair, L.M.

1988-01-01

An assessment of the adequacy of the supply of health physicists, nuclear engineers, and other engineers for the nuclear electric utility industry is based on job openings for scientists and engineers in broader nuclear-power-related fields, which include engineering and design, manufacturing, fabrication, supporting services, and government. In assessing the likely adequacy of labor supplies for commercial nuclear power job openings over the next 5 yr, consideration has been given to competing sources of labor demands, including nuclear energy research and development activities, nuclear defense, and the total US economy, and to the likely supply of new graduates. In particular, over the last 3 yr, the number of degrees awarded and enrollments in nuclear engineering programs have declined 12 and 14%, respectively, and in health physics programs, 5 and 14%, respectively. For health physics and nuclear engineers, tight labor market conditions (i.e. labor supplies and demand balanced at relatively high salaries) are expected over the next 5 yr because of declining enrollments and slowly growing employment levels plus job replacement needs. The commercial nuclear power field is expected to face tight labor markets for electrical and materials engineers because of strong competing demands in the economy. Other engineering occupations are likely to have adequate supplies for the nuclear power field but at salaries that continue to be relatively higher than salaries for other professional occupations

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)

Trends in the design of advanced nuclear reactors

International Nuclear Information System (INIS)

Poong-Eil Juhn; Kupitz, Juergen

1996-01-01

Nuclear energy is an essentially unlimited energy source with the potential to provide energy in the form of electricity, district heat and process heat environmentally acceptable conditions. However, this potential will be realized only if nuclear power plants can meet the challenges of national safety requirements, economic competitiveness and public acceptance. Worldwide, a tremendous amount of experience has been accumulated during the development, licensing, construction and operation of nuclear power plants. This experience forms a sound basis for further improvements. Nuclear programmes in the IAEA Member States are addressing the development of advanced reactors, which are intended to have better economics, higher reliability and improved safety. The IAEA, as a global international governmental organization dealing with nuclear power, promotes international information exchange and international co-operation between all countries with their own advanced power programmes and offers assistance to countries with an interest in exploratory or research programmes. The paper gives an overview of global trends in the design of advanced nuclear reactors for electricity generation and heat production along with the role of IAEA. (author)

Exporting nuclear engineering and the industry's viewpoint

International Nuclear Information System (INIS)

Barthelt, K.

1986-01-01

Nuclear energy offers all possibilities to reduce the energy problems in the world which arise with the world-wide increasing population and the energy demand connected with it. The Federal Republic of Germany lives on the exports of refined technical methods which also include nuclear engineering. The exports of nuclear engineering should lead to a technology transfer with guidance and training on an equal basis between the industrial and developing countries. The preconditions of exporting nuclear-technical systems are a well-functioning domestic market and a certain support by the government, especially with regard to giving guarantees for the special exports risks of these big projects. On the other hand, exports are also needed in order to be able to continue providing high-level technology for the domestic market. (UA) [de

Finally, nuclear engineering textbooks with a Canadian flavour{exclamation_point}

Energy Technology Data Exchange (ETDEWEB)

Bonin, H.W. [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)

2002-07-01

The need for nuclear engineering textbooks more appropriate to the Canadian nuclear industry context and the CANDU nuclear reactor program has long been felt not only among the universities offering nuclear engineering programs at the graduate level, but also within the Canadian nuclear industry itself. Coverage of the CANDU reactor system in the textbooks presently supporting teaching is limited to a brief description of the concept. Course instructors usually complement these textbooks with course notes written from their personal experience from past employment within the nuclear industry and from their research interests In the last ten years, the Canadian nuclear industry has been involved on an increasing basis with the issue of the technology transfer to foreign countries which have purchased CANDU reactors or have been in the process of purchasing one or several CANDUs. For some of these countries, the 'turn key' approach is required, in which the Canadian nuclear industry looks after everything up to the commissioning of the nuclear power plant, including the education and training of local nuclear engineers and plant personnel. Atomic Energy of Canada Limited (AECL) in particular has dispatched some personnel tasked to prepare and give short courses on some specific aspects of CANDU design and operation, but a lack of consistency was observed as different persons prepared and gave the courses rather independently. To address the many problems tied with nuclear engineering education, the CANTEACH program was set up involving major partners of the Canadian nuclear industry. Parts of the activities foreseen by CANTEACH consist in the writing of nuclear engineering textbooks and associated computer-based pedagogical material. The present paper discusses the main parts of two textbooks being produced, one in reactor physics at steady state and the other on nuclear fuel management. (author)

Continuing Professional Development (CPD) of the nuclear and radiation professional engineers

International Nuclear Information System (INIS)

Sasaki, Satoru

2016-01-01

Professional Engineer is the national qualification stipulated by the Professional Engineer Act. A Professional Engineer in this Act means a person who conducts business on matters of planning, research, design, analysis, testing, evaluation or guidance thereof, which requires application of extensive scientific and technical expertise, and has three obligation and two responsibility related to engineer ethic. A technical discipline for nuclear and radiation technology in 2004, was established for the purpose of upgrading the skills of engineers in nuclear technology fields, utilizing their ability in nuclear safety regulation fields, and further strengthening safety management system in each entity. The activity of the nuclear and radiation professional engineers for the past 10 years was evaluated. For the next ten years, awareness of the role of the professional engineer to talk with general public is needed, and it is important to continue professional development. (author)

Master's degree in nuclear engineering by videotaped courses

International Nuclear Information System (INIS)

Corradini, M.L.; Vogelsang, W.F.

1991-01-01

In 1986, a group of northern midwest utilities met with faculty from the nuclear engineering department at the University of Wisconsin (UW) to discuss the possibility of offering graduate courses by videotape for academic credit and earning a master's degree. Four years later, two utility employees from Northern States Power (NSP) and Wisconsin Electric Power Companies (WEPCO) graduated from the University of Wisconsin with master's degrees earned entirely by taking videotape graduate courses at their individual nuclear power plant sites. Within these 4 years, more than a dozen videotaped graduate courses were developed by the faculty of the department in a formalized master's degree program in nuclear engineering and engineering physics. This paper outlines the program's development and its current features

Nuclear Reactor Physics

Science.gov (United States)

Stacey, Weston M.

2001-02-01

An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

Advances in biomedical engineering and biotechnology during 2013-2014.

Science.gov (United States)

Liu, Feng; Wang, Ying; Burkhart, Timothy A; González Penedo, Manuel Francisco; Ma, Shaodong

2014-01-01

The 3rd International Conference on Biomedical Engineering and Biotechnology (iCBEB 2014), held in Beijing from the 25th to the 28th of September 2014, is an annual conference that intends to provide an opportunity for researchers and practitioners around the world to present the most recent advances and future challenges in the fields of biomedical engineering, biomaterials, bioinformatics and computational biology, biomedical imaging and signal processing, biomechanical engineering and biotechnology, amongst others. The papers published in this issue are selected from this conference, which witnesses the advances in biomedical engineering and biotechnology during 2013-2014.

Experience with performance based training of nuclear criticality safety engineers

International Nuclear Information System (INIS)

Taylor, R.G.

1993-01-01

Historically, new entrants to the practice of nuclear criticality safety have learned their job primarily by on-the-job training (OJT) often by association with an experienced nuclear criticality safety engineer who probably also learned their job by OJT. Typically, the new entrant learned what he/she needed to know to solve a particular problem and accumulated experience as more problems were solved. It is likely that more formalism will be required in the future. Current US Department of Energy requirements for those positions which have to demonstrate qualification indicate that it should be achieved by using a systematic approach such as performance based training (PBT). Assuming that PBT would be an acceptable mechanism for nuclear criticality safety engineer training in a more formal environment, a site-specific analysis of the nuclear criticality safety engineer job was performed. Based on this analysis, classes are being developed and delivered to a target audience of newer nuclear criticality safety engineers. Because current interest is in developing training for selected aspects of the nuclear criticality safety engineer job, the analysis i's incompletely developed in some areas. Details of this analysis are provided in this report

Advanced nuclear reactor safety issues and research needs

International Nuclear Information System (INIS)

2002-01-01

On 18-20 February 2002, the OECD Nuclear Energy Agency (NEA) organised, with the co-sponsorship of the International Atomic Energy Agency (IAEA) and in collaboration with the European Commission (EC), a Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs. Currently, advanced nuclear reactor projects range from the development of evolutionary and advanced light water reactor (LWR) designs to initial work to develop even further advanced designs which go beyond LWR technology (e.g. high-temperature gas-cooled reactors and liquid metal-cooled reactors). These advanced designs include a greater use of advanced technology and safety features than those employed in currently operating plants or approved designs. The objectives of the workshop were to: - facilitate early identification and resolution of safety issues by developing a consensus among participating countries on the identification of safety issues, the scope of research needed to address these issues and a potential approach to their resolution; - promote the preservation of knowledge and expertise on advanced reactor technology; - provide input to the Generation IV International Forum Technology Road-map. In addition, the workshop tried to link advancement of knowledge and understanding of advanced designs to the regulatory process, with emphasis on building public confidence. It also helped to document current views on advanced reactor safety and technology, thereby contributing to preserving knowledge and expertise before it is lost. (author)

Enterprise SRS: Leveraging Ongoing Operations To Advance Nuclear Fuel Cycles Research And Development Programs

Energy Technology Data Exchange (ETDEWEB)

Murray, Alice M.; Marra, John E.; Wilmarth, William R.; Mcguire, Patrick W.; Wheeler, Vickie B.

2013-07-03

The Savannah River Site (SRS) is repurposing its vast array of assets to solve future national issues regarding environmental stewardship, national security, and clean energy. The vehicle for this transformation is Enterprise SRS which presents a new, radical view of SRS as a united endeavor for ''all things nuclear'' as opposed to a group of distinct and separate entities with individual missions and organizations. Key among the Enterprise SRS strategic initiatives is the integration of research into facilities in conjunction with on-going missions to provide researchers from other national laboratories, academic institutions, and commercial entities the opportunity to demonstrate their technologies in a relevant environment and scale prior to deployment. To manage that integration of research demonstrations into site facilities, The Department of Energy, Savannah River Operations Office, Savannah River Nuclear Solutions, the Savannah River National Laboratory (SRNL) have established a center for applied nuclear materials processing and engineering research (hereafter referred to as the Center). The key proposition of this initiative is to bridge the gap between promising transformational nuclear fuel cycle processing discoveries and large commercial-scale-technology deployment by leveraging SRS assets as facilities for those critical engineering-scale demonstrations necessary to assure the successful deployment of new technologies. The Center will coordinate the demonstration of R&D technologies and serve as the interface between the engineering-scale demonstration and the R&D programs, essentially providing cradle-to-grave support to the research team during the demonstration. While the initial focus of the Center will be on the effective use of SRS assets for these demonstrations, the Center also will work with research teams to identify opportunities to perform research demonstrations at other facilities. Unique to this approach is the fact

Advanced engineering mathematics

CERN Document Server

Jeffrey, Alan

2001-01-01

Advanced Engineering Mathematics provides comprehensive and contemporary coverage of key mathematical ideas, techniques, and their widespread applications, for students majoring in engineering, computer science, mathematics and physics. Using a wide range of examples throughout the book, Jeffrey illustrates how to construct simple mathematical models, how to apply mathematical reasoning to select a particular solution from a range of possible alternatives, and how to determine which solution has physical significance. Jeffrey includes material that is not found in works of a similar nature, such as the use of the matrix exponential when solving systems of ordinary differential equations. The text provides many detailed, worked examples following the introduction of each new idea, and large problem sets provide both routine practice, and, in many cases, greater challenge and insight for students. Most chapters end with a set of computer projects that require the use of any CAS (such as Maple or Mathematica) th...

Gaseous core nuclear-driven engines featuring a self-shutoff mechanism to provide nuclear safety

International Nuclear Information System (INIS)

Heidrich, J.; Pettibone, J.; Chow, Tze-Show; Condit, R.; Zimmerman, G.

1991-11-01

Nuclear driven engines are described that could be run in either pulsed or steady state modes. In the pulsed mode nuclear energy is released by fissioning of uranium or plutonium in a supercritical assembly of fuel and working gas. In a steady state mode a fuel-gas mixture is injected into a magnetic nozzle where it is compressed into a critical state and produces energy. Engine performance is modeled using a code that calculates hydrodynamics, fission energy production, and neutron transport self-consistently. Results are given demonstrating a large negative temperature coefficient that produces self-shutoff or control of energy production. Reduced fission product inventory and the self-shutoff provide inherent nuclear safety. It is expected that nuclear engine reactor units could be scaled up from about 100 MW e

The changing face of nuclear engineering education

International Nuclear Information System (INIS)

Poston, J.W.

1991-01-01

Nuclear engineering education in the US is in a near-crisis situation. Most academic programs are small with limited enrollments and faculty. Some of these programs are being absorbed into larger academic units, while others are being terminated. The number of identifiable academic programs has dropped dramatically over the last several years, and there is genuine concern that this downward trend will continue. The recent report by the National Academy of Sciences highlights the problems, needs, and prospects for nuclear engineering education in this country. At the same time, some programs appear to be relatively healthy and somewhat secure. A closer look at these programs indicates that there has been an evolution in the approach taken by these survivors toward both their academic and research programs. This paper discusses the approaches taken at Texas A and M University over the last 8 to 10 years to strengthen the Department of Nuclear Engineering

Nuclear Targeting Terms for Engineers and Scientists

Energy Technology Data Exchange (ETDEWEB)

St Ledger, John W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-02-01

The Department of Defense has a methodology for targeting nuclear weapons, and a jargon that is used to communicate between the analysts, planners, aircrews, and missile crews. The typical engineer or scientist in the Department of Energy may not have been exposed to the nuclear weapons targeting terms and methods. This report provides an introduction to the terms and methodologies used for nuclear targeting. Its purpose is to prepare engineers and scientists to participate in wargames, exercises, and discussions with the Department of Defense. Terms such as Circular Error Probable, probability of hit and damage, damage expectancy, and the physical vulnerability system are discussed. Methods for compounding damage from multiple weapons applied to one target are presented.

Master on Nuclear Engineering and Applications (MINA): instrument of knowledge management in the nuclear sector

International Nuclear Information System (INIS)

Herranz, L. E.; Garcia Cuesta, J. C.; Falcon, S.; Casas, J. A.

2013-01-01

Knowledge Management in nuclear industry is indespensable to ensure excellence in performance and safety of nuclear installations. The Master on Nuclear Engineering and Applications (MINA) is a Spanish education venture which foundations and evolution have meant and adaptation to the European Education system and to the domestic and international changes occured in the nuclear environment. This paper summarizes the most relevant aspects of such transformation, its motivation and the final outcome. Finally, it discusses the potential benefit of a closer collaboration among the existing national education ventures in the frame of Nuclear Engineering. (Author)

Recent advances in nuclear cardiology

DEFF Research Database (Denmark)

Gutte, H.; Petersen, C. Leth; Kjaer, A.

2008-01-01

Nuclear cardiology is an essential part of functional, non-invasive, cardiac imaging. Significant advances have been made in nuclear cardiology since planar (201)thallium ((201)TI) scintigraphy was introduced for the evaluation of left ventricular (LV) perfusion nearly 40 years ago. The use...... of nuclear cardiology has been steadily increasing over the last 20 years with important steps being the introduction of (99m)technetium- ((99m)Tc)-labelled perfusion radiotracers, the change from only planar to now much more single photon emission computed tomography (SPECT) and positron emission tomography...... (PET), electrocardiogram gating of nuclear perfusion imaging, and finally introducing nuclear hybrid imaging using either SPECT or PET together with either computed tomography or magnetic resonance imaging. The indications have extended from nearly only coronary artery diseases to several non...

Application of AI Technology for some design problems in nuclear engineering

International Nuclear Information System (INIS)

Yoshikawa, Hidekazu; Gofuku, Akio; Takahashi, Makoto

1993-01-01

We have been engaged in the research and development on advanced computer application such as artificial intelligence in the field of instrumentation, control and systems analysis of nuclear engineering, for a long period since early 80a. Since then, our research activities have covered the following areas: reactor diagnostic methods and systems, post-trip plant analyzer. module-based simulation system for NPP dynamic simulation, various intelligent support methods for light water reactor two-phase flow analysis, intelligent CAD/CAE system for conceptual design of advanced reactor, human cognitive experiment on man-machine interface and the related bio cybernetic measurement, and man-machine system design evaluation methodology development. In this paper, we will start by brief historical reviews on our past progress in the aforementioned research items to. Then, we will proceed to introduce on-going two topics and, concerning methodological development of object-oriented intelligent CAD/CAE model for conceptual design of advanced reactor, and realtime human cognitive state estimator by means of bio cybernetic measurement

Risk evaluation method for faults by engineering approach. (1) Nuclear safety for accident scenario and measures for fault movement

International Nuclear Information System (INIS)

Narabayashi, Tadashi; Chiba, Go; Okamoto, Koji; Kameda, Hiroyuki; Ebisawa, Katsumi; Yamazaki, Haruo; Konagai, Kazuo; Kamiya, Masanobu; Nagasawa, Kazuyuki

2016-01-01

Japan, as a frequent earthquake country, has a responsibility to resolve efficient measures to enhance nuclear safety, to continue utilizing the nuclear power, based on the risks and importance levels in the scientific and rational manner. In his paper describes how to evaluate the risk of faults movement by engineering approach. An open fruitful discussion by experts in the various area of earthquake, geology, geotechnical, civil, and a seismic design as well as other stakeholders such as academia professors, nuclear reactor engineers, regulators, and licensees. The Atomic Energy Society established an Investigation Committee on Development of Activity and Risk Evaluation Method for Faults by Engineering Approach (IC-DAREFEA) on October 1st, a 2014. The Investigation Committee utilizes the most advanced scientific and rational judgement, and continuous discussions and efforts in the global field, in order to collect and organize these knowledge and reflect the global standards and nuclear regulations, such as risk evaluation method for the faults movements and prevention of severe accidents, based on the accumulated database in the world, including Chuetsuoki Earthquake, North Nagano Earthquake and Kumamoto Earthquake. (author)

[Advanced online search techniques and dedicated search engines for physicians].

Science.gov (United States)

Nahum, Yoav

2008-02-01

In recent years search engines have become an essential tool in the work of physicians. This article will review advanced search techniques from the world of information specialists, as well as some advanced search engine operators that may help physicians improve their online search capabilities, and maximize the yield of their searches. This article also reviews popular dedicated scientific and biomedical literature search engines.

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1976-01-01

Advances in Nuclear Science and Technology, Volume 9 provides information pertinent to the fundamental aspects of nuclear science and technology. This book discusses the safe and beneficial development of land-based nuclear power plants.Organized into five chapters, this volume begins with an overview of the possible consequences of a large-scale release of radioactivity from a nuclear reactor in the event of a serious accident. This text then discusses the extension of conventional perturbation techniques to multidimensional systems and to high-order approximations of the Boltzmann equation.

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1972-01-01

Advances in Nuclear Science and Technology, Volume 6 provides information pertinent to the fundamental aspects of nuclear science and technology. This book covers a variety of topics, including nuclear steam generator, oscillations, fast reactor fuel, gas centrifuge, thermal transport system, and fuel cycle.Organized into six chapters, this volume begins with an overview of the high standards of technical safety for Europe's first nuclear-propelled merchant ship. This text then examines the state of knowledge concerning qualitative results on the behavior of the solutions of the nonlinear poin

Recent advances in systems metabolic engineering tools and strategies.

Science.gov (United States)

Chae, Tong Un; Choi, So Young; Kim, Je Woong; Ko, Yoo-Sung; Lee, Sang Yup

2017-10-01

Metabolic engineering has been playing increasingly important roles in developing microbial cell factories for the production of various chemicals and materials to achieve sustainable chemical industry. Nowadays, many tools and strategies are available for performing systems metabolic engineering that allows systems-level metabolic engineering in more sophisticated and diverse ways by adopting rapidly advancing methodologies and tools of systems biology, synthetic biology and evolutionary engineering. As an outcome, development of more efficient microbial cell factories has become possible. Here, we review recent advances in systems metabolic engineering tools and strategies together with accompanying application examples. In addition, we describe how these tools and strategies work together in simultaneous and synergistic ways to develop novel microbial cell factories. Copyright © 2017 Elsevier Ltd. All rights reserved.

Advanced digital technology - improving nuclear power plant performance through maintainability

International Nuclear Information System (INIS)

Ford, J.L.; Senechal, R.R.; Altenhein, G.D.; Harvey, R.P.

1998-01-01

In today's energy sector there is ever increasing pressure on utilities to operate power plants at high capacity factors. To ensure nuclear power is competitive into the next century, it is imperative that strategic design improvements be made to enhance the performance of nuclear power plants. There are a number of factors that affect a nuclear power plant's performance; lifetime maintenance is one of the major contributors. The maturing of digital technology has afforded ABB the opportunity to make significant design improvements in the area of maintainability. In keeping with ABB's evolutionary advanced nuclear plant design approach, digital technology has systematically been incorporated into the control and protection systems of the most recent Korean nuclear units in operation and under construction. One example of this was the multi-functional design team approach that was utilized for the development of ABB's Digital Plant Protection System (DPPS). The design team consisted of engineers, maintenance technicians, procurement specialists and manufacturing personnel in order to provide a complete perspective on all facets of the design. The governing design goals of increased reliability and safety, simplicity of design, use of off-the-shelf products and reduced need for periodic surveillance testing were met with the selection of proven ABB-Advant Programmable Logic Controllers (PLCs) as the heart of the DPPS. The application of digital PLC technology allows operation for extended periods without requiring routine maintenance or re-calibration. A well documented commercial dedication program approved by the United States Nuclear Regulatory Commission (US NRC) as part of the System 80+ TM Advanced Light Water Reactor Design Certification Program, allowed the use of off-the shelf products in the design of the safety protection system. In addition, a number of mechanical and electrical improvements were made which support maintainability. The result is a DPPS

Nuclear Science and Engineering education at the Delft University of Technology

International Nuclear Information System (INIS)

Bode, P.

2009-01-01

There is a national awareness in the Netherlands for strengthening education in the nuclear sciences, because of the ageing workforce, and to ensure competence as acceptability increases of nuclear power as an option for diversification of the energy supply. This may be reflected by the rapidly increasing number of students at the Delft University of Technology with interest in nuclear science oriented courses, and related bachelor and MSc graduation projects. These considerations formed the basis of the Nuclear Science and Engineering concentration, effectively starting in 2009. The programme can be taken as focus of the Research and Development Specialisation within the Master Programme in Applied Physics or as a Specialisation within the Master's Programme in Chemical Engineering. Both programmes require successful completion of a total of 120 ECTS study points, consisting of two academic years of 60 ECTS (1680 hours of study). Of that total, 100 ECTS are in the field of Nuclear Science and Engineering, depending on students choices within the programme, including a (industrial) internship, to be taken in companies all over the world. In Chemical Engineering, there is a compulsory design project during which a product or process should be developed. Both programmes also require a final graduation project. In both curricula, Nuclear Science and Engineering comprises compulsory and elective courses, which allow students to focus on either health or energy. Examples of courses include Nuclear Science, Nuclear Chemistry, Nuclear Engineering, Reactor Physics, Chemistry of the Nuclear Fuel Cycle, Medical Physics and Radiation Technology and Radiological Health Physics. (Author)

Role of testing in requalifying Transamerica Delaval, Inc., engines for nuclear service

International Nuclear Information System (INIS)

Nesbitt, J.F.; Dingee, D.A.; Laity, W.W.

1985-03-01

This paper discusses the role of testing in requalifying Transamerica Delaval, Inc. (TDI) diesel generators for use as emergency standby power sources at nuclear power plants. ''Lead'' engine tests (to confirm the design adequacy of key engine components under conditions that could induce high-cycle fatigue) and ''following'' engine tests (for engines of the same model and equipped with the same components as the ''lead'' engine) have been conducted at several nuclear power plants. The tests conducted by Duke Power Company (Catawba Nuclear Station Unit 1) and Long Island Lighting Company (Shoreham Nuclear Power Station Unit 1) are discussed. 2 refs

Advanced Nuclear Magnetic Resonance

OpenAIRE

Alonso, Diego A.

2014-01-01

Transparencias en inglés de la asignatura "Resonancia Magnética Nuclear Avanzada" (Advanced Nuclear Magnetic Resonance) (36643) que se imparte en el Máster de Química Médica como asignatura optativa de 3 créditos ECTS. En esta asignatura se completa el estudio iniciado en la asignatura de quinto curso de la licenciatura en Química "Determinación estructural" (7448) y en la del Grado de Química de tercer curso "Determinación estructural de los compuestos orgánicos" (26030) en lo referente a té...

Energy Efficient Engine program advanced turbofan nacelle definition study

Science.gov (United States)

Howe, David C.; Wynosky, T. A.

1985-01-01

Advanced, low drag, nacelle configurations were defined for some of the more promising propulsion systems identified in the earlier Benefit/Cost Study, to assess the benefits associated with these advanced technology nacelles and formulate programs for developing these nacelles and low volume thrust reversers/spoilers to a state of technology readiness in the early 1990's. The study results established the design feasibility of advanced technology, slim line nacelles applicable to advanced technology, high bypass ratio turbofan engines. Design feasibility was also established for two low volume thrust reverse/spoiler concepts that meet or exceed the required effectiveness for these engines. These nacelle and thrust reverse/spoiler designs were shown to be applicable in engines with takeoff thrust sizes ranging from 24,000 to 60,000 pounds. The reduced weight, drag, and cost of the advanced technology nacelle installations relative to current technology nacelles offer a mission fuel burn savings ranging from 3.0 to 4.5 percent and direct operating cost plus interest improvements from 1.6 to 2.2 percent.

The world nuclear power engineering. 1998 year

International Nuclear Information System (INIS)

Preobrazhenskaya, L.B.

2000-01-01

The purpose of this article consists in the analysis of the state and prospects of the world nuclear power engineering development. The data on the ratio and value of electrical energy obtained at the NPPs in the world in 1998, the specific capital expenditures on the NPPs construction by 2005, the forecast for the capacity of all NPPs by 2020 are presented. The progress in developing nuclear power engineering conditioned by improvement of the NPPs operation, optimization of their life-cycle and developing of new NPPs projects is noted [ru

Generating human resources in nuclear engineering in India: need of the hour

International Nuclear Information System (INIS)

Roy, Prateep

2010-01-01

With the fast growth of energy requirement scenario, particularly, in India with limited dependence on fossil power and increased emphasis on green power we have lots of nuclear power plant and associated projects in pipeline. This requires enormous human resources trained and qualified in nuclear engineering who will be engaged in all aspects of nuclear plant projects right from conceptualization, design, construction, development, operation, maintenance till decommissioning. As on today, Department of Atomic Energy (DAE) in Government of India is almost the only agency catering to this need. DAE grooms graduate engineers from various disciplines and postgraduates from sciences, specially, Physics and Chemistry. But, it takes enough financial resources and full 1-year duration past graduation from Indian Government. Even after imparting training to these freshly recruited DAE employees, sizeable chunk of the population quit DAE for better prospect such as higher studies abroad, management studies, IT profession etc. Also, the people trained in nuclear engineering are fewer in number than required and the gap would be increasingly large as time progresses and increasing number of nuclear plants would be constructed/operational. Comparatively larger number of engineering graduates currently produced in India are in Computer Engineering/Information Technology rather than in conventional disciplines like Civil, Mechanical, Electrical, Electronics and Telecommunications Engineering. This poses another problem of orienting/motivating the manpower in nuclear fields. Considering these problems the author proposes to produce and develop nuclear engineering graduates directly in the academic institutions which will help the nation in reducing the gap between the increasing demand of manpower in view of large number of nuclear plants in the pipeline and the availability of the nuclear engineers. Even large number of industries related to manufacturing and consultancy also

Advancing the practice of systems engineering at JPL

Science.gov (United States)

Jansma, Patti A.; Jones, Ross M.

2006-01-01

In FY 2004, JPL launched an initiative to improve the way it practices systems engineering. The Lab's senior management formed the Systems Engineering Advancement (SEA) Project in order to "significantly advance the practice and organizational capabilities of systems engineering at JPL on flight projects and ground support tasks." The scope of the SEA Project includes the systems engineering work performed in all three dimensions of a program, project, or task: 1. the full life-cycle, i.e., concept through end of operations 2. the full depth, i.e., Program, Project, System, Subsystem, Element (SE Levels 1 to 5) 3. the full technical scope, e.g., the flight, ground and launch systems, avionics, power, propulsion, telecommunications, thermal, etc. The initial focus of their efforts defined the following basic systems engineering functions at JPL: systems architecture, requirements management, interface definition, technical resource management, system design and analysis, system verification and validation, risk management, technical peer reviews, design process management and systems engineering task management, They also developed a list of highly valued personal behaviors of systems engineers, and are working to inculcate those behaviors into members of their systems engineering community. The SEA Project is developing products, services, and training to support managers and practitioners throughout the entire system lifecycle. As these are developed, each one needs to be systematically deployed. Hence, the SEA Project developed a deployment process that includes four aspects: infrastructure and operations, communication and outreach, education and training, and consulting support. In addition, the SEA Project has taken a proactive approach to organizational change management and customer relationship management - both concepts and approaches not usually invoked in an engineering environment. This paper'3 describes JPL's approach to advancing the practice of

Coordinating Space Nuclear Research Advancement and Education

International Nuclear Information System (INIS)

Bess, John D.; Webb, Jonathon A.; Gross, Brian J.; Craft, Aaron E.

2009-01-01

The advancement of space exploration using nuclear science and technology has been a goal sought by many individuals over the years. The quest to enable space nuclear applications has experienced many challenges such as funding restrictions; lack of political, corporate, or public support; and limitations in educational opportunities. The Center for Space Nuclear Research (CSNR) was established at the Idaho National Laboratory (INL) with the mission to address the numerous challenges and opportunities relevant to the promotion of space nuclear research and education.1 The CSNR is operated by the Universities Space Research Association and its activities are overseen by a Science Council comprised of various representatives from academic and professional entities with space nuclear experience. Program participants in the CSNR include academic researchers and students, government representatives, and representatives from industrial and corporate entities. Space nuclear educational opportunities have traditionally been limited to various sponsored research projects through government agencies or industrial partners, and dedicated research centers. Centralized research opportunities are vital to the growth and development of space nuclear advancement. Coordinated and focused research plays a key role in developing the future leaders in the space nuclear field. The CSNR strives to synchronize research efforts and provide means to train and educate students with skills to help them excel as leaders.

Brief 74 Nuclear Engineering Enrollments and Degrees Survey, 2014 Data

Energy Technology Data Exchange (ETDEWEB)

None, None

2015-03-15

The 2014 survey includes degrees granted between September 1, 2013 and August 31, 2014, and enrollments for fall 2014. There are three academic programs new to this year's survey. Thirty-five academic programs reported having nuclear engineering programs during 2014, and data were provided by all thirty-five. The enrollments and degrees data include students majoring in nuclear engineering or in an option program equivalent to a major. Two nuclear engineering programs have indicated that health physics option enrollments and degrees are also reported in the health physics enrollments and degrees survey.

Institute of Nuclear Engineering: report 1974-1976

International Nuclear Information System (INIS)

Amyot, L.

1976-01-01

The Institute of Nuclear Engineering is described in terms of its objectives, resources, instructional duties, and research. Basically the Institute is involved in the study of technical, economic and ecological aspects of nuclear installations, basic radioisotopic methods, and general energy problems. (E.C.B.)

Nuclear science and engineering education at a university research reactor

International Nuclear Information System (INIS)

Loveland, W.

1993-01-01

The role of an on-site irradiation facility in nuclear science and engineering education is examined. Using the example of a university research reactor, the use of such devices in laboratory instruction, public outreach programs, special instructional programs, research, etc. is discussed. Examples from the Oregon State University curriculum in nuclear chemistry, nuclear engineering and radiation health are given. (author) 1 tab

Annual report of Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, fiscal year 1996

International Nuclear Information System (INIS)

1997-08-01

This report summarizes research and educational activities, operation status of the research facilities of the Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo on fiscal year 1996. This facility has four major research facilities such as fast neutron source reactor 'Yayoi', electron Linac, fundamental experiment facility for nuclear fusion reactor blanket design and high fluence irradiation facility(HIT). Education and research activities are conducted in a wide fields of nuclear engineering using these facilities. The former two facilities are available for various studies by universities all over Japan, facility for nuclear fusion reactor blanket design is utilized for research within the Faculty of Engineering and HIT is used for the research within the University of Tokyo. The facility established a plan to reorganized into a nation wide research collaboration center in fiscal year 1995 and after further discussion of a future program it is decided to hold 'Nuclear energy symposium' periodically after fiscal year 1997 as a part of the activity for appealing the research results to the public. (G.K.)

Development of human factors engineering guide for nuclear power project

International Nuclear Information System (INIS)

Wu Dangshi; Sheng Jufang

1997-01-01

'THE PRACTICAL GUIDE FOR APPLICATION OF HUMAN FACTORS ENGINEERING TO NUCLEAR POWER PROJECT (First Draft, in Chinese)', which was developed under a research program sponsored by National Nuclear Safety Administration (NNSA) is described briefly. It is hoped that more conscious, more systematical and more comprehensive application of Human Factors Engineering to the nuclear power projects from the preliminary feasibility studies up to the commercial operation will benefit the safe, efficient and economical operations of nuclear power plants in China

NUKEM. Innovative solutions for nuclear engineering; Innovative Loesungen rund um nukleares Engineering

Energy Technology Data Exchange (ETDEWEB)

Scheffler, Beate [NUKEM Technologies GmbH, Alzenau (Germany)

2011-03-15

Management of radioactive waste, handling spent fuel elements, decommissioning of nuclear facilities, and engineering and consulting activities are services associated with the name of NUKEM all over the world. The company's scientists and engineers develop solution concepts combining the latest technologies with proven techniques and many years of experience. The company;s history and the services offered to the nuclear industry began more than 5 decades ago. The predecessor, NUKEM Nuklear-Chemie-Metallurgie, was founded in 1960 as one of the earliest nuclear companies in Germany. Originally, the firm produced fuel elements for a variety of reactor lines. As early as in the 1970s, logical extensions of these business activities were nuclear engineering and plant construction. In the meantime, NUKEM Technologies GmbH has developed a worldwide reputation for its activities. Numerous reference projects bear witness to optimum project management and customer satisfaction. Since 2009, NUKEM Technologies has been a wholly owned subsidiary of the Russian Atomstroyexport. NUKEM Technologies operates sales and project offices outside Germany, e.g. in Russia, China, Lithuania, France, and Bulgaria. In this way, the company is present in its target markets of Russia, Western and Eastern Europe as well as Asia, offering customers and partners fast and direct contacts. (orig.)

Nuclear engineering terms and definitions

International Nuclear Information System (INIS)

1981-01-01

The most important nuclear engineering's terms and definitions are given in this standard. The definitions take into account the Austrian Regulations for Radiation Protection, for and pertinent ISO and DIN-Standards as also the OENORM A7006 and OENORM A6601. (M.T.)

Ceramic technology for Advanced Heat Engines Project

Energy Technology Data Exchange (ETDEWEB)

Johnson, D.R.

1991-07-01

Significant accomplishments in fabricating ceramic components for advanced heat engine programs have provided evidence that the operation of ceramic parts in high-temperature engine environments is feasible. However, these programs have also demonstrated that additional research is needed in materials and processing development, design methodology, and database and life prediction before industry will have a sufficient technology base from which to produce reliable cost-effective ceramic engine components commercially. An assessment of needs was completed, and a five year project plan was developed with extensive input from private industry. The project approach includes determining the mechanisms controlling reliability, improving processes for fabricating existing ceramics, developing new materials with increased reliability, and testing these materials in simulated engine environments to confirm reliability. Although this is a generic materials project, the focus is on the structural ceramics for advanced gas turbine and diesel engines, ceramic bearings and attachments, and ceramic coatings for thermal barrier and wear applications in these engines. To facilitate the rapid transfer of this technology to US industry, the major portion of the work is being done in the ceramic industry, with technological support from government laboratories, other industrial laboratories, and universities. This project is managed by ORNL for the Office of Transportation Technologies, Office of Transportation Materials, and is closely coordinated with complementary ceramics tasks funded by other DOE offices, NASA, DOD, and industry.

Engineering development in nuclear power plant construction

International Nuclear Information System (INIS)

Guenther, P.

1979-01-01

Proceeding from the up-to-now experience in the erection of nuclear power stations, especially of the first and second unit of the Greifswald nuclear power plant, the following essential aspects of the development of constructional engineering are discussed: (1) constructional features and criteria, (2) organizational management, (3) current status and problems in prelimary operations, and (4) possibilities of further expenditure reductions in constructing nuclear power stations

Design study on advanced nuclear fuel recycle system. Conceptual design study of recycle system using molten salt

International Nuclear Information System (INIS)

Kasai, Y.; Kakehi, I.; Moro, T.; Higashi, T.; Tobe, K.; Kawamura, F.; Yonezawa, S.; Yoshiuji, T.

1998-10-01

Advanced recycle system engineering group of OEC (Oarai Engineering Center) has being carried out a design study of the advanced nuclear fuel recycle system using molten salt (electro-metallurgical process). This system is aiming for improvements of fuel cycle economy and reduction of environmental burden (MA recycles, Minimum of radioactive waste disposal), and also improvement of safety and nuclear non-proliferation. This report describes results of the design study that has been continued since December 1996. (1) A design concept of the advanced nuclear fuel recycle system, that is a module type recycles system of pyrochemical reprocessing and fuel re-fabrication was studied. The module system has advantage in balance of Pu recycle where modules are constructed in coincidence with the construction plan of nuclear power plants, and also has flexibility for technology progress. A demonstration system, minimum size of the above module, was studies. This system has capacity of 10 tHM/y and is able to demonstrate recycle technology of MOX fuel, metal fuel and nitride fuel. (2) Each process of the system, which are pyrochemical electrorefining system, cathode processor, de-cladding system, waste disposal system, etc., were studied. In this study, capacity of an electrorefiner was discussed, and vitrification experiment of molten salt using lead-boric acid glass was conducted. (3) A hot cell system and material handling system of the demonstration system was studied. A robot driven by linear motor was studied for the handling system, and an arrangement plan of the cell system was made. Criticality analysis in the cell system and investigation of material accountancy system of the recycle plant were also made. This design study will be continued in coincidence with design study of reactor and fuel, aiming to establish the concept of FBR recycle system. (author)

Laguna Verde nuclear power plant: an experience to consider in advanced BWR design

International Nuclear Information System (INIS)

Fuentes Marquez, L.

2001-01-01

Laguna Verde is a BWR 5 containment Mark II. Designed by GE, two external re-circulation loops, each of them having two speed re-circulation pump and a flow control valve to define the drive flow and consequently the total core flow an power control by total core flow. Laguna Verde Design and operational experience has shown some insights to be considering in design for advanced BRW reactors in order to improve the potential of nuclear power plants. NSSS and Balance of plant design, codes used to perform nuclear core design, margins derived from engineering judgment, at the time Laguna Verde designed and constructed had conducted to have a plant with an operational license, generating with a very good performance and availability. Nevertheless, some design characteristics and operational experience have shown that potential improvements or areas of opportunity shall be focused in the advanced BWR design. Computer codes used to design the nuclear core have been evolved relatively fast. The computers are faster and powerful than those used during the design process, also instrumentation and control are becoming part of this amazing technical evolution in the industry. The Laguna Verde experience is the subject to share in this paper. (author)

Notes on Advanced Engineering Education

Science.gov (United States)

Klimenko, A. Y.

2017-01-01

This article reviews history, analyses principles and presents a modern interpretation of advanced engineering education (AEE). AEE originated in France, was adapted in Germany and reached its zenith in the second half of the twentieth century as part of technological efforts induced by the space race. AEE is an enhanced form of education aimed at…

Advances and perspectives in tooth tissue engineering.

Science.gov (United States)

Monteiro, Nelson; Yelick, Pamela C

2017-09-01

Bio-engineered teeth that can grow and remodel in a manner similar to that of natural teeth have the potential to serve as permanent replacements to the currently used prosthetic teeth, such as dental implants. A major challenge in designing functional bio-engineered teeth is to mimic both the structural and anisotropic mechanical characteristics of the native tooth. Therefore, the field of dental and whole tooth regeneration has advanced towards the molecular and nanoscale design of bio-active, biomimetic systems, using biomaterials, drug delivery systems and stem cells. The focus of this review is to discuss recent advances in tooth tissue engineering, using biomimetic scaffolds that provide proper architectural cues, exhibit the capacity to support dental stem cell proliferation and differentiation and sequester and release bio-active agents, such as growth factors and nucleic acids, in a spatiotemporal controlled manner. Although many in vitro and in vivo studies on tooth regeneration appear promising, before tooth tissue engineering becomes a reality for humans, additional research is needed to perfect methods that use adult human dental stem cells, as opposed to embryonic dental stem cells, and to devise the means to generate bio-engineered teeth of predetermined size and shape. Copyright © 2016 John Wiley & Sons, Ltd. Copyright © 2016 John Wiley & Sons, Ltd.

Advanced teleoperation in nuclear applications

International Nuclear Information System (INIS)

Hamel, W.R.; Feldman, M.J.; Martin, H.L.

1984-01-01

A new generation of integrated remote maintenance systems is being developed to meet the needs of future nuclear fuel reprocessing at the Oak Ridge National Laboratory. Development activities cover all aspects of an advanced teleoperated maintenance system with particular emphasis on a new force-reflecting servomanipulator concept. The new manipulator, called the advanced servomanipulator, is microprocessor controlled and is designed to achieve force-reflection performance near that of mechanical master/slave manipulators. The advanced servomanipulator uses a gear-drive transmission which permits modularization for remote maintainability (by other advanced servomanipulators) and increases reliability. Human factors analysis has been used to develop an improved man/machine interface concept based upon colorgraphic displays and menu-driven tough screens. Initial test and evaluation of two advanced servomanipulator slave arms and several other development components have begun. 9 references, 5 figures

Microbial engineering for the production of advanced biofuels.

Science.gov (United States)

Peralta-Yahya, Pamela P; Zhang, Fuzhong; del Cardayre, Stephen B; Keasling, Jay D

2012-08-16

Advanced biofuels produced by microorganisms have similar properties to petroleum-based fuels, and can 'drop in' to the existing transportation infrastructure. However, producing these biofuels in yields high enough to be useful requires the engineering of the microorganism's metabolism. Such engineering is not based on just one specific feedstock or host organism. Data-driven and synthetic-biology approaches can be used to optimize both the host and pathways to maximize fuel production. Despite some success, challenges still need to be met to move advanced biofuels towards commercialization, and to compete with more conventional fuels.

Nuclear instrument engineering - the measuring and informative basis of nuclear science and technology

International Nuclear Information System (INIS)

Matveev, V.V.; Krasheninnikov, I.S.; Murin, I.D.; Stas', K.N.

1977-01-01

The cornerstones of developing nuclear instrument engineering in the USSR are shortly discussed. The industry is based on a well developed theory. A system approach is a characteristic feature of the present-day measuring and control systems engineering. Major functions of reactor instruments measuring different types of ionizing radiation are discussed at greater length. Nuclear measuring and control instruments and methods are widely used in different fields of science and technoloay and in different industries in the USSR. The efficient and safe operation of a nuclear facility is underlined to depend strongly upon a correlation between a technological process and the information and control system of the facility

Introduction to digital instrumentation and control techniques used in nuclear engineering

International Nuclear Information System (INIS)

Kurilla, R.G.; Kenney, E.S.

1988-01-01

For the past 8 yr, the nuclear engineering department at Pennsylvania State University has been teaching a digital interfacing class at the undergraduate (senior) level. With the ever-increasing use of computers in the nuclear engineering area (such as in the use of automated data acquisition systems) and the complexity of control instrumentation, more than a cursory introduction into electronics and computer controls is needed. Because of the ever-increasing popularity, and hence importance, of IBM-PC compatible microcomputers in the engineering fields, the program has been adapted to the Intel 8086 microprocessor. Courses such as this one are helpful in ensuring the students have an adequate design and practice base as required by accrediting groups. The course, is composed of three parts: (1) machine code/assembly language, (2) interfacing, and (3) final project. Experience demonstrates that a course of this inherent complexity can successfully be taught within a nuclear engineering curriculum without extensive prerequisites. The important ingredient is to treat nuclear engineering students for exactly what they are, engineers. By having them use their creativity and adaptability, they can successfully integrate the digital interfacing techniques now routinely used in the nuclear industry

International Joint Conference on Mechanics, Design Engineering & Advanced Manufacturing

CERN Document Server

Nigrelli, Vincenzo; Oliveri, Salvatore; Peris-Fajarnes, Guillermo; Rizzuti, Sergio

2017-01-01

This book gathers papers presented at the International Joint Conference on Mechanics, Design Engineering and Advanced Manufacturing (JCM 2016), held on 14-16 September, 2016, in Catania, Italy. It reports on cutting-edge topics in product design and manufacturing, such as industrial methods for integrated product and process design; innovative design; and computer-aided design. Further topics covered include virtual simulation and reverse engineering; additive manufacturing; product manufacturing; engineering methods in medicine and education; representation techniques; and nautical, aeronautics and aerospace design and modeling. The book is divided into eight main sections, reflecting the focus and primary themes of the conference. The contributions presented here will not only provide researchers, engineers and experts in a range of industrial engineering subfields with extensive information to support their daily work; they are also intended to stimulate new research directions, advanced applications of t...

Advances in nuclear science and technology

CERN Document Server

Henley, Ernest J

1973-01-01

Advances in Nuclear Science and Technology, Volume 7 provides information pertinent to the fundamental aspects of nuclear science and technology. This book discusses the safe and beneficial development of land-based nuclear power plants.Organized into five chapters, this volume begins with an overview of irradiation-induced void swelling in austenitic stainless steels. This text then examines the importance of various transport processes for fission product redistribution, which depends on the diffusion data, the vaporization properties, and the solubility in the fuel matrix. Other chapters co

Out-of-core nuclear fuel cycle optimization utilizing an engineering workstation

International Nuclear Information System (INIS)

Turinsky, P.J.; Comes, S.A.

1986-01-01

Within the past several years, rapid advances in computer technology have resulted in substantial increases in their performance. The net effect is that problems that could previously only be executed on mainframe computers can now be executed on micro- and minicomputers. The authors are interested in developing an engineering workstation for nuclear fuel management applications. An engineering workstation is defined as a microcomputer with enhanced graphics and communication capabilities. Current fuel management applications range from using workstations as front-end/back-end processors for mainframe computers to completing fuel management scoping calculations. More recently, interest in using workstations for final in-core design calculations has appeared. The authors have used the VAX 11/750 minicomputer, which is not truly an engineering workstation but has comparable performance, to complete both in-core and out-of-core fuel management scoping studies. In this paper, the authors concentrate on our out-of-core research. While much previous work in this area has dealt with decisions concerned with equilibrium cycles, the current project addresses the more realistic situation of nonequilibrium cycles

Estimates of the radiation environment for a nuclear rocket engine

International Nuclear Information System (INIS)

Courtney, J.C.; Manohara, H.M.; Williams, M.L.

1992-01-01

Ambitious missions in deep space, such as manned expeditions to Mars, require nuclear propulsion if they are to be accomplished in a reasonable length of time. Current technology is adequate to support the use of nuclear fission as a source of energy for propulsion; however, problems associated with neutrons and gammas leaking from the rocket engine must be addressed. Before manned or unmanned space flights are attempted, an extensive ground test program on the rocket engine must be completed. This paper compares estimated radiation levels and nuclear heating rates in and around the rocket engine for both a ground test and space environments

Nuclear plant engineering work and integrated management system

International Nuclear Information System (INIS)

Ohkubo, Y.; Obata, T.; Tanaka, K.

1992-01-01

The Application of computers to the design, engineering, manufacturing and construction works of nuclear power plants has greatly contributed to improvement of productivity and reliability in the nuclear power plants constructed by Mitsubishi Nuclear Group for more than ten years. However, in most cases, those systems have been developed separately and utilized independently in different computer software and hardware environments and have not been fully utilized to achieve high efficiency and reliability. In order to drastically increase the productivity and efficiency, development of NUclear power plant engineering Work and INtegrated manaGement System (NUWINGS) started in 1987 to unify and integrate various conventional and developing systems using the state-of-the-art computer technology. The NUWINGS is almost completed and is now applied to actual plant construction. (author)

Aspects of consolidation of engineering capability related to nuclear power plants

International Nuclear Information System (INIS)

Mueller, A.E.F.; Gasparian, A.E.; Calvet Filho, H.J.

1980-01-01

A major interest of countries launching nuclear program is to consolidate an engineering capability for Nuclear Power Plants design by performing part of the engineering services locally. A decade of nuclear power plant engineering and construction has exposed Brazilian architect-engineers to this new challenge. To cope with it, technology sources were identified, agreements were made and transfer is going on between foreign and local companies. Services performed by Brazilian architect-engineers are summarized. Foreign technology must be judiciously examined before implementation in a different environment. The receiver has to be prepared to develop his own capabilities and absorb the know-how being offered, taking into consideration the local engineering experience and construction practices. Some of the problems faced are outlined herein. The performed efforts brought Brazilian architect-engineers to a consolidated level of experience. (Author) [pt

Engineering product storage under the advanced fuel cycle initiative. Part I: An iterative thermal transport modeling scheme for high-heat-generating radioactive storage forms

International Nuclear Information System (INIS)

Kaminski, Michael D.

2005-01-01

The US Department of Energy is developing an integrated nuclear fuel cycle technology under its Advanced Fuel Cycle Initiative (AFCI). Under the AFCI, waste minimization is stressed. Engineered product storage materials will be required to store concentrated radioactive cesium, strontium, americium, and curium for periods of tens to hundreds of years. The fabrication of such engineered products has some precedence but the concept is largely novel. We thus present a theoretical model used to calculate the maximum radial dimensions of right cylinder storage forms under several scenarios. Maximum dimensions are small, comparable to nuclear fuel pins in some cases, to avoid centerline melting temperatures; this highlights the need for a careful strategy for engineered product storage fabrication and storage

Engine cycle design considerations for nuclear thermal propulsion systems

International Nuclear Information System (INIS)

Pelaccio, D.G.; Scheil, C.M.; Collins, J.T.

1993-01-01

A top-level study was performed which addresses nuclear thermal propulsion system engine cycle options and their applicability to support future Space Exploration Initiative manned lunar and Mars missions. Technical and development issues associated with expander, gas generator, and bleed cycle near-term, solid core nuclear thermal propulsion engines are identified and examined. In addition to performance and weight the influence of the engine cycle type on key design selection parameters such as design complexity, reliability, development time, and cost are discussed. Representative engine designs are presented and compared. Their applicability and performance impact on typical near-term lunar and Mars missions are shown

Advanced scientific computational methods and their applications to nuclear technologies. (4) Overview of scientific computational methods, introduction of continuum simulation methods and their applications (4)

International Nuclear Information System (INIS)

Sekimura, Naoto; Okita, Taira

2006-01-01

Scientific computational methods have advanced remarkably with the progress of nuclear development. They have played the role of weft connecting each realm of nuclear engineering and then an introductory course of advanced scientific computational methods and their applications to nuclear technologies were prepared in serial form. This is the fourth issue showing the overview of scientific computational methods with the introduction of continuum simulation methods and their applications. Simulation methods on physical radiation effects on materials are reviewed based on the process such as binary collision approximation, molecular dynamics, kinematic Monte Carlo method, reaction rate method and dislocation dynamics. (T. Tanaka)

Advances in water resources engineering

CERN Document Server

Wang, Lawrence

2015-01-01

The Handbook of Environmental Engineering is a collection of methodologies that study the effects of pollution and waste in their three basic forms: gas, solid, and liquid. A sister volume to Volume 15: Modern Water Resources Engineering, this volume focuses on the theory and analysis of various water resources systems including watershed sediment dynamics and modeling, integrated simulation of interactive surface water and groundwater systems, river channel stabilization with submerged vanes, non-equilibrium sediment transport, reservoir sedimentation, and fluvial processes, minimum energy dissipation rate theory and applications, hydraulic modeling development and application, geophysical methods for assessment of earthen dams, soil erosion on upland areas by rainfall and overland flow, geofluvial modeling methodologies and applications, and an environmental water engineering glossary. This critical volume will serve as a valuable reference work for advanced undergraduate and graduate students, designers of...

Engineering and maintenance applied to safety-related valves in nuclear power plants

International Nuclear Information System (INIS)

Verdu, M. F.; Perez-Aranda, J.

2014-01-01

Nuclear Division in Iberdrola engineering and Construction has a team with extensive experience on engineering and services works related to valves. Also, this team is linked to UNESA as Technical support and Reference Center. Iberdrola engineering and construction experience in nuclear power plants valves, gives effective response to engineering and maintenance works that can be demanded in a nuclear power plant and it requires a high degree of qualification and knowledge both in Operation and Outages. (Author)

Advance elements of optoisolation circuits nonlinearity applications in engineering

CERN Document Server

Aluf, Ofer

2017-01-01

This book on advanced optoisolation circuits for nonlinearity applications in engineering addresses two separate engineering and scientific areas, and presents advanced analysis methods for optoisolation circuits that cover a broad range of engineering applications. The book analyzes optoisolation circuits as linear and nonlinear dynamical systems and their limit cycles, bifurcation, and limit cycle stability by using Floquet theory. Further, it discusses a broad range of bifurcations related to optoisolation systems: cusp-catastrophe, Bautin bifurcation, Andronov-Hopf bifurcation, Bogdanov-Takens (BT) bifurcation, fold Hopf bifurcation, Hopf-Hopf bifurcation, Torus bifurcation (Neimark-Sacker bifurcation), and Saddle-loop or Homoclinic bifurcation. Floquet theory helps as to analyze advance optoisolation systems. Floquet theory is the study of the stability of linear periodic systems in continuous time. Another way to describe Floquet theory, it is the study of linear systems of differential equations with p...

Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013

International Nuclear Information System (INIS)

2013-01-01

The Mathematics and Computation Division of the American Nuclear (ANS) and the Idaho Section of the ANS hosted the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M and C 2013). This proceedings contains over 250 full papers with topics ranging from reactor physics; radiation transport; materials science; nuclear fuels; core performance and optimization; reactor systems and safety; fluid dynamics; medical applications; analytical and numerical methods; algorithms for advanced architectures; and validation verification, and uncertainty quantification

Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-01

The Mathematics and Computation Division of the American Nuclear (ANS) and the Idaho Section of the ANS hosted the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M and C 2013). This proceedings contains over 250 full papers with topics ranging from reactor physics; radiation transport; materials science; nuclear fuels; core performance and optimization; reactor systems and safety; fluid dynamics; medical applications; analytical and numerical methods; algorithms for advanced architectures; and validation verification, and uncertainty quantification.

Indian Nuclear Society annual conference-1994 on advanced technologies related to nuclear power: proceedings

International Nuclear Information System (INIS)

Grover, R.B.

1994-01-01

The focal theme of the conference is advanced technologies related to nuclear power. Over the past three decades civilian nuclear power plants around the world have accumulated about 6000 reactor years of experience and have performed quite well. Overall safety record has been satisfactory. However, nuclear community is trying to compete with its own record by trying to enhance the safety characteristics of the best operating plant. A safety culture has been established in the nuclear establishments, which is providing impetus to advances in all aspects of nuclear technology all over the world. India has ongoing programmes for the development of advanced reactors and related advanced technologies. Evolution of pressurised heavy water reactors in India, developments made in the design of advanced heavy water reactor and the fast reactor programme, are some of the topics covered in addition to highlighting worldwide developments for the next generation of light water reactors. India is one of the few countries in the world where expertise about complete fuel cycle is available. Developments in the back end of the fuel cycle, use of thorium and plutonium and other related issues are also discussed. Technology control regimes being advocated and adopted by developed nations make it imperative for us to indigenise every equipment and component that goes into a power plant. In view of this, some aspects of manufacturing technologies, inspection techniques and maintenance problems are also covered. Relevant papers are processed separately for INIS. (M.K.V.)

Advanced nuclear control and protection system ANCAP-80

International Nuclear Information System (INIS)

Asai, Takashi; Okano, Michihiko; Ishibashi, Kengo; Hasegawa, Masakoto; Fukuda, Hiroyoshi; Hosomichi, Renichi.

1983-01-01

Advanced reactor protection systems were developed to improve operational reliability and availability and to ease the burden of operators of Mitsubishi PWR Nuclear Power Stations. (Called ANCAP-80; Advanced Nuclear Control And Protection System) For the PWR plants now being planned and in future plans, Mitsubishi will adopt these systems with the following functional features; (1) Four channel protection logic, (2) Automatic bypass logic, (3) Automatic test provision, (4) Optical isolators. (author)

The Plant-Window System: A framework for an integrated computing environment at advanced nuclear power plants

International Nuclear Information System (INIS)

Wood, R.T.; Mullens, J.A.; Naser, J.A.

1997-01-01

Power plant data, and the information that can be derived from it, provide the link to the plant through which the operations, maintenance and engineering staff understand and manage plant performance. The extensive use of computer technology in advanced reactor designs provides the opportunity to greatly expand the capability to obtain, analyze, and present data about the plant to station personnel. However, to support highly efficient and increasingly safe operation of nuclear power plants, it is necessary to transform the vast quantity of available data into clear, concise, and coherent information that can be readily accessed and used throughout the plant. This need can be met by an integrated computer workstation environment that provides the necessary information and software applications, in a manner that can be easily understood and sued, to the proper users throughout the plan. As part of a Cooperative Research and Development Agreement with the Electric Power Research Institute, the Oak Ridge National laboratory has developed functional requirements for a Plant-Wide Integrated Environment Distributed On Workstations (Plant-Window) System. The Plant-Window System (PWS) can serve the needs of operations, engineering, and maintenance personnel at nuclear power stations by providing integrated data and software applications within a common computing environment. The PWS requirements identify functional capabilities and provide guidelines for standardized hardware, software, and display interfaces so as to define a flexible computing environment for both current generation nuclear power plants and advanced reactor designs

Educational experiments of radiochemistry in the nuclear engineering school

International Nuclear Information System (INIS)

Akatsu, Eiko

1995-06-01

Educational experiments of radiochemistry are described. They were an improvement of educational experiment of burn-up measurement as well as experiments on a solvent extraction, a cation exchange behavior of 60 Co, liquid scintillation spectrometry and half-life determination of 87 Rb, and determination of 137 Cs in sea water. Two or one of the experiments were ordinarily studied, depending the occasional situations, by the students of the general course or of the nuclear engineering course in the Nuclear Engineering School, Nuclear Education Center, JAERI from 1976 to 1994. (author)

Advances in nuclear science and technology

CERN Document Server

Greebler, Paul

1968-01-01

Advances in Nuclear Science and Technology Volume 4 provides information pertinent to the fundamental aspects of advanced reactor concepts. This book discusses the advances in various areas of general applicability, including modern perturbation theory, optimal control theory, and industrial application of ionizing radiations.Organized into seven chapters, this volume begins with an overview of the technology of sodium-cooled fast breeder power reactors and gas-cooled power reactors. This text then examines the key role of reactor safety in the development of fast breeder reactors. Other chapt

Dictionary of nuclear engineering. In four languages: English, German, French, Russian

Energy Technology Data Exchange (ETDEWEB)

Sube, R [comp.

1985-01-01

This dictionary covers nuclear engineering defined in its general sense as applied nuclear physics: industrial and other applications of nuclear power, isotopes and ionizing radiation, nuclear materials, nuclear facilities and nuclear weapons together with their scientific and technological fundamentals. During the compilation of terms, great attention was only given to generally valid basic expressions and to special terms where these occurred in all four languages. A great number of textbooks and monographs, as well as specialist journals covering many years, have been evaluated. Detailed attention has been paid to standards. Of importance in nuclear engineering are the international standards of the International Atomic Energy Organization (including the terminology employed by the International Nuclear Information System INIS), the International Organization of Standardization, the Council for Mutual Economic Assistance, the World Energy Conference, the International Electrical Engineering Commission, and also a great many national standards which, unfortunately, frequently deviate from one another as regards definition and, in particular, designation.

Fuel rod bundles proposed for advanced pressure tube nuclear reactors

International Nuclear Information System (INIS)

Prodea, Iosif; Catana, Alexandru

2010-01-01

The paper aims to be a general presentation for fuel bundles to be used in Advanced Pressure Tube Nuclear Reactors (APTNR). The characteristics of such a nuclear reactor resemble those of known advanced pressure tube nuclear reactors like: Advanced CANDU Reactor (ACR TM -1000, pertaining to AECL) and Indian Advanced Heavy Water Reactor (AHWR). We have also developed a fuel bundle proposal which will be referred as ASEU-43 (Advanced Slightly Enriched Uranium with 43 rods). The ASEU-43 main design along with a few neutronic and thermalhydraulic characteristics are presented in the paper versus similar ones from INR Pitesti SEU-43 and CANDU-37 standard fuel bundles. General remarks regarding the advantages of each fuel bundle and their suitability to be burned in an APTNR reactor are also revealed. (authors)

NATO Advanced Research Workshop on Molecular Engineering for Advanced Materials

CERN Document Server

Schaumburg, Kjeld

1995-01-01

An important aspect of molecular engineering is the `property directed' synthesis of large molecules and molecular assemblies. Synthetic expertise has advanced to a state which allows the assembly of supramolecules containing thousands of atoms using a `construction kit' of molecular building blocks. Expansion in the field is driven by the appearance of new building blocks and by an improved understanding of the rules for joining them in the design of nanometer-sized devices. Another aspect is the transition from supramolecules to materials. At present no single molecule (however large) has been demonstrated to function as a device, but this appears to be only a matter of time. In all of this research, which has a strongly multidisciplinary character, both existing and yet to be developed analytical techniques are and will remain indispensable. All this and more is discussed in Molecular Engineering for Advanced Materials, which provides a masterly and up to date summary of one of the most challenging researc...

Nuclear engineering education in the United States: a status report

International Nuclear Information System (INIS)

Miller, D.W.; Spinrad, B.I.

1986-01-01

The executive summary of the White Paper entitled The Revitalization of Nuclear Energy Education in the United States is the major component of this paper. The White Paper was completed under the auspices of the Nuclear Engineering Department Heads Organization (NEDHO). The presentation highlights events and program changes that have occurred in 1985-1986 following publication of the NEDHO White Paper. Many of these events provide optimism for the revitalization of nuclear engineering education

Status of University of Cincinnati reactor-site nuclear engineering graduate programs

International Nuclear Information System (INIS)

Anno, J.N.; Christenson, J.M.; Eckart, L.E.

1993-01-01

The University of Cincinnati (UC) nuclear engineering program faculty has now had 12 yr of experience in delivering reactor-site educational programs to nuclear power plant technical personnel. Currently, with the sponsorship of the Toledo-Edison Company (TED), we are conducting a multiyear on-site graduate program with more than 30 participants at the Davis-Besse nuclear power plant. The program enables TED employees with the proper academic background to earn a master of science (MS) degree in nuclear engineering (mechanical engineering option). This paper presents a brief history of tile evolution of UC reactor-site educational programs together with a description of the progress of the current program

Advanced CFD simulation for the assessment of nuclear safety issues at EDF. Some examples

International Nuclear Information System (INIS)

Vare, Christophe

2014-01-01

EDF R and D has computer power that puts it amongst the top industrial research centers in the world. Its supercomputers and in-house codes as well as its experts represent important capabilities to support EDF activities (safety analyses, support to the design of new reactors, analysis of accidental situations non reproducible by experiments, better understanding of physics or complex system response, effects of uncertainties and identification of prominent parameters, qualification and optimization of processes and materials...). Advanced numerical simulation is a powerful tool allowing EDF to increase its competitiveness, improve its performance and the safety of its plants. On this issue, EDF made the choice to develop its own in-house codes, instead of using commercial software, in order to be able to capitalize its expertise and methodologies. This choice allowed as well easier technological transfer to the concerned business units or engineering divisions, fast adaptation of our simulation tools to emerging needs and the development of specific physics or functionalities not addressed by the commercial offer. During the last ten years, EDF has decided to open its in-house codes, through the Open Source way. This is the case for Code – Aster (structure analysis), Code – Saturne (computational fluid dynamics, CFD), TELEMAC (flow calculations in aquatic environment), SALOME (generic platform for Pre and Post-Processing) and SYRTHES (heat transfer in complex geometries), among others. The 3 open source software: Code – Aster, Code – Saturne and TELEMAC, are certified by the French Nuclear Regulatory Authority for many «Important to Safety» studies. Advanced simulation, which treats complex, multi-field and multi-physics problems, is of great importance for the assessment of nuclear safety issues. This paper will present 2 examples of advanced simulation using Code – Saturne for safety issues of nuclear power plants in the fields of R and D and

The Nuclear Review: the Institution of Nuclear Engineers' response to the Review of Nuclear Power

International Nuclear Information System (INIS)

Anon.

1994-01-01

The United Kingdom Government's Nuclear Review currently underway, addresses whether and in what form nuclear power should continue to be part of the country's power generation capability. This article sets out the response of the Institution of Nuclear Engineers to the Nuclear Review. This pro-nuclear group emphasises the benefits to be gained from diversity of generation in the energy supply industry. The environmentally benign nature of nuclear power is emphasised, in terms of gaseous emissions. The industry's excellent safety record also argues in favour of nuclear power. Finally, as power demand increases globally, a health U.K. nuclear industry could generate British wealth through power exports and via the construction industry. The Institution's view on radioactive waste management is also set out. (UK)

The nuclear option

International Nuclear Information System (INIS)

Herken, G.

1992-01-01

A development history and current status evaluation are presented for nuclear-thermal rocket propulsion systems applicable to interplanetary flight. While the most advanced current chemical rocket engines, such as the SSMEs of the Space Shuttle, produce specific impulses of the order of 450 secs, a nuclear-thermal rocket engine tested at Los Alamos in 1969 generated 845 secs; such specific impulse improvements could represent weeks or months of interplanetary travel time. Attention is given to the achievements of the historical Nuclear Engine for Rocket Vehicle Application, Helios, and Orion design programs, as well as to the current Vehicle for Interplanetary Space Transportation Applications, which is fusion-based

Advanced technology for nuclear powerplants

International Nuclear Information System (INIS)

Rohm, H.H.

1987-01-01

Advanced technology offers significant potential benefit to the nuclear industry. Improvements can be anticipated in plant performance, reliability, and overall plant safety as well as reduced life cycle costs. Utilizing artificial intelligence and expert systems, robotics, advanced instruments and controls, and modularization technologies can enhance plant operations and provide new insights and perspectives to plant risk and thus focus resources to areas of importance. Plant reliability, operability, availability, accident interdiction and limitation, and plant recovery are expected to improve. However, utilizing these technologies is not an automatic process. In addition to the actual costs associated with developing and implementing the technologies, operator training and acceptance represents a potential significant problem. Traditional plant operators have little or no experience with computer technology. There has already been some difficulty getting nuclear plant operators to accept and use the new technologies that have been implemented to accept and use the new technologies that have been implemented thus far

Nuclear decommissioning

International Nuclear Information System (INIS)

Anon.

1987-01-01

The paper on nuclear decommissioning was presented by Dr H. Lawton to a meeting of the British Nuclear Energy Society and Institution of Nuclear Engineers, 1986. The decommissioning work currently being undertaken on the Windscale advanced gas cooled reactor (WAGR) is briefly described, along with projects in other countries, development work associated with the WAGR operation and costs. (U.K.)

Development of System Engineering Technology for Nuclear Fuel Cycle

International Nuclear Information System (INIS)

Kim, Ho Dong; Kim, Sung Ki; Song, Kee Chan

2010-04-01

This report is aims to establish design requirements for constructing mock-up system of pyroprocess by 2011 to realize long-term goal of nuclear energy promotion comprehensive plan, which is construction of engineering scale pyroprocess integrated process demonstration facility. The development of efficient process for spent fuel and establishment of system engineering technology to demonstrate the process are required to develop nuclear energy continuously. The detailed contents of research for these are as follows; - Design of Mock-up facility for demonstrate pyroprocess, Construction, Approval, Trial run, Performance test - Development of nuclear material accountancy technology for unit processes of pyroprocess and design of safeguards system - Remote operation of demonstrating pyroprocess / Development of maintenance technology and equipment - Establishment of transportation system and evaluation of pre-safety for interim storage system - Deriving and implementation of a method to improve nuclear transparency for commercialization proliferation resistance nuclear fuel cycle Spent fuel which is the most important pending problem of nuclear power development would be reduced and recycled by developing the system engineering technology of pyroprocess facility by 2010. This technology would contribute to obtain JD for the use of spent fuel between the ROK-US and to amend the ROK-US Atomic Energy Agreement scheduled in 2014

Proceedings of national symposium on advanced instrumentation for nuclear research

International Nuclear Information System (INIS)

1993-01-01

The National Symposium on Advanced Instrumentation for Nuclear Research was held in Bombay during January 27-29, 1993 at BARC. Progress of modern nuclear research is closely related to the availability of state of the art instruments and systems. With the advancements in experimental techniques and sophisticated detector developments, the performance specifications have become more stringent. State of the art techniques and diverse applications of sophisticated nuclear instrumentation systems are discussed along with indigenous efforts to meet the specific instrumentation needs of research programs in nuclear sciences. Papers of relevance to nuclear science and technology are indexed separately. (original)

UMCP-BG and E collaboration in nuclear power engineering in the framework of DOE-Utility Nuclear Power Engineering Education Matching Grant Program

Energy Technology Data Exchange (ETDEWEB)

Wolfe, Lothar PhD

2000-03-01

The DOE-Utility Nuclear Power Engineering Education Matching Grant Program has been established to support the education of students in Nuclear Engineering Programs to maintain a knowledgeable workforce in the United States in order to keep nuclear power as a viable component in a mix of energy sources for the country. The involvement of the utility industry ensures that this grant program satisfies the needs and requirements of local nuclear energy producers and at the same time establishes a strong linkage between education and day-to-day nuclear power generation. As of 1997, seventeen pairs of university-utility partners existed. UMCP was never a member of that group of universities, but applied for the first time with a proposal to Baltimore Gas and Electric Company in January 1999 [1]. This proposal was generously granted by BG&E [2,3] in the form of a gift in the amount of $25,000 from BG&E's Corporate Contribution Program. Upon the arrival of a newly appointed Director of Administration in the Department of Materials and Nuclear Engineering, the BG&E check was deposited into the University's Maryland Foundation Fund. The receipt of the letter and the check enabled UMCP to apply for DOE's matching funds in the same amount by a proposal.

Advanced engineering environment pilot project.

Energy Technology Data Exchange (ETDEWEB)

Schwegel, Jill; Pomplun, Alan R.; Abernathy, Rusty (Parametric Technology Corporation, Needham, MA)

2006-10-01

The Advanced Engineering Environment (AEE) is a concurrent engineering concept that enables real-time process tooling design and analysis, collaborative process flow development, automated document creation, and full process traceability throughout a product's life cycle. The AEE will enable NNSA's Design and Production Agencies to collaborate through a singular integrated process. Sandia National Laboratories and Parametric Technology Corporation (PTC) are working together on a prototype AEE pilot project to evaluate PTC's product collaboration tools relative to the needs of the NWC. The primary deliverable for the project is a set of validated criteria for defining a complete commercial off-the-shelf (COTS) solution to deploy the AEE across the NWC.

Main research results in the field of nuclear power engineering of the Nuclear Reactors and Thermal Physics Institute in 2014

International Nuclear Information System (INIS)

Trufanov, A.A.; Orlov, Yu.I.; Sorokin, A.P.; Chernonog, V.L.

2015-01-01

The main results of scientific and technological activities for last years of the Nuclear Reactors and Thermal Physics Institute FSUE SSC RF - IPPE in solving problems of nuclear power engineering are presented. The work have been carried out on the following problems: justification of research and development solutions and safety of NPPs with fast reactors of new generation with sodium (BN-1200, MBIR) and lead (BREST-OD-300) coolants, justification of safety of operating and advanced NPPs with WWER reactor facilities (WWER-1000, AEhS 2006, WWER-TOI), development and benchmarking of computational codes, research and development support of Beloyarsk-3 (BN-600) and Bilibino (BN-800) NPPs operation, decommissioning of AM and BR-10 research reactors, pilot scientific studies (WWER-SKD, ITER), international scientific and technical cooperation. Problems for further investigations are charted [ru

Advanced supersonic propulsion study, phases 3 and 4. [variable cycle engines

Science.gov (United States)

Allan, R. D.; Joy, W.

1977-01-01

An evaluation of various advanced propulsion concepts for supersonic cruise aircraft resulted in the identification of the double-bypass variable cycle engine as the most promising concept. This engine design utilizes special variable geometry components and an annular exhaust nozzle to provide high take-off thrust and low jet noise. The engine also provides good performance at both supersonic cruise and subsonic cruise. Emission characteristics are excellent. The advanced technology double-bypass variable cycle engine offers an improvement in aircraft range performance relative to earlier supersonic jet engine designs and yet at a lower level of engine noise. Research and technology programs required in certain design areas for this engine concept to realize its potential benefits include refined parametric analysis of selected variable cycle engines, screening of additional unconventional concepts, and engine preliminary design studies. Required critical technology programs are summarized.

Advanced LWR Nuclear Fuel Cladding Development

International Nuclear Information System (INIS)

Bragg-Sitton, S.; Griffith, G.

2012-01-01

The Advanced Light Water Reactor (LWR) Nuclear Fuel Development Research and Development (R and D) Pathway encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. To achieve significant operating improvements while remaining within safety boundaries, significant steps beyond incremental improvements in the current generation of nuclear fuel are required. Fundamental enhancements are required in the areas of nuclear fuel composition, cladding integrity, and fuel/cladding interaction to allow improved fuel economy via power uprates and increased fuel burn-up allowance while potentially improving safety margin through the adoption of an 'accident tolerant' fuel system that would offer improved coping time under accident scenarios. In a staged development approach, the LWRS program will engage stakeholders throughout the development process to ensure commercial viability of the investigated technologies. Applying minimum performance criteria, several of the top-ranked materials and fabrication concepts will undergo a rigorous series of mechanical, thermal and chemical characterization tests to better define their properties and operating potential in a relatively low-cost, nonnuclear test series. A reduced number of options will be recommended for test rodlet fabrication and in-pile nuclear testing under steady-state, transient and accident conditions. (author)

Grooved Fuel Rings for Nuclear Thermal Rocket Engines

Science.gov (United States)

Emrich, William

2009-01-01

An alternative design concept for nuclear thermal rocket engines for interplanetary spacecraft calls for the use of grooved-ring fuel elements. Beyond spacecraft rocket engines, this concept also has potential for the design of terrestrial and spacecraft nuclear electric-power plants. The grooved ring fuel design attempts to retain the best features of the particle bed fuel element while eliminating most of its design deficiencies. In the grooved ring design, the hydrogen propellant enters the fuel element in a manner similar to that of the Particle Bed Reactor (PBR) fuel element.

Introduction to nuclear test engineering

International Nuclear Information System (INIS)

O'Neal, W.C.; Paquette, D.L.

1982-01-01

The basic information in this report is from a vu-graph presentation prepared to acquaint new or prospective employees with the Nuclear Test Engineering Division (NTED). Additional information has been added here to enhance a reader's understanding when reviewing the material after hearing the presentation, or in lieu of attending a presentation

Technology readiness levels for advanced nuclear fuels and materials development

Energy Technology Data Exchange (ETDEWEB)

Carmack, W.J., E-mail: jon.carmack@inl.gov [Idaho National Laboratory, Idaho Falls, ID (United States); Braase, L.A.; Wigeland, R.A. [Idaho National Laboratory, Idaho Falls, ID (United States); Todosow, M. [Brookhaven National Laboratory, Upton, NY (United States)

2017-03-15

Highlights: • Definition of nuclear fuels system technology readiness level. • Identification of evaluation criteria for nuclear fuel system TRLs. • Application of TRLs to fuel systems. - Abstract: The Technology Readiness process quantitatively assesses the maturity of a given technology. The National Aeronautics and Space Administration (NASA) pioneered the process in the 1980s to inform the development and deployment of new systems for space applications. The process was subsequently adopted by the Department of Defense (DoD) to develop and deploy new technology and systems for defense applications. It was also adopted by the Department of Energy (DOE) to evaluate the maturity of new technologies in major construction projects. Advanced nuclear fuels and materials development is needed to improve the performance and safety of current and advanced reactors, and ultimately close the nuclear fuel cycle. Because deployment of new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the assessment process to advanced fuel development is useful as a management, communication, and tracking tool. This article provides definition of technology readiness levels (TRLs) for nuclear fuel technology as well as selected examples regarding the methods by which TRLs are currently used to assess the maturity of nuclear fuels and materials under development in the DOE Fuel Cycle Research and Development (FCRD) Program within the Advanced Fuels Campaign (AFC).

Technical verification of advanced nuclear fuel for KSNPs

International Nuclear Information System (INIS)

Lee, C. B.; Bang, J. G.; Kim, D. H. and others

2002-03-01

KNFC has developed the advanced 16x16 fuel assembly for the Korean Standard Nuclear Plants through the three-year R and D project (from April 1999 to March 2002) under the Nuclear R and D program by MOST. The purpose of this project is to verify the advanced 16x16 fuel assembly for the Korean Standard Nuclear Plants being developed by KNFC during the same period. Verification tests for the advanced fuel assembly and its components such as characteristic test on the spacer grid spring and dimple, static buckling and dynamic impact test on the 5x5 partial spacer grid, the fuel rod vibration test supported by the PLUS7 mid-spacer grid, fretting wear test, turbulent flow structure test in wind tunnel and corrosion test were performed by using the KAERI facilities. Design reports and test results produced by KNFC were technically reviewed. For the domestic production of burnable poison rod, manufacturing technology of burnable poison pellets was developed

The School for Nuclear Engineering is 25 years old: Where teachers go to school

International Nuclear Information System (INIS)

Knapp, W.

1986-01-01

For a quarter of a century the School for Nuclear Engineering at the Karlsruhe Nuclear Research Centre has provided further education in all areas of nuclear engineering. The courses are attended by all kinds of people: school teachers, shift managers in nuclear power stations and engineers from the Third World, for example. (orig.) [de

The School Advanced Ventilation Engineering Software (SAVES)

Science.gov (United States)

The School Advanced Ventilation Engineering Software (SAVES) package is a tool to help school designers assess the potential financial payback and indoor humidity control benefits of Energy Recovery Ventilation (ERV) systems for school applications.

Quality assurance system in nuclear engineering

International Nuclear Information System (INIS)

Adams, H.W.; Hoensch, V.

1985-01-01

Due to the close connection between the German Atomic Energy Law and the nuclear control regulations, quality systems in nuclear engineering have taken on a special form. Quality assurance systems as a stipulated organisation of structure and procedure to assure quality have implications for the organisation of the electric supply company at the planning, erection and commissioning stage and for the organisation of the nuclear power station facility. To supervise the application and effectiveness of the stipulated organisation of structure and procedure internally and externally among contractors, special organisation units have been set up at the plant suppliers, manufactures, electric supply companies and nuclear power station facilities, which in the electric supply field go by the name of Quality Assurance Supervision. (orig.) [de

Reconstruction of nuclear science and engineering harmonized with human society

International Nuclear Information System (INIS)

2003-03-01

At the beginning of the 21th century, the use of nuclear power has assumed very serious dimensions, because there are many problems not only safety technologies but also action of technical expert. The situation and problems of nuclear power are explained. It consists of six chapter as followings; introduction, history and R and D of nuclear power, paradigm change of nuclear science and engineering, energy science, investigation of micro world, how to research and development and education and training of special talent. The improvement plans and five proposals are stated as followings; 1) a scholar and engineer related to nuclear power have to understand ethics and build up closer connection with person in the various fields. 2) Nuclear power generation and nuclear fuel cycle are important in future, so that they have to be accepted by the society by means of opening to the public. Safety science, anti-pollution measurements, treatment and disposal of radioactive waste and development of new reactor and fusion reactor should be carried out. 3) It is necessary that the original researches of quantum beam and isotope have to step up. 4) The education of nuclear science and technology and upbringing special talent has to be reconstructed. New educational system such as 'nuclear engineering course crossing with many universities' is established. 5) Cooperation among industry, academic world and government. (S.Y.)

Recent development of nuclear power in Japan and instrumentation and control system and control room equipment for advanced light water reactors

International Nuclear Information System (INIS)

Wakayama, N.

1992-01-01

This paper was provided for the 13th IAEA/IWG-NPPCI Meeting and aims to introduce an outline of recent development of nuclear power in Japan and some topics in the field of nuclear power plant control and instrumentation. Forty units of nuclear power plants are in operation in Japan and five units of BWRs and six PWRs are under construction. Construction of prototype FBR Monju have almost completed an construction of High-Temperature Engineering Test Reactor, HTTR, started in March 1991. In parallel of those, extensive effort has been carried out to develop the third generation LWRs which are called Advanced BWR (ABWR) and Advanced PWR (APWR). Two Advanced BWRs are under safety review for construction. Instrumentation and control system of these Advanced LWRs adopts integrated digital I and C system, optical multiplexing signal transmission, fault tolerant control systems and software logic for reactor protection and safety systems and enhances plant control performance and provides human-friendly operation and maintenance environments. Main control room of these Advanced LWRs, comprised with large display panels and advanced console, has special futures such as one-man sit-down operation, human friendly man-machine interface, high level automation in operation and maintenance. (author). 7 refs, 9 figs, 1 tab

SAPHIR, a simulator for engineering and training on N4-type nuclear power plants

International Nuclear Information System (INIS)

Vovan, C.

1999-01-01

SAPHIR, the new simulator developed by FRAMATOME, has been designed to be a convenient tool for engineering and training for different types of nuclear power plants. Its first application is for the French 'N4' four-loop 1500MWe PWR. The basic features of SAPHIR are: (1) Use of advanced codes for modelling He primary and secondary systems' including an axial steam generator model, (2) Use of a simulation workshop containing different tools for modelling fluid, electrical, instrument and control networks, (3) A Man-Machine Interface designed for an easy and convivial use which can simulate the different computerized control consoles of the 'N4' control room. This paper outlines features and capabilities of this tool, both for engineering and training purposes. (author)

JAERI Nuclear Engineering School and technology transfer

International Nuclear Information System (INIS)

Nishimura, Kazuaki; Kawaguchi, Chiyoji

1978-01-01

A method is introduced to evaluate the degree of nuclear technology transfer; that is, the output powers of Japanese nuclear reactors constructed in these 20 years are chronologically plotted in a semi-log figure. All reactors plotted are classified into imported and domestic ones according to a value of domestication factor. A space between two historical trajectories of reactor construction may be interpreted as one of the measures indicating the degree of nuclear technology transfer. In connection with this method, historical change of educational and training courses in Nuclear Engineering School of Japan Atomic Energy Research Institute is reviewed in this report. (author)