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Sample records for basic lego reactor

  1. A Basic LEGO Reactor Design for the Provision of Lunar Surface Power

    International Nuclear Information System (INIS)

    John Darrell Bess

    2008-01-01

    A final design has been established for a basic Lunar Evolutionary Growth-Optimized (LEGO) Reactor using current and near-term technologies. The LEGO Reactor is a modular, fast-fission, heatpipe-cooled, clustered-reactor system for lunar-surface power generation. The reactor is divided into subcritical units that can be safely launched with lunar shipments from Earth, and then emplaced directly into holes drilled into the lunar regolith to form a critical reactor assembly. The regolith would not just provide radiation shielding, but serve as neutron-reflector material as well. The reactor subunits are to be manufactured using proven and tested materials for use in radiation environments, such as uranium-dioxide fuel, stainless-steel cladding and structural support, and liquid-sodium heatpipes. The LEGO Reactor system promotes reliability, safety, and ease of manufacture and testing at the cost of an increase in launch mass per overall rated power level and a reduction in neutron economy when compared to a single-reactor system. A single unshielded LEGO Reactor subunit has an estimated mass of approximately 448 kg and provides approximately 5 kWe. The overall envelope for a single subunit with fully extended radiator panels has a height of 8.77 m and a diameter of 0.50 m. Six subunits could provide sufficient power generation throughout the initial stages of establishing a lunar outpost. Portions of the reactor may be neutronically decoupled to allow for reduced power production during unmanned periods of base operations. During later stages of lunar-base development, additional subunits may be emplaced and coupled into the existing LEGO Reactor network, subject to lunar base power demand. Improvements in reactor control methods, fuel form and matrix, shielding, as well as power conversion and heat rejection techniques can help generate an even more competitive LEGO Reactor design. Further modifications in the design could provide power generative opportunities for

  2. Project Luna Succendo: The Lunar Evolutionary Growth-Optimized (LEGO) Reactor

    Science.gov (United States)

    Bess, John Darrell

    A final design has been established for a basic Lunar Evolutionary Growth-Optimized (LEGO) Reactor using current and near-term technologies. The LEGO Reactor is a modular, fast-fission, heatpipe-cooled, clustered-reactor system for lunar-surface power generation. The reactor is divided into subcritical units that can be safely launched within lunar shipments from the Earth, and then emplaced directly into holes drilled into the lunar regolith to form a critical reactor assembly. The regolith would not just provide radiation shielding, but serve as neutron-reflector material as well. The reactor subunits are to be manufactured using proven and tested materials for use in radiation environments, such as uranium-dioxide fuel, stainless-steel cladding and structural support, and liquid-sodium heatpipes. The LEGO Reactor system promotes reliability, safety, and ease of manufacture and testing at the cost of an increase in launch mass per overall rated power level and a reduction in neutron economy when compared to a single-reactor system. A single unshielded LEGO Reactor subunit has an estimated mass of approximately 448 kg and provides 5 kWe using a free-piston Stirling space converter. The overall envelope for a single unit with fully extended radiator panels has a height of 8.77 m and a diameter of 0.50 m. The subunits can be placed with centerline distances of approximately 0.6 m in a hexagonal-lattice pattern to provide sufficient neutronic coupling while allowing room for heat rejection and interstitial control. A lattice of six subunits could provide sufficient power generation throughout the initial stages of establishing a lunar outpost. Portions of the reactor may be neutronically decoupled to allow for reduced power production during unmanned periods of base operations. During later stages of lunar-base development, additional subunits may be emplaced and coupled into the existing LEGO Reactor network Future improvements include advances in reactor control

  3. Introduction for Freshmen to Embedded Systems Using LEGO Mindstorms

    Science.gov (United States)

    Kim, Seung Han; Jeon, Jae Wook

    2009-01-01

    The purpose of the course presented here is to introduce freshmen to embedded systems using LEGO Mindstorms, under an ANSI-C programming environment. The students build their own LEGO robots, make programs for them using ANSI-C, and operate them. By creating these LEGO robots, the students become more motivated, learning the basic concepts of…

  4. A truly Lego®-like modular microfluidics platform

    Science.gov (United States)

    Vittayarukskul, Kevin; Lee, Abraham Phillip

    2017-03-01

    Ideally, a modular microfluidics platform should be simple to assemble and support 3D configurations for increased versatility. The modular building blocks should also be mass producible like electrical components. These are fundamental features of world-renowned Legos® and why Legos® inspire many existing modular microfluidics platforms. In this paper, a truly Lego®-like microfluidics platform is introduced, and its basic feasibility is demonstrated. Here, PDMS building blocks resembling 2  ×  2 Lego® bricks are cast from 3D-printed master molds. The blocks are pegged and stacked on a traditional Lego® plate to create simple, 3D microfluidic networks, such as a single basket weave. Characteristics of the platform, including reversible sealing and automatic alignment of channels, are also analyzed and discussed in detail.

  5. A truly Lego®-like modular microfluidics platform

    International Nuclear Information System (INIS)

    Vittayarukskul, Kevin; Lee, Abraham Phillip

    2017-01-01

    Ideally, a modular microfluidics platform should be simple to assemble and support 3D configurations for increased versatility. The modular building blocks should also be mass producible like electrical components. These are fundamental features of world-renowned Legos ® and why Legos ® inspire many existing modular microfluidics platforms. In this paper, a truly Lego ® -like microfluidics platform is introduced, and its basic feasibility is demonstrated. Here, PDMS building blocks resembling 2  ×  2 Lego ® bricks are cast from 3D-printed master molds. The blocks are pegged and stacked on a traditional Lego ® plate to create simple, 3D microfluidic networks, such as a single basket weave. Characteristics of the platform, including reversible sealing and automatic alignment of channels, are also analyzed and discussed in detail. (paper)

  6. LEGO-Method--New Strategy for Chemistry Calculation

    Science.gov (United States)

    Molnar, Jozsef; Molnar-Hamvas, Livia

    2011-01-01

    The presented strategy of chemistry calculation is based on mole-concept, but it uses only one fundamental relationship of the amounts of substance as a basic panel. The name of LEGO-method comes from the famous toy of LEGO[R] because solving equations by grouping formulas is similar to that. The relations of mole and the molar amounts, as small…

  7. LEGO products have become more complex.

    Science.gov (United States)

    Bartneck, Christoph; Moltchanova, Elena

    2018-01-01

    The LEGO Group has become the largest toy company in the world and they can look back to a proud history of more than 50 years of producing bricks and other toys. Starting with a simple set of basic bricks their range of toys appeared to have increased in complexity over the years. We processed the inventories of most sets from 1955-2015 and our analysis showed that LEGO sets have become bigger, more colorful and more specialized. The vocabulary of bricks has increased significantly resulting in sets sharing fewer bricks. The increased complexity of LEGO sets and bricks enables skilled builders to design ever more amazing models but it may also overwhelm less skilled or younger builders.

  8. LEGO products have become more complex.

    Directory of Open Access Journals (Sweden)

    Christoph Bartneck

    Full Text Available The LEGO Group has become the largest toy company in the world and they can look back to a proud history of more than 50 years of producing bricks and other toys. Starting with a simple set of basic bricks their range of toys appeared to have increased in complexity over the years. We processed the inventories of most sets from 1955-2015 and our analysis showed that LEGO sets have become bigger, more colorful and more specialized. The vocabulary of bricks has increased significantly resulting in sets sharing fewer bricks. The increased complexity of LEGO sets and bricks enables skilled builders to design ever more amazing models but it may also overwhelm less skilled or younger builders.

  9. A model of Alto Lazio boiling water reactor using the LEGO code balance of plant simulation

    International Nuclear Information System (INIS)

    Spelta, S.; Garbossa, G.B.

    1989-01-01

    An extensive effort has been made at the Italian National Electricity Board (ENEL) to construct and validate a LEGO model capable of simulating the operational transients of the Alto Lazio Nuclear Station, a two twin-units site with BWR/6 class reactors, rated at 2894 MWt and with Mark III containment. LEGO is a modular package developed at the Research and development Department of the Italian National Electricity Board (CRA-ENEL) for computer aided modeling of fossil-fired and nuclear steam power plants. In this paper a system analysis model capable of describing steady-state and transient performance of the Balance of Plant (BOP) of the Alto Lazio Power Station is presented. This is one of two companion papers devoted to the description of the overall plant model including both the Nuclear Steam Supply System (NSSS) and the BOP. In the paper, after a brief summary of the main LEGO characteristics, a description of the BOP lay-out is presented. The overall model, which has been set-up, including control systems and automation, is very detailed and consists of almost 2000 differential or algebraic equations. After a brief description of the mathematical model, two significant transients obtained using the overall model are presented and discussed

  10. Lego Car Race

    Science.gov (United States)

    Preston, Christine

    2017-01-01

    Familiar toys can be used to scaffold young children's learning about basic physics as well as guide scientific inquiry. Teachers looking for resources to engage young children and develop science inquiry skills need look no further than the toy box. In this two-part activity, children first construct a Lego® car and use it to explore the effects…

  11. A model of Altio Lazio boiling water reactor using the LEGO code nuclear steam supply system simulation

    International Nuclear Information System (INIS)

    Garbossa, G.B.; Spelta, S.; Cori, R.; Mosca, R.; Cento, P.

    1989-01-01

    An extensive effort has been made at the Italian National Electricity Board (ENEL) to construct and validate a LEGO model capable of simulating the operational transients of the Alto Lazio Nuclear Station, a two-twin units site with BWR/6 class reactors, rated at 2894 MWt and with Mark III containment. The desired end-product of this effort is an overall plant model consisting of the Nuclear Steam Supply System model, described in this paper, and the Balance of Plant model, capable of simulating the transient response of Alto Lazio Station. The models utilize the in-house developed LEGO code, which is a modular package oriented to power plant modeling and suitable to perform transient analyses to assist during power plant design, control system design and operating procedure verification. The ability of the NSSS model to predict correctly the plant response is demonstrated through comparison with results calculated by the vendor, using REDY code, and by an in-house RETRAN-02 model

  12. LEGO

    DEFF Research Database (Denmark)

    Schleicher, Marianne

    2012-01-01

    Kulturevolutionær refleksion over LEGOs udfordringer, når virksomheden gennem leg opfordrer til variation i religiøse, ikke-vestlige kulturer.......Kulturevolutionær refleksion over LEGOs udfordringer, når virksomheden gennem leg opfordrer til variation i religiøse, ikke-vestlige kulturer....

  13. Live LEGO House: a Mixed Reality Game for the Edutainment

    OpenAIRE

    Portalés Ricart, Cristina

    2007-01-01

    Gaming is a natural way of learning and multimedia technologies bring new possibilities in the field of edutainment. Live LEGO House in an interactive space to explore coexistence and multicultural factors through gaming based on the Mixed Reality(MXR)technology. The system consists basically on a physical/real house built with the LEGO blocks, which is enriched with different non-physical/virtual multimedia files, including sounds, videos and 3D animations with multicultural content. Childre...

  14. 2011 FIRST LEGO League

    Science.gov (United States)

    2010-01-01

    Matthew Myles (left) and Agrippa Kellum from Armstrong Middle School in Starkville, watch as their LEGO robot competes during a Dec. 4 tournament. Elementary and middle school students from across Mississippi gathered in Hattiesburg to participate in the Mississippi Championship FIRST (For Inspiration and Recognition of Science and Technology) LEGO League Tournament. Stennis supports FIRST LEGO League each year by providing mentors, training and tournament volunteers.

  15. Have LEGO Products Become More Violent?

    Directory of Open Access Journals (Sweden)

    Christoph Bartneck

    Full Text Available Although television, computer games and the Internet play an important role in the lives of children they still also play with physical toys, such as dolls, cars and LEGO bricks. The LEGO company has become the world's largest toy manufacturer. Our study investigates if the LEGO company's products have become more violent over time. First, we analyzed the frequency of weapon bricks in LEGO sets. Their use has significantly increased. Second, we empirically investigated the perceived violence in the LEGO product catalogs from the years 1978-2014. Our results show that the violence of the depicted products has increased significantly over time. The LEGO Company's products are not as innocent as they used to be.

  16. Have LEGO Products Become More Violent?

    Science.gov (United States)

    Bartneck, Christoph; Min Ser, Qi; Moltchanova, Elena; Smithies, James; Harrington, Erin

    2016-01-01

    Although television, computer games and the Internet play an important role in the lives of children they still also play with physical toys, such as dolls, cars and LEGO bricks. The LEGO company has become the world's largest toy manufacturer. Our study investigates if the LEGO company's products have become more violent over time. First, we analyzed the frequency of weapon bricks in LEGO sets. Their use has significantly increased. Second, we empirically investigated the perceived violence in the LEGO product catalogs from the years 1978-2014. Our results show that the violence of the depicted products has increased significantly over time. The LEGO Company's products are not as innocent as they used to be.

  17. Have LEGO Products Become More Violent?

    Science.gov (United States)

    Min Ser, Qi; Moltchanova, Elena; Smithies, James; Harrington, Erin

    2016-01-01

    Although television, computer games and the Internet play an important role in the lives of children they still also play with physical toys, such as dolls, cars and LEGO bricks. The LEGO company has become the world’s largest toy manufacturer. Our study investigates if the LEGO company’s products have become more violent over time. First, we analyzed the frequency of weapon bricks in LEGO sets. Their use has significantly increased. Second, we empirically investigated the perceived violence in the LEGO product catalogs from the years 1978–2014. Our results show that the violence of the depicted products has increased significantly over time. The LEGO Company’s products are not as innocent as they used to be. PMID:27203424

  18. Build your own tiny Lego LHC

    CERN Multimedia

    Abha Eli Phoboo

    2015-01-01

    A PhD student working on the ATLAS experiment has created a replica of the Large Hadron Collider using Lego building blocks. Nathan Readioff, from the University of Liverpool (see here), submitted his design to Lego Ideas (see here) this week and is now awaiting the 10,000 votes needed for it to qualify for the Lego Review, which decides if projects become new Lego products. You can help this project, vote online now!   A computer simulation of the miniature Lego LHC, complete with four detectors connected with blue dipole magnets. His Lego design is a stylised model of the LHC, showcasing the four main detectors ALICE, ATLAS, CMS and LHCb at the micro scale. Each detector is small enough to fit in the palm of your hand, yet the details of the internal systems are intricate, revealed by cutaway walls. Every major detector component is represented by a Lego piece. The models are not strictly to scale with one another, but the same size base is used for each one to maximise the detail that can...

  19. Instant LEGO Mindstorm EV3

    CERN Document Server

    Garber, Gary

    2013-01-01

    Filled with practical, step-by-step instructions and clear explanations for the most important and useful tasks. A concise guide full of step-by-step recipes to teach you how to build and program an advanced robot.""Instant LEGO Mindstorm EV3"" is for both the adult tinkerer who has never touched LEGO before and the experienced LEGO engineer who has evolved from Mindstorm NXT to EV3. If you are interested in entering or advising students in robot competitions such as the FIRST LEGO League, the Wold Robot Olympiad, or RoboGames, then this book is a must for you. Even if you haven't purchased yo

  20. A modular approach to lead-cooled reactors modelling

    Energy Technology Data Exchange (ETDEWEB)

    Casamassima, V. [CESI RICERCA, via Rubattino 54, I-20134 Milano (Italy)], E-mail: casamassima@cesiricerca.it; Guagliardi, A. [CESI RICERCA, via Rubattino 54, I-20134 Milano (Italy)], E-mail: guagliardi@cesiricerca.it

    2008-06-15

    After an overview of the lego plant simulation tools (LegoPST), the paper gives some details about the ongoing LegoPST extension for modelling lead fast reactor plants. It refers to a simple mathematical model of the liquid lead channel dynamic process and shows the preliminary results of its application in dynamic simulation of the BREST 300 liquid lead steam generator. Steady state results agree with reference data [IAEA-TECDOC 1531, Fast Reactor Database, 2006 Update] both for water and lead.

  1. A modular approach to lead-cooled reactors modelling

    International Nuclear Information System (INIS)

    Casamassima, V.; Guagliardi, A.

    2008-01-01

    After an overview of the lego plant simulation tools (LegoPST), the paper gives some details about the ongoing LegoPST extension for modelling lead fast reactor plants. It refers to a simple mathematical model of the liquid lead channel dynamic process and shows the preliminary results of its application in dynamic simulation of the BREST 300 liquid lead steam generator. Steady state results agree with reference data [IAEA-TECDOC 1531, Fast Reactor Database, 2006 Update] both for water and lead

  2. LEGO: A Modular Approach to Accelerator Alignment Data Analysis

    Energy Technology Data Exchange (ETDEWEB)

    LeCocq, Catherine M

    2003-05-14

    The underlying unity of the numerous surveying computational methods is hidden by many practical differences in data acquisition. Traditional programming languages have added to the confusion by requiring programmers to describe the numeric data in very concrete and low-level structures (mostly arrays). In fact the algorithms behind all coordinate determination from surveying observations come down to basic methods of linear algebra. Lego uses the paradigm of object oriented programming (OOP) to more closely model the fundamental mathematical structures of all geodetic methods. Once the methods are in OOP form, the commonality across them becomes more obvious and a general architecture for a wide range of geodetic treatments becomes possible. This paper describes the fundamental concepts of this architecture and its advantages in terms of clarity (maintainability, testability and multi-author), portability and extensibility (observation types, resolution techniques and storage methods). The very first version of Lego was built in 1994 as a set of C routines to be used for the adjustment of theodolite data and tracker data. The routines were organized into six modules. Each module answered a specific task. The tasks had been identified as followed: general implementation, input, generic surveying formulas, statistical functions, matrix manipulation and specific resolution technique. This organization was the reason for the name Lego, but more seriously the purpose of this separation was to make Lego easily adaptable to any environment and easily expandable to new resolution techniques. At a second look, it was also a cry for being converted into a more modern language. Because C++ is primarily a superset of C, most C++ compilers have no problems compiling regular C code and may also handle a mixture of C and C++. This made the transformation of Lego very fast and painless. Up to now Lego is still using C functions for file access and dynamic memory allocation but is

  3. LEGO: A Modular Approach to Accelerator Alignment Data Analysis

    International Nuclear Information System (INIS)

    LeCocq, Catherine M

    2003-01-01

    The underlying unity of the numerous surveying computational methods is hidden by many practical differences in data acquisition. Traditional programming languages have added to the confusion by requiring programmers to describe the numeric data in very concrete and low-level structures (mostly arrays). In fact the algorithms behind all coordinate determination from surveying observations come down to basic methods of linear algebra. Lego uses the paradigm of object oriented programming (OOP) to more closely model the fundamental mathematical structures of all geodetic methods. Once the methods are in OOP form, the commonality across them becomes more obvious and a general architecture for a wide range of geodetic treatments becomes possible. This paper describes the fundamental concepts of this architecture and its advantages in terms of clarity (maintainability, testability and multi-author), portability and extensibility (observation types, resolution techniques and storage methods). The very first version of Lego was built in 1994 as a set of C routines to be used for the adjustment of theodolite data and tracker data. The routines were organized into six modules. Each module answered a specific task. The tasks had been identified as followed: general implementation, input, generic surveying formulas, statistical functions, matrix manipulation and specific resolution technique. This organization was the reason for the name Lego, but more seriously the purpose of this separation was to make Lego easily adaptable to any environment and easily expandable to new resolution techniques. At a second look, it was also a cry for being converted into a more modern language. Because C++ is primarily a superset of C, most C++ compilers have no problems compiling regular C code and may also handle a mixture of C and C++. This made the transformation of Lego very fast and painless. Up to now Lego is still using C functions for file access and dynamic memory allocation but is

  4. Basic concepts of automation and mechatronics with LEGO mindstorms NXT

    Directory of Open Access Journals (Sweden)

    Matijević Milan S.

    2014-01-01

    Full Text Available Mindstorsms LEGO NXT is using in engineering education at well recognized engineering schools like RWTH Aachen University where is created the RWTH - Mindstorms NXT Toolbox for Matlab. MATLAB / Simulink is widely available and popular for students around the world, but software toolboxes which are required for work with the real time systems are too expensive for the universities, especially those in developing countries. This paper describes an approach that is currently used in introductory subjects in the field of automation and mechatronics at the University of Kragujevac, and that does not require expensive software support.

  5. Mathematics and "Lego" Robots

    Science.gov (United States)

    Hansen, Janus Halkier; Traeholt, Rune

    2007-01-01

    For the last four years, Soenderholm School, near the town of Aalborg, Northjutland, Denmark, has had an optional subject in the seventh grade called First "Lego" League (FLL). FLL is an international contest which aims to advance pupils' scientific interest. The task is for participants to build and program a "Lego" robot able…

  6. Lego Group

    DEFF Research Database (Denmark)

    Møller Larsen, Marcus; Pedersen, Torben; Slepniov, Dmitrij

    2010-01-01

    The last years’ rather adventurous journey from 2004 to 2009 had taught the fifth-largest toy-maker in the world - the LEGO Group - the importance of managing the global supply chain effectively. In order to survive the largest internal financial crisis in its roughly 70 years of existence......, the management had, among many initiatives, decided to offshore and outsource a major chunk of its production to Flextronics. In this pursuit of rapid cost-cutting sourcing advantages, the LEGO Group planned to license out as much as 80 per cent of its production besides closing down major parts...

  7. Investování do setů stavebnic LEGO

    OpenAIRE

    Voborský, Michal

    2017-01-01

    This Bachelor thesis indetifies LEGO sets as an opportunity for investment and determines sets as alternative assets. The thesis is divided into five chapters. First defines alternative assets and investing in them. Second describes the history of the LEGO Company and their products. Third one describes ways of investing in LEGO sets and defines markets, where LEGO is traded. Fourth part describes factors which influence the value of LEGO sets. Last, fifth, part analyses return on investment ...

  8. Basic training of nuclear power reactor personnel

    International Nuclear Information System (INIS)

    Palabrica, R.J.

    1981-01-01

    The basic training of nuclear power reactor personnel should be given very close attention since it constitutes the foundation of their knowledge of nuclear technology. Emphasis should be given on the thorough understanding of basic nuclear concepts in order to have reasonable assurance of successful assimilation by those personnel of more specialized and advanced concepts to which they will be later exposed. Basic training will also provide a means for screening to ensure that those will be sent for further spezialized training will perform well. Finally, it is during the basic training phase when nuclear reactor operators will start to acquire and develop attitudes regarding reactor operation and it is important that these be properly founded. (orig.)

  9. LEGO A Modular Approach to Accelerator Alignment Data Analysis

    CERN Document Server

    Lecocq, C M

    2003-01-01

    The underlying unity of the numerous surveying computational methods is hidden by many practical differences in data acquisition. Traditional programming languages have added to the confusion by requiring programmers to describe the numeric data in very concrete and low-level structures (mostly arrays). In fact the algorithms behind all coordinate determination from surveying observations come down to basic methods of linear algebra. Lego uses the paradigm of object oriented programming (OOP) to more closely model the fundamental mathematical structures of all geodetic methods. Once the methods are in OOP form, the commonality across them becomes more obvious and a general architecture for a wide range of geodetic treatments becomes possible. This paper describes the fundamental concepts of this architecture and its advantages in terms of clarity (maintainability, testability and portability and extensibility (observation types, resolution techniques and storage methods). The very first version of Lego was bu...

  10. Lego: When video games bridge between play and cinema

    Directory of Open Access Journals (Sweden)

    Mattia Thibault

    2015-09-01

    Full Text Available This paper proposes an exploration of the Lego Transmedia World. The starting point is a definition of a Lego aesthetics based on four characteristics: modularity, translatability, intertextuality and a tripartite nature of Lego minifigures. A brief analysis of the most popular types of Lego products – toys, games, video games and movies – will delineate a continuum that goes from different degrees of playfulness to mere readership: continuum in which videogames hold a special position. The final aim of this article is to underline, thanks to the Lego case study, the complexity and variety of the knotty intertextual nets that characterize transmedia realities.

  11. 3D Digital Legos for Teaching Security Protocols

    Science.gov (United States)

    Yu, Li; Harrison, L.; Lu, Aidong; Li, Zhiwei; Wang, Weichao

    2011-01-01

    We have designed and developed a 3D digital Lego system as an education tool for teaching security protocols effectively in Information Assurance courses (Lego is a trademark of the LEGO Group. Here, we use it only to represent the pieces of a construction set.). Our approach applies the pedagogical methods learned from toy construction sets by…

  12. The LEGO bric system under reconstruction

    DEFF Research Database (Denmark)

    Jørgensen, Ulrik

    1998-01-01

    The new LEGO brick concept including 'intelligent' bricks and microcomputers is analysed in the line of path dependency and incriptions of patterns of use.......The new LEGO brick concept including 'intelligent' bricks and microcomputers is analysed in the line of path dependency and incriptions of patterns of use....

  13. LEGO mindstorm masterpieces building and programming advanced robots

    CERN Document Server

    2003-01-01

    In LEGO Mindstorm Masterpieces, some of the world's leading LEGO Mindstorms inventors share their knowledge and development secrets. The unique style of this book will allow it to cover an incredibly broad range of topics in unparalleled detail. Chapters within the book will include detailed discussions of the mechanics that drive the robot - and also provide step-by-step construction diagrams for each of the robots. This is perfect book for LEGO hobbyists looking to take their skills to the next level whether they build world-class competitive robots or just like to mess around for the fun of it.For experienced users of LEGO Mindstorms, LEGO Mindstorms Masterpiece is composed of three fundamental sections:·Part One: A review of the advanced robot building concepts and theories.·Part Two: Step-by-step building instructions for a series of complex models. The companion programming code is included, along with in-depth explanations of concepts needed for the specific models. Robots include Line Followers, Bip...

  14. LEGO Robotics: An Authentic Problem Solving Tool?

    Science.gov (United States)

    Castledine, Alanah-Rei; Chalmers, Chris

    2011-01-01

    With the current curriculum focus on correlating classroom problem solving lessons to real-world contexts, are LEGO robotics an effective problem solving tool? This present study was designed to investigate this question and to ascertain what problem solving strategies primary students engaged with when working with LEGO robotics and whether the…

  15. On the asymptotic enumeration of LEGO structures

    DEFF Research Database (Denmark)

    Abrahamsen, Mikkel; Eilers, Søren

    2011-01-01

    We investigate experimentally the growth regimes of the number of LEGO structures that can be constructed contiguously from n blocks of equal shape and color.......We investigate experimentally the growth regimes of the number of LEGO structures that can be constructed contiguously from n blocks of equal shape and color....

  16. Modular Lego-Electronics

    KAUST Repository

    Shaikh, Sohail F.; Ghoneim, Mohamed T.; Bahabry, Rabab R.; Khan, Sherjeel M.; Hussain, Muhammad Mustafa

    2017-01-01

    . Here, a generic manufacturable method of converting state-of-the-art complementary metal oxide semiconductor-based ICs into modular Lego-electronics is shown with unique geometry that is physically identifiable to ease manufacturing and enhance

  17. LEGO Diorama Images

    Data.gov (United States)

    Allegheny County / City of Pittsburgh / Western PA Regional Data Center — We often create dioramas from LEGO bricks for use with our presentations, blogs, and social media posts. We find it's much more fun and effective to reenact...

  18. Lego Robotics: STEM Sport of the Mind

    Science.gov (United States)

    Gura, Mark

    2012-01-01

    Lego robotics is engaging, hands-on, and encompasses every one of the NETS for Students. It also inspires a love of science, technology, engineering, and mathematics (STEM) and provides the experience students need to use digital age skills in the real world. In this article, the author discusses how schools get involved with Lego Robotics and…

  19. A Lego version of ATLAS

    CERN Multimedia

    Laëtitia Pedroso

    2010-01-01

    There's nothing very unusual about a small child making simple objects out of Lego. But wouldn't you be surprised to learn that one six-year old has just made a life-like model of the ATLAS detector?   Bastian with his Lego ATLAS detector. © Photo provided by Kai Nicklas, Bastian's father. It all began a month ago when the boy's father was watching a video about the construction of the ATLAS detector on the Internet. He hadn't noticed that his son was watching it over his shoulder. The small boy was fascinated by what he was seeing on the computer screen and his first reaction was to exclaim: "Wow! That's a terrific machine! I think the people who built it must be really clever." The detector must have really fired his imagination because, after asking his father a few questions, he decided to make a Lego model of it. Look at the photo and you will see how closely the model he produced resembles the actual ATLAS detector. Is the little boy in question, Bastia...

  20. Nuclear reactor engineering: Reactor design basics. Fourth edition, Volume One

    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 design and operation of nuclear power plants. Extensively updated, the fourth edition includes new material on reactor safety and risk analysis, regulation, fuel management, waste management, and operational aspects of nuclear power. This volume contains the following: energy from nuclear fission; nuclear reactions and radiations; neutron transport; nuclear design basics; nuclear reactor kinetics and control; radiation protection and shielding; and reactor materials

  1. LEGO Koncern 2000 - 2003 - en årsagsanalyse

    OpenAIRE

    Rosenberg, Morten; Özbudak, Devrim; Møller, Mads; Herneth, Daniel

    2006-01-01

    Denne rapport omhandler LEGO Koncernens økonomiske krise i årene 2000-2003. Vores videnskabsteoretiske er Kritisk realisme og vi bruger i projektet; en regnskabsanalyse, komparativ rapport og en PEST-analyse Denne rapport omhandler LEGO Koncernens økonomiske krise i årene 2000-2003. Vores videnskabsteoretiske er Kritisk realisme og vi bruger i projektet; en regnskabsanalyse, komparativ rapport og en PEST-analyse

  2. Lego Group: An Outsourcing Journey

    DEFF Research Database (Denmark)

    Larsen, Marcus Møller; Pedersen, Torben; Slepniov, Dmitrij

    2010-01-01

    The last years’ rather adventurous journey from 2004 to 2009 had taught the fifth-largest toy-maker in the world - the LEGO Group - the importance of managing the global supply chain effectively. In order to survive the largest internal financial crisis in its roughly 70 years of existence......, the management had, among many initiatives, decided to offshore and outsource a major chunk of its production to Flextronics. In this pursuit of rapid cost-cutting sourcing advantages, the LEGO Group planned to license out as much as 80 per cent of its production besides closing down major parts...

  3. Using LEGO for learning fractions, supporting or distracting?

    Science.gov (United States)

    Rejeki, Sri; Setyaningsih, Nining; Toyib, Muhamad

    2017-05-01

    The role of games used for learning mathematics is still in debate. However, many research revealed that it gave positive effects on both students' motivation and performance in mathematics. Therefore, this study aims at investigating the effects of using LEGO-as one of games which students are familiar with, for learning mathematics, on both students' conceptual knowledge of fractions and students' attitude in learning mathematics. A set of learning activities consisting three meetings of fractions learning was designed for this study. The activities were mainly about solving word-context problems using LEGO as the model. Thirty students of seven grade with high-ability in mathematics and thirty two students with low-ability in mathematics were involved in this study. The data were collected through students' written works, video registration and field notes during the teaching and learning activities. The results indicate that in general the use of LEGO in learning activities support the conceptual understanding on fractions for both students with high-ability and low-ability in mathematics. Moreover, for students with low-ability in mathematics, it promotes the computational skill of fractions operation. The evidences also suggest that bringing LEGO into classroom activities improve students' motivation and engagement. However, in some cases, students were more focus on playing than learning. Therefore, teachers play important roles on providing clear pedagogical instructions about the way to use LEGO properly.

  4. MIT pebble bed reactor project

    Energy Technology Data Exchange (ETDEWEB)

    Kadak, Andrew C. [Massachusetts Institute of Technology, Cambridge (United States)

    2007-03-15

    The conceptual design of the MIT modular pebble bed reactor is described. This reactor plant is a 250 Mwth, 120 Mwe indirect cycle plant that is designed to be deployed in the near term using demonstrated helium system components. The primary system is a conventional pebble bed reactor with a dynamic central column with an outlet temperature of 900 C providing helium to an intermediate helium to helium heat exchanger (IHX). The outlet of the IHX is input to a three shaft horizontal Brayton Cycle power conversion system. The design constraint used in sizing the plant is based on a factory modularity principle which allows the plant to be assembled 'Lego' style instead of constructed piece by piece. This principle employs space frames which contain the power conversion system that permits the Lego-like modules to be shipped by truck or train to sites. This paper also describes the research that has been conducted at MIT since 1998 on fuel modeling, silver leakage from coated fuel particles, dynamic simulation, MCNP reactor physics modeling and air ingress analysis.

  5. MIT pebble bed reactor project

    International Nuclear Information System (INIS)

    Kadak, Andrew C.

    2007-01-01

    The conceptual design of the MIT modular pebble bed reactor is described. This reactor plant is a 250 Mwth, 120 Mwe indirect cycle plant that is designed to be deployed in the near term using demonstrated helium system components. The primary system is a conventional pebble bed reactor with a dynamic central column with an outlet temperature of 900 C providing helium to an intermediate helium to helium heat exchanger (IHX). The outlet of the IHX is input to a three shaft horizontal Brayton Cycle power conversion system. The design constraint used in sizing the plant is based on a factory modularity principle which allows the plant to be assembled 'Lego' style instead of constructed piece by piece. This principle employs space frames which contain the power conversion system that permits the Lego-like modules to be shipped by truck or train to sites. This paper also describes the research that has been conducted at MIT since 1998 on fuel modeling, silver leakage from coated fuel particles, dynamic simulation, MCNP reactor physics modeling and air ingress analysis

  6. Orthognathic model surgery with LEGO key-spacer.

    Science.gov (United States)

    Tsang, Alfred Chee-Ching; Lee, Alfred Siu Hong; Li, Wai Keung

    2013-12-01

    A new technique of model surgery using LEGO plates as key-spacers is described. This technique requires less time to set up compared with the conventional plaster model method. It also retains the preoperative setup with the same set of models. Movement of the segments can be measured and examined in detail with LEGO key-spacers. Copyright © 2013 American Association of Oral and Maxillofacial Surgeons. Published by Elsevier Inc. All rights reserved.

  7. IMPLEMENTASI ALGORITMA BREADTH FIRST SEARCH DAN OBSTACLE DETECTION DALAM PENELUSURAN LABIRIN DINAMIS MENGGUNAKAN ROBOT LEGO

    Directory of Open Access Journals (Sweden)

    Adi Wibowo

    2012-05-01

    Full Text Available Dewasa ini perkembangan teknologi di dunia robot edukasi berkembang pesat. Robot-robot edukasi ini sering digunakan dalam riset penelitian karena kemudahan-kemudahan yang diberikannya dari segi perangkat keras. Salah satu contoh robot edukasi adalah robot LEGO Mindstorms NXT. Pada penelitian ini robot LEGO dibangun dalam bentuk robot line follower. Robot ini mampu menelusuri dan mencari jalan keluar dari labirin dinamis. Dalam menelusuri dan mencari jalan keluar, robot LEGO menggunakan algoritma Breadth First Search dan Manhattan Distance dalam memutuskan jalan mana yang harus diambil. Ketika menemui objek halangan, robot LEGO akan mengenali dan menghindari objek halangan tersebut dengan algoritma Obstacle Detection yang dimilikinya. Hasil implementasi membuktikan bahwa algoritma penelusuran labirin dinamis ini dapat diimplementasikan pada robot LEGO meskipun terdapat banyak keterbatasan dalam robot LEGO. Nowadays, the development of technology in educational robots is rapidly evolving. Educational robots are often used in research studies because they provide convenience in terms of hardware. One example is the educational robot LEGO Mindstorms NXT robot. In this research, LEGO robots built in the form of line follower robot. Robot is able to browse and find a way out of the dynamic labyrinth. In track and find a way out, LEGO robot uses an algorithm Breadth First Search and Manhattan Distance in deciding which path to take. When encountering an obstacle object, LEGO robot will recognize and avoid that obstacle objects with Obstacle Detection algorithm. The results prove that the implementation of a dynamic maze search algorithm can be implemented on a LEGO robot even though there are many limitations in LEGO robot.

  8. Konstruksi Genre Dalam Film “the Lego Movie”

    OpenAIRE

    Natalia, Vivi

    2014-01-01

    “The Lego Movie” adalah film animasi dari produsen film Warner Bros yang menceritakan kehidupan dan petualangan Emmet, seorang konstruksi bangunan yang salah terdeteksi sebagai orang spesial yang mampu menyelesaikan masalah dunia. Film ini adalah sebuah film yang membawa konvensi-konvensi genre yang berbeda dibanding film-film animasi lainnya. Peneliti melakukan analisis genre terhadap film “The Lego Movie” menggunakan 6 elemen menurut Jane Stoke, yaitu setting, lokasi, peristiwa naratif, plo...

  9. Long-term outcome of social skills intervention based on interactive LEGO play.

    Science.gov (United States)

    Legoff, Daniel B; Sherman, Michael

    2006-07-01

    LEGO building materials have been adapted as a therapeutic modality for increasing motivation to participate in social skills intervention, and providing a medium through which children with social and communication handicaps can effectively interact. A 3 year retrospective study of long-term outcome for autistic spectrum children participating in LEGO therapy (N = 60) compared Vineland Adaptive Behavior Scale socialization domain (VABS-SD) and Gilliam Autism Rating Scale social interaction subscale (GARS-SI) scores preand post-treatment with a matched comparison sample (N = 57) who received comparable non-LEGO therapy. Although both groups made significant gains on the two outcome measures, LEGO participants improved significantly more than the comparison subjects. Diagnosis and pre-treatment full-scale IQ scores did not predict outcome scores; however, Vineland adaptive behavior composite, Vineland communication domain, and verbal IQ all predicted outcome on the VABS-SD, especially for the LEGO therapy group. Results are discussed in terms of implications for methods of social skills intervention for autistic spectrum disorders.

  10. Learning with LEGO

    Science.gov (United States)

    Durrani, Matin

    2017-12-01

    I have lost count of the number of wheezes to get people hooked on particle physics. There have been straightforward scientific accounts, personal tales of discovery, books filled with cartoons, essays and even historical vignettes. In Particle Physics Brick by Brick, science communicator Ben Still has decided to use LEGO bricks to coax readers into learning more about the subatomic world.

  11. LEGO-inspired drug design

    DEFF Research Database (Denmark)

    Thanh Tung, Truong; Dao, Trong Tuan; Grifell Junyent, Marta

    2018-01-01

    The fungal plasma membrane H+-ATPase (Pma1p) is a potential target for the discovery of new antifungal agents. Surprisingly, no structure-activity relationship studies for small molecules targeting Pma1p have been reported. Herein, we disclose a LEGO-inspired fragment assembly strategy for design...

  12. Anmeldelse af Eigil Lego Andersen: Dirigent og generalforsamling

    DEFF Research Database (Denmark)

    Werlauff, Erik

    2011-01-01

    Artiklen er en anmeldelse af advokat, adj. professor, dr. jur. Eigil Lego Andersens juridiske monografi om dirigenten og generalforsamlingen, herunder med lancering af en række nye afstemningsmetoder til brug for generalforsamlingen i (større) aktieselskaber.......Artiklen er en anmeldelse af advokat, adj. professor, dr. jur. Eigil Lego Andersens juridiske monografi om dirigenten og generalforsamlingen, herunder med lancering af en række nye afstemningsmetoder til brug for generalforsamlingen i (større) aktieselskaber....

  13. Control Systems Lab Using a LEGO Mindstorms NXT Motor System

    Science.gov (United States)

    Kim, Y.

    2011-01-01

    This paper introduces a low-cost LEGO Mindstorms NXT motor system for teaching classical and modern control theories in standard third-year undergraduate courses. The LEGO motor system can be used in conjunction with MATLAB, Simulink, and several necessary toolboxes to demonstrate: 1) a modeling technique; 2) proportional-integral-differential…

  14. Supramolecular Lego assembly towards three-dimensional multi-responsive hydrogels.

    Science.gov (United States)

    Ma, Chunxin; Li, Tiefeng; Zhao, Qian; Yang, Xuxu; Wu, Jingjun; Luo, Yingwu; Xie, Tao

    2014-08-27

    Inspired by the assembly of Lego toys, hydrogel building blocks with heterogeneous responsiveness are assembled utilizing macroscopic supramolecular recognition as the adhesion force. The Lego hydrogel provides 3D transformation upon pH variation. After disassembly of the building blocks by changing the oxidation state, they can be re-assembled into a completely new shape. © 2014 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  15. LEGO Dimensions meets Doctor Who: Transbranding and New Dimensions of Transmedia Storytelling?

    Directory of Open Access Journals (Sweden)

    Matt Hills

    2016-01-01

    Full Text Available This article explores how the ‘toys-to-life’ videogame LEGO Dimensions (WarnerBros. Interactive Entertainment/Traveller’s Tales/The LEGO Group, 2015 mashes upmany different franchise storyworlds and brands. Specifically, I focus on how DoctorWho (BBC, 1963—, the British TV science fiction series, is licensed and transmediallyengaged with in Dimensions. I consider how the transbranding of LEGO Dimensionsappears to co-opt children’s “transgressive play” (Nørgård and Toft-Nielsen, 2014by combining intellectual properties, but actually continues to operate according tologics of shared corporate ownership where many of the combined storyworlds areultimately owned by Time Warner (placing Dimensions in competition with Disney’sown ‘toys-to-life’ game. Considering what value might accrue to the brand of DoctorWho by participating in LEGO Dimensions, I identify this as a particular example of“What If?” transmedia (Mittell, 2015, arguing that LEGO Dimensions’ Doctor Whonevertheless fluctuates in terms of its brand (inauthenticity. The Starter Pack remainscloser to LEGO Games’/Traveller’s Tales’ established format, subordinating Who, whilstthe separate Level Pack engages more precisely with Doctor Who’s history, albeit stilldisplaying some notable divergences from the TV series (Booth, 2015. Although LEGODimensions challenges influential theories of transmedia storytelling (Jenkins, 2006;Aldred, 2014, its transbranding and child/adult targeting accord with established approachesto transmedia licensing (Santo 2015 and fan-consumer socialization (Kinder1991.

  16. Listening and Legos[TM

    Science.gov (United States)

    Morris, Pamela

    2012-01-01

    This simple exercise, performed in teams, gives students practice in listening to instructions, particularly when there are restrictions for the communication. The teams compete in a limited amount of time to build a Lego[TM] structure based on the instructions of one team member. Which team listens the best and is most successful?

  17. Basic conceptions for reactor pressure vessel manipulators and their evaluation

    International Nuclear Information System (INIS)

    Popp, P.

    1987-01-01

    The study deals with application fields and basic design conceptions of manipulators in reactor pressure vessels as well as their evaluation. It is shown that manipulators supported at the reactor flange have essential advantages

  18. FIRST LEGO League Kickoff

    Science.gov (United States)

    2007-01-01

    Randall Hicks (right), Jacobs Technology's Education Services manager at NASA John C. Stennis Space Center, answers questions about the playing field for FIRST (For Inspiration and Recognition of Science and Technology) LEGO League's 2007 Challenge, `Power Puzzle.' More than 140 teachers, mentors, parents and students from 15 schools attended the Sept. 15 FLL season kickoff at StenniSphere, the visitor center at SSC. The teams from southern and central Mississippi and Mobile, Ala., who came to SSC heard rules for and asked questions about `Power Puzzle,' and saw robot demonstrations by Gulfport and Picayune high schools' past FIRST Robotics competitions. Using LEGO Mindstorms NXT kits, FLL teams of children ages 9-14 will spend the next three months building and programming robots to perform 'Power Puzzle's' challenge tasks, then pit them in competitions. They also will submit a research project about how energy choices impact the environment and the economy. The season will culminate at the Mississippi Championship Tournament on Dec. 8 at the Mississippi Gulf Coast Community College. FLL, considered the `little league' of the FIRST Robotics Competition, partners FIRST and the LEGO Group. Competitions aim to inspire and celebrate science and technology using real-world context and hands-on experimentation. NASA recognizes FIRST activities as an excellent hands-on method to increase student knowledge of science, engineering, technology and mathematics. Schools represented in this year's kickoff were: Madison Avenue Upper Elementary, the Mississippi Band of Choctaw Indians' Conehatta Elementary, Hattiesburg's Lillie Burney Elementary, Pearl Upper Elementary, Long Beach Middle, Oktibehha Elementary, d'Iberville Middle, Saucier's West Wortham Middle, Picayune's Nicholson Elementary and Roseland Park Baptist Church Academy, Bay St. Louis' St. Stanislaus College and Mobile's Davidson High, as well as two home-school groups from the Jackson area.

  19. Basic safety principles of KLT-40C reactor plants

    International Nuclear Information System (INIS)

    Beliaev, V.; Polunichev, V.

    2000-01-01

    The KLT-40 NSSS has been developed for a floating power block of a nuclear heat and power station on the basis of ice-breaker-type NSSS (Nuclear Steam Supply System) with application of shipbuilding technologies. Basic reactor plant components are pressurised water reactor, once-through coil-type steam generator, primary coolant pump, emergency protection rod drive mechanisms of compensate group-electromechanical type. Basic RP components are incorporated in a compact steam generating block which is arranged within metal-water shielding tank's caissons. Domestic regulatory documents on safety were used for the NSSS design. IAEA recommendations were also taken into account. Implementation of basic safety principles adopted presently for nuclear power allowed application of the KLT-40C plant for a floating power unit of a nuclear co-generation station. (author)

  20. Innovation management based on proactive engagement of customers: A case study on LEGO Group. Part I: Innovation Management at Lego Group

    Science.gov (United States)

    Rusu, G.; Avasilcăi, S.

    2015-11-01

    Customers' proactive engagement in the innovation process represents a business priority for companies which adopt the open innovation business model. In such a context, it is of outmost importance for companies to use the online environment and social media, in order to create an interactive and open dialogue with customers and other important external stakeholders, achieving to gather creative solutions and innovative ideas by involving them in the process of co-creating value. Thus, the current paper is based on a case study approach, which aims to highlight the open innovation business model of the LEGO Group, one of the most successful and active company in engaging customers in submitting ideas and creative solutions for developing new products and new technologies, through online platforms. The study then proceeds to analyze the innovation management at LEGO Group, emphasizing the most important elements regarding the management team, the success and failures, the evolution of the LEGO products focusing on the innovation efforts of the company, its mission, vision, and values, emphasizing the innovation terms which guide the actions and objectives of the LEGO Group. Also, the research based on the case study approach, outlines the most important policies and strategies of the company, the organizational structure consisting of flat structures which facilitate the orientation of the team management on the innovation process and the proactive involvement of consumers and other external stakeholders in product development, highlighting also the most important activities developed by the management team in exploring the new opportunities which may occur on the market, involving customers in sharing their ideas at festivals, participating to discussions of adult fans on web-based platforms and establishing partnerships with the external stakeholders in order to create value. Moreover, the paper is focused on identifying the company's concerns regarding the

  1. Alle ønsker sig en Lego-aktie til jul

    DEFF Research Database (Denmark)

    Iversen, Martin Jes

    2014-01-01

    Både små og store investorer får julelys i øjnene ved tanken om at eje et stykke af Lego. På sigt kunne en børsnotering gøre Danmark til et rigere land.......Både små og store investorer får julelys i øjnene ved tanken om at eje et stykke af Lego. På sigt kunne en børsnotering gøre Danmark til et rigere land....

  2. Basic concept of common reactor physics code systems. Final report of working party on common reactor physics code systems (CCS)

    International Nuclear Information System (INIS)

    2004-03-01

    A working party was organized for two years (2001-2002) on common reactor physics code systems under the Research Committee on Reactor Physics of JAERI. This final report is compilation of activity of the working party on common reactor physics code systems during two years. Objectives of the working party is to clarify basic concept of common reactor physics code systems to improve convenience of reactor physics code systems for reactor physics researchers in Japan on their various field of research and development activities. We have held four meetings during 2 years, investigated status of reactor physics code systems and innovative software technologies, and discussed basic concept of common reactor physics code systems. (author)

  3. Using LEGO Blocks for Technology-Mediated Task-Based English Language Learning

    Science.gov (United States)

    Gadomska, Agnieszka

    2015-01-01

    LEGO blocks have been played with by generations of children worldwide since the 1950s. It is undeniable that they boost creativity, eye-hand coordination, focus, planning, problem solving and many other skills. LEGO bricks have been also used by educators across the curricula as they are extremely motivating and engaging and, in effect, make…

  4. Using a Lego-based communications simulation to introduce medical students to patient-centered interviewing.

    Science.gov (United States)

    Harding, S R; D'Eon, M F

    2001-01-01

    Teaching patient-centered interviewing skills to medical students can be challenging. We have observed that 1st-year medical students, in particular, do not feel free to concentrate on the interviewing skills because they are preoccupied with complicated technical medical knowledge. The Lego simulation we use with our 1st-year students as part of a professional-skills course overcomes that difficulty. The Lego activity is a role play analogous to a doctor-patient interview that uses identical sets of Legos for the "doctor" and for the "patients" and a small construction that represents a patient history. With a simple questionnaire, data were collected from students at different points during instruction. Results indicate that the Lego activity was very effective in helping students learn the importance of open-ended questioning. It also was rated as highly as the very dynamic interactive part of the instructional session. The effectiveness of the Lego activity may be due to the properties of analogies.

  5. PLAYING LEGO INCREASE COGNITIVE DEVELOPMENT ON PRESCHOOL CHILD (4-5 YEARS OLD

    Directory of Open Access Journals (Sweden)

    Sri Utami

    2017-07-01

    Full Text Available Introduction: The preschool cognitive development can be stimulated with playing activity. The preschool child who stimulateless, their creativity will be checked and it can effect their cognitive development. Playing lego is one of the stimulation which give chance to the preschool child to express creativity and explorate their skill in playing construction. This research was aimed to analyze the effect of playing lego to the preschool cognitive development. Method: Quasy experimental pre post test design was used in this research. Total sample were 18 preschool child (4-5 years old. The independent variable was playing lego and the dependent variable was the cognitive development. Data were analyzed by Wilcoxon Signed Rank Test and Mann Whitney U Test with the significance α<0.05. Result: Result showed that the control group has significance level p=0.059 and the treatment group has significance level p=0.008. The result of Mann Whitney U Test showed p=0.001. Discussion: It can be concluded that playing lego can effect the preschool cognitive development in spatial factor, reasoning, memory, and perceptual speed. It can be suggested to the further research to examine the effect of playing lego to the motoric development or social development.

  6. Lego Group: An Outsourcing Journey

    DEFF Research Database (Denmark)

    Larsen, Marcus Møller; Pedersen, Torben; Slepniov, Dmitrij

    2010-01-01

    , the management had, among many initiatives, decided to offshore and outsource a major chunk of its production to Flextronics. In this pursuit of rapid cost-cutting sourcing advantages, the LEGO Group planned to license out as much as 80 per cent of its production besides closing down major parts...

  7. On the entropy of LEGO

    DEFF Research Database (Denmark)

    Durhuus, Bergfinnur; Eilers, Søren

    We propose the further study of the rate of growth of the number of contiguous buildings which may be made from n LEGO blocks of the same size and color. Specializing to blocks of dimension 2x4 we give upper and lower bounds, and speculate on the true value....

  8. A 'LEGO' Hybrid Photon Detector - assembled from standard mass-produced vacuum components

    International Nuclear Information System (INIS)

    Ferenc, Daniel; Lorenz, Eckart; Mirzoyan, Razmik

    2000-01-01

    Motivated primarily by the MAGIC atmospheric Cherenkov telescope project, we have developed a 'LEGO' Hybrid Photon Detector (HPD) comprising excellent focusing properties and protection against positive ion feedback. LEGO-HPD is supposed to be assembled from standard high vacuum components, which insures simplicity in the assembly procedure and reliability of operation

  9. A basic design of SR4 instrumentation and control system for research reactor

    International Nuclear Information System (INIS)

    Syahrudin Yusuf; M Subhan; Ikhsan Shobari; Sutomo Budihardjo

    2010-01-01

    An SR4 instrumentation and control systems of research reactor is the equipment of nuclear research reactors as power protection devices and control systems. The equipment is to monitor safety parameters and process parameters in the state of reactor shut down, start-up, and in operation at fixed power. In the engineering of Instrumentation and control systems SR4 research reactor, its basic design consists of technical specifications of the reactor protection system devices, technical specifications of the reactor power control system devices, technical specifications information system devices, and systems process termination cabling as a support system. This basic design is used as the basis for the preparation of detailed design and subsequent engineering development of instrumentation systems and control system integrated. (author)

  10. Calling all LEGO lovers! Add a mini control room to your collection

    CERN Multimedia

    Katarina Anthony

    2015-01-01

    The mini LHC Lego project launched in March (see here) now has almost 6,000 supporters - well on its way to the 10,000 votes needed for it to (hopefully!) hit store shelves. This week, the project added a new feature to its line: a mini control centre! The new LEGO Control centre, featuring operators "Kerstin" and "Marco".   The mini LHC project is the brainchild of ATLAS PhD student Nathan Readioff, who designed Lego replicas of the LHC and the ALICE, ATLAS, CMS and LHCb experiments on a micro scale. Each detector model is small enough to fit in the palm of your hand but crammed with detailed internal systems revealed by cutaway walls. Every major detector component is represented by a Lego piece. Now, Nathan has created a control centre to complement the mini LHC project. This would be an add-on feature for Lego’s consideration, should they decide to develop the accelerator into a box set. “The control centre is ...

  11. Bright bricks, dark play: On the impossibility of studying LEGO

    OpenAIRE

    Giddings, S.

    2014-01-01

    It is generally recognized that the pleasures of LEGO do not end once the instructions in a particular set have been followed and the model depicted on the box is accurately realized. Generations of children have —just as the manufacturers intended— pulled apart the pristine model and begun again, making new vehicles, environments and creatures. The new set joins the larger box of LEGO full of older bricks, and is mixed and hybridized. This hybridization has become particularly evident in rec...

  12. Implementation of Reconfigurable Manufacturing Systems, the Case of The LEGO Group

    DEFF Research Database (Denmark)

    Wang, Ying; Bilberg, Arne; Hadar, Ronen

    of reconfigurable manufacturing systems (RMS). A literature review is made to describe the advantages and core characteristics of RMS. Based on the theory, a conceptual model is developed to analyze where RMS would be most suitable and have most benefits in The LEGO Group. Finally, the conclusion is drawn based...... on the analysis through the model. Keywords: Reconfigurable Manufacturing Systems, Conceptual Model of RMS, Production of The LEGO Group...

  13. FIRST LEGO League announces State Championship winners

    Science.gov (United States)

    2007-01-01

    PEAK Home School Network Team 1832 'Techno Warriors' of Brandon sport the Champions Award they won during the Dec. 8 FIRST (For Inspiration and Recognition of Science and Technology) LEGO League 2007 Mississippi Championship Tournament.

  14. Facilities Management and Value Adding - The LEGO case

    DEFF Research Database (Denmark)

    Jensen, Per Anker; Katchamart, Akarapong

    on the management model for FM included in the European FM standards, recent theories on added value of FM and real estate and the related concept of Value Management from building projects. The paper outlines a preliminary theoretical based management concept, which is investigated, tested and discussed based...... on a case study of LEGO. Results: The study shows that the management model for FM creates a relevant starting point but also that stakeholder and relationship management is an essential aspect of Value Adding Management. The case study confirms the relevance of the basic concept and provides an important...... example of how Value Adding Management can be implemented and added value measured. Practical Implications: The concept of Value Adding Management is expected to increase the awareness of the impacts and strategic importance of FM for organisations and can be a practical tool for facilities managers...

  15. LEGO for Two-Party Secure Computation

    DEFF Research Database (Denmark)

    Nielsen, Jesper Buus; Orlandi, Claudio

    2009-01-01

    This paper continues the recent line of work of making Yao’s garbled circuit approach to two-party computation secure against an active adversary. We propose a new cut-and-choose based approach called LEGO (Large Efficient Garbled-circuit Optimization): It is specifically aimed at large circuits...

  16. Race to improve student understanding of uncertainty: Using LEGO race cars in the physics lab

    Science.gov (United States)

    Parappilly, Maria; Hassam, Christopher; Woodman, Richard J.

    2018-01-01

    Laboratories using LEGO race cars were developed for students in an introductory physics topic with a high early drop-out rate. In a 2014 pilot study, the labs were offered to improve students' confidence with experiments and laboratory skills, especially uncertainty propagation. This intervention was extended into the intro level physics topic the next year, for comparison and evaluation. Considering the pilot study, we subsequently adapted the delivery of the LEGO labs for a large Engineering Mechanics cohort. A qualitative survey of the students was taken to gain insight into their perception of the incorporation of LEGO race cars into physics labs. For Engineering, the findings show that LEGO physics was instrumental in teaching students the measurement and uncertainty, improving their lab reporting skills, and was a key factor in reducing the early attrition rate. This paper briefly recalls the results of the pilot study, and how variations in the delivery yielded better learning outcomes. A novel method is proposed for how LEGO race cars in a physics lab can help students increase their understanding of uncertainty and motivate them towards physics practicals.

  17. Liquid-handling Lego robots and experiments for STEM education and research

    OpenAIRE

    Gerber, Lukas C.; Calasanz-Kaiser, Agnes; Hyman, Luke; Voitiuk, Kateryna; Patil, Uday; Riedel-Kruse, Ingmar H.

    2017-01-01

    Liquid-handling robots have many applications for biotechnology and the life sciences, with increasing impact on everyday life. While playful robotics such as Lego Mindstorms significantly support education initiatives in mechatronics and programming, equivalent connections to the life sciences do not currently exist. To close this gap, we developed Lego-based pipetting robots that reliably handle liquid volumes from 1 ml down to the sub-μl range and that operate on standard laboratory plasti...

  18. Transforming LEGO for the Digital Economy

    DEFF Research Database (Denmark)

    Andersen, Peter; Ross, Jeanne

    2016-01-01

    processes. The goal of the new transformation is “to become a digital company.” Although the company already looked digital in 2016, management felt it had not become digital—in its products and processes. This case describes the LEGO Group’s journey to become a successful digital company....

  19. LEGO: a novel method for gene set over-representation analysis by incorporating network-based gene weights.

    Science.gov (United States)

    Dong, Xinran; Hao, Yun; Wang, Xiao; Tian, Weidong

    2016-01-11

    Pathway or gene set over-representation analysis (ORA) has become a routine task in functional genomics studies. However, currently widely used ORA tools employ statistical methods such as Fisher's exact test that reduce a pathway into a list of genes, ignoring the constitutive functional non-equivalent roles of genes and the complex gene-gene interactions. Here, we develop a novel method named LEGO (functional Link Enrichment of Gene Ontology or gene sets) that takes into consideration these two types of information by incorporating network-based gene weights in ORA analysis. In three benchmarks, LEGO achieves better performance than Fisher and three other network-based methods. To further evaluate LEGO's usefulness, we compare LEGO with five gene expression-based and three pathway topology-based methods using a benchmark of 34 disease gene expression datasets compiled by a recent publication, and show that LEGO is among the top-ranked methods in terms of both sensitivity and prioritization for detecting target KEGG pathways. In addition, we develop a cluster-and-filter approach to reduce the redundancy among the enriched gene sets, making the results more interpretable to biologists. Finally, we apply LEGO to two lists of autism genes, and identify relevant gene sets to autism that could not be found by Fisher.

  20. Programación de LEGO MindStorms bajo GNU/Linux

    OpenAIRE

    Matellán Olivera, Vicente; Heras Quirós, Pedro de las; Centeno González, José; González Barahona, Jesús

    2002-01-01

    GNU/Linux sobre un ordenador personal es la opción libre preferida por muchos desarrolladores de aplicaciones, pero también es una plataforma de desarrollo muy popular para otros sistemas, incluida la programación de robots, en particular es muy adecuada para jugar con los LEGO Mindstorms. En este artículo presentaremos las dos opciones más extendidas a la hora de programar estos juguetes: NQC y LegOS. NQC es una versión reducida de C que permite el desarrollo rápido de programas ...

  1. Color dithering methods for LEGO-like 3D printing

    Science.gov (United States)

    Sun, Pei-Li; Sie, Yuping

    2015-01-01

    Color dithering methods for LEGO-like 3D printing are proposed in this study. The first method is work for opaque color brick building. It is a modification of classic error diffusion. Many color primaries can be chosen. However, RGBYKW is recommended as its image quality is good and the number of color primary is limited. For translucent color bricks, multi-layer color building can enhance the image quality significantly. A LUT-based method is proposed to speed the dithering proceeding and make the color distribution even smoother. Simulation results show the proposed multi-layer dithering method can really improve the image quality of LEGO-like 3D printing.

  2. A Day at FIRST Lego League

    Science.gov (United States)

    McIntyre, Nancy

    2012-01-01

    This article features an after-school FIRST Lego League (FLL) program at Chaminade Middle School in Chatsworth, California, USA. The after-school FLL program feeds into the high school FIRST Robotics Competition (FRC) program wherein aspiring young engineers come to the high school team with several years of FLL experience. Through the FLL…

  3. Wave propagation in complex structures with LEGO

    NARCIS (Netherlands)

    Lancellotti, V.; Hon, de B.P.; Tijhuis, A.G.

    2012-01-01

    We present the extension of the linear embedding via Green's operators (LEGO) scheme to problems that involve elementary sources localized inside complex structures made of different dielectric media with inclusions. We show how this new feature allows solving problems of wave propagation within,

  4. Exploring New Firm Creation Out of Brand Communities: The Case of LEGO

    DEFF Research Database (Denmark)

    Hienerth, Christoph; Lettl, Christopher; Biskjaer, Michael Mose

    2011-01-01

    In the field of new product development, brand communities have attracted a great deal of attention from both academics and practitioners as a means of facilitating consumer-producer co-creation processes. In this paper, we extend the line of research on brand communities to the field...... brand community enjoys a broader range of LEGO products and services. Our findings reveal the emergence of a hybrid organizational form in which new business ideas are neither exploited solely within the boundaries of the focal producer firm, nor pursued by fully independent new firms alone. We observe...... of entrepreneurship studies by examining the conditions under which new firms emerge out of these social networks. Our empirical setting is the global LEGO brand community. As a well-known pioneering firm that is constantly experimenting with new ways of collaborating with its fan and customer base, LEGO recently...

  5. Spiral CT scanning technique in the detection of aspiration of LEGO foreign bodies.

    Science.gov (United States)

    Applegate, K E; Dardinger, J T; Lieber, M L; Herts, B R; Davros, W J; Obuchowski, N A; Maneker, A

    2001-12-01

    Radiolucent foreign bodies (FBs) such as plastic objects and toys remain difficult to identify on conventional radiographs of the neck and chest. Children may present with a variety of respiratory complaints, which may or may not be due to a FB. To determine whether radiolucent FBs such as plastic LEGOs and peanuts can be seen in the tracheobronchial tree or esophagus using low-dose spiral CT, and, if visible, to determine the optimal CT imaging technique. Multiple spiral sequences were performed while varying the CT parameters and the presence and location of FBs in either the trachea or the esophagus first on a neck phantom and then a cadaver. Sequences were rated by three radiologists blinded to the presence of a FB using a single scoring system. The LEGO was well visualized in the trachea by all three readers (both lung and soft-tissue windowing: combined sensitivity 89 %, combined specificity 89 %) and to a lesser extent in the esophagus (combined sensitivity 31 %, combined specificity 100 %). The peanut was not well visualized (combined sensitivity LEGO was 120 kV, 90 mA, 3-mm collimation, 0.75 s/revolution, and 2.0 pitch. This allowed for coverage of the cadaver tracheobronchial tree (approximately 11 cm) in about 18 s. Although statistical power was low for detecting significant differences, all three readers noted higher average confidence ratings with lung windowing among 18 LEGO-in-trachea scans. Rapid, low-dose spiral CT may be used to visualize LEGO FBs in the airway or esophagus. Peanuts were not well visualized.

  6. Elite weapons for lego fanatics build working handcuffs, body armor, batons, sunglasses, and the world's hardest hitting brick guns

    CERN Document Server

    Hüdepohl, Martin

    2015-01-01

    The last LEGO brick weapon construction book and design guide you'll ever need, Elite Weapons for LEGO Fanatics features building instructions for thirteen fully functional LEGO masterpieces, including the monstrous, 27-inch-long Dinosaur Superior, a fully automatic combat rifle that can puncture aluminum cans, and a highly detailed HK G3 brick replica. Also featuring a helmet, a baton, handcuffs, sunglasses, and a grappling hook gun, which allows you to retrieve distant objects without ever leaving your seat, Elite Weapons for LEGO Fanatics includes a chapter on how to find the LEGO pieces you need and a comic book story featuring a hero using the weapons in action. LEGO fans of all ages and skill levels will find a treasure trove of models, including: • Hammerhead Jr., a single-shot crossbow and it's big brother, the heavy-duty Hammerhead Sr. • Panzer Pod combat helmet • KlopSTOCK baton • Melody, a rubber-firing machine pistol • Nice-1, a pocket-sized pistol that packs a punch • Chinahook harpoon gun ...

  7. Particle physics brick by brick atomic and subatomic physics explained... in LEGO

    CERN Document Server

    Still, Ben

    2017-01-01

    Using LEGO (R) blocks to create a uniquely visual and clear depiction of the way our universe is put together. This is the perfect introduction to the enigmatic and fascinating world of Quantum Physics.Our story starts with the Big Bang, and along the way, the constructs and interactions within and among atoms and sub-atomic particles, and the forces that play upon them, are clearly explained, with each LEGO (R) block representing a different atomic or sub-atomic particle. The different colours and size denote what that particle is and its relationship with the other 'building blocks'.Each chapter is presented in digestible chunks, using toy building blocks to illustrate the ideas and experiments that have led to some of the biggest discoveries of the past 150 years.Soon you'll be able to construct every element in the Universe using a box of LEGO (R) and this book!

  8. LEGO, Legoland og Billund Lalandia nr. 2

    DEFF Research Database (Denmark)

    Leth Pasgaard, Jens Chr.

    2007-01-01

    kant af Ribe Amt. Ud over LEGO koncernens produktionsudflytning påvirkes Ny Billund Kommune endvidere af lukningen af Danish Crowns slagteri i Grindsted, hvor 700 arbejdspladser for nyligt blev nedlagt. Det er således forståeligt at kommunen byder nye investorer velkommen. Kommunen har potentialet til...

  9. Innovation management based on proactive engagement of customers: A case study on LEGO Group. Part II: Challenge of engaging the digital customer

    Science.gov (United States)

    Avasilcăi, S.; Rusu, G.

    2015-11-01

    To foster the development of innovative products and new technologies, nowadays companies use an open innovation system, encouraging stakeholders to contribute, using the companies’ online platforms for open innovation or social media, bringing and sharing creative solutions and ideas in order to respond to challenging needs the company directly expresses. Accordingly, the current research continues the analysis of the LEGO Group innovation efforts, aiming to provide a case study approach based on describing the most important projects and online instruments company uses to interact with customers and other external stakeholders. Thus, by analysing the experience of the company in developing projects of involving stakeholders in the innovation processes, the article emphasizes the objective of these past projects developed by LEGO Group, outlining their objectives regarding the focus on the product or process innovation, the team management and stakeholders involved in the innovation actions and the results they obtained. Moreover, the case study highlights the features of the most important online instruments LEGO Group uses at the moment for engaging LEGO fans, children, parents, and other external stakeholders in developing new LEGO sets. Thus, LEGO online instruments provide the opportunity for customers to be creative and to respond to LEGO management team challenges. Accordingly, LEGO involve customers in bringing innovative ideas for LEGO sets through LEGO Ideas instrument, which aims to engage customers in submitting projects, voting and supporting ideas and also sharing them on social media. Also, the research emphasizes the role of supporting the open dialogue and interaction with customers and other external stakeholders through LEGO.com Create & Share Galleries instrument, using their creativity to upload innovative models in the public galleries. The continuous challenges LEGO launches for their fans create a long-term connection between company and

  10. Block Party: Legos in the Library

    Science.gov (United States)

    Klebanoff, Abbe

    2009-01-01

    Toys don't belong in the library. That's probably what some people still think. But the author's library outside Philadelphia was having such a hard time attracting boys who had outgrown storytime that he and his colleagues decided to try something new. So his school started a Lego club. Since their June 2008 kickoff, they've been amazed by how…

  11. The parametric resonance—from LEGO Mindstorms to cold atoms

    Science.gov (United States)

    Kawalec, Tomasz; Sierant, Aleksandra

    2017-07-01

    We show an experimental setup based on a popular LEGO Mindstorms set, allowing us to both observe and investigate the parametric resonance phenomenon. The presented method is simple but covers a variety of student activities like embedded software development, conducting measurements, data collection and analysis. It may be used during science shows, as part of student projects and to illustrate the parametric resonance in mechanics or even quantum physics, during lectures or classes. The parametrically driven LEGO pendulum gains energy in a spectacular way, increasing its amplitude from 10° to about 100° within a few tens of seconds. We provide also a short description of a wireless absolute orientation sensor that may be used in quantitative analysis of driven or free pendulum movement.

  12. The parametric resonance—from LEGO Mindstorms to cold atoms

    International Nuclear Information System (INIS)

    Kawalec, Tomasz; Sierant, Aleksandra

    2017-01-01

    We show an experimental setup based on a popular LEGO Mindstorms set, allowing us to both observe and investigate the parametric resonance phenomenon. The presented method is simple but covers a variety of student activities like embedded software development, conducting measurements, data collection and analysis. It may be used during science shows, as part of student projects and to illustrate the parametric resonance in mechanics or even quantum physics, during lectures or classes. The parametrically driven LEGO pendulum gains energy in a spectacular way, increasing its amplitude from 10° to about 100° within a few tens of seconds. We provide also a short description of a wireless absolute orientation sensor that may be used in quantitative analysis of driven or free pendulum movement. (paper)

  13. Liquid-handling Lego robots and experiments for STEM education and research.

    Directory of Open Access Journals (Sweden)

    Lukas C Gerber

    2017-03-01

    Full Text Available Liquid-handling robots have many applications for biotechnology and the life sciences, with increasing impact on everyday life. While playful robotics such as Lego Mindstorms significantly support education initiatives in mechatronics and programming, equivalent connections to the life sciences do not currently exist. To close this gap, we developed Lego-based pipetting robots that reliably handle liquid volumes from 1 ml down to the sub-μl range and that operate on standard laboratory plasticware, such as cuvettes and multiwell plates. These robots can support a range of science and chemistry experiments for education and even research. Using standard, low-cost household consumables, programming pipetting routines, and modifying robot designs, we enabled a rich activity space. We successfully tested these activities in afterschool settings with elementary, middle, and high school students. The simplest robot can be directly built from the widely used Lego Education EV3 core set alone, and this publication includes building and experiment instructions to set the stage for dissemination and further development in education and research.

  14. Liquid-handling Lego robots and experiments for STEM education and research.

    Science.gov (United States)

    Gerber, Lukas C; Calasanz-Kaiser, Agnes; Hyman, Luke; Voitiuk, Kateryna; Patil, Uday; Riedel-Kruse, Ingmar H

    2017-03-01

    Liquid-handling robots have many applications for biotechnology and the life sciences, with increasing impact on everyday life. While playful robotics such as Lego Mindstorms significantly support education initiatives in mechatronics and programming, equivalent connections to the life sciences do not currently exist. To close this gap, we developed Lego-based pipetting robots that reliably handle liquid volumes from 1 ml down to the sub-μl range and that operate on standard laboratory plasticware, such as cuvettes and multiwell plates. These robots can support a range of science and chemistry experiments for education and even research. Using standard, low-cost household consumables, programming pipetting routines, and modifying robot designs, we enabled a rich activity space. We successfully tested these activities in afterschool settings with elementary, middle, and high school students. The simplest robot can be directly built from the widely used Lego Education EV3 core set alone, and this publication includes building and experiment instructions to set the stage for dissemination and further development in education and research.

  15. Spiral CT scanning technique in the detection of aspiration of LEGO foreign bodies

    International Nuclear Information System (INIS)

    Applegate, K.E.; Dardinger, J.T.; Herts, B.R.; Davros, W.J.; Obuchowski, N.A.; Lieber, M.L.; Maneker, A.

    2001-01-01

    Background:. Radiolucent foreign bodies (FBs) such as plastic objects and toys remain difficult to identify on conventional radiographs of the neck and chest. Children may present with a variety of respiratory complaints, which may or may not be due to a FB. Objective: To determine whether radiolucent FBs such as plastic LEGOs and peanuts can be seen in the tracheobronchial tree or esophagus using low-dose spiral CT, and, if visible, to determine the optimal CT imaging technique. Materials and methods: Multiple spiral sequences were performed while varying the CT parameters and the presence and location of FBs in either the trachea or the esophagus first on a neck phantom and then a cadaver. Sequences were rated by three radiologists blinded to the presence of a FB using a single scoring system. Results: The LEGO was well visualized in the trachea by all three readers (both lung and soft-tissue windowing: combined sensitivity 89 %, combined specificity 89 %) and to a lesser extent in the esophagus (combined sensitivity 31 %, combined specificity 100 %). The peanut was not well visualized (combined sensitivity < 35 %). The optimal technique for visualizing the LEGO was 120 kV, 90 mA, 3-mm collimation, 0.75 s/revolution, and 2.0 pitch. This allowed for coverage of the cadaver tracheobronchial tree (approximately 11 cm) in about 18 s. Although statistical power was low for detecting significant differences, all three readers noted higher average confidence ratings with lung windowing among 18 LEGO-in-trachea scans. Conclusion: Rapid, low-dose spiral CT may be used to visualize LEGO FBs in the airway or esophagus. Peanuts were not well visualized. (orig.)

  16. Lego Serious Play in Law

    Directory of Open Access Journals (Sweden)

    Frederico de Andrade Gabrich

    2016-12-01

    Full Text Available The legal education is not fully following the significant changes in society in the XXI century, and this determines significant lack of student motivation. The teaching methodologies used in legal courses continued to follow the teacher's knowledge and books, grounded in instructionism. It takes the development and application of new teaching methodologies that favor the change of the dominant mental model, systems thinking, innovation and real problems solution that motivate students for learning. The Lego Serious

  17. How LEGO Built the Foundations and Enterprise Capabilities for Digital Leadership

    DEFF Research Database (Denmark)

    El Sawy, Omar; Henrik, Amsinck; Kræmmergaard, Pernille

    2016-01-01

    We define digital leadership as doing the right things for the strategic success of digitalization for the enterprise and its business ecosystem. Digital leadership means thinking differently about business strategy, business models, the IT function, enterprise platforms, mindsets and skill sets......, and the workplace. Based on the decade-long digitalization journey and experiences of the LEGO Group, this article provides insights on building the foundations for enhancing enterprise capabilities for digital leadership. Leveraging digitalization is one of the LEGO Group’s four strategic priorities...... and is fundamental to it being a world leader in its industry...

  18. Generation NXT: Building Young Engineers with LEGOs

    Science.gov (United States)

    Karp, T.; Gale, R.; Lowe, L. A.; Medina, V.; Beutlich, E.

    2010-01-01

    This paper describes key success factors for the implementation and development of a LEGO robotics engineering outreach program for elementary school students in West Texas. The outreach program not only aims at getting young students excited about engineering but at the same time aims at improving retention rates among electrical and computer…

  19. Revision of the second basic plans of power reactor development in Power Reactor and Nuclear Fuel Development Corporation

    International Nuclear Information System (INIS)

    1978-01-01

    Revision of the second basic plans concerning power reactor development in PNC (Power Reactor and Nuclear Fuel Development Corporation) is presented. (1) Fast breeder reactors: As for the experimental fast breeder reactor, after reaching the criticality, the power is raised to 50 MW thermal output within fiscal 1978. The prototype fast breeder reactor is intended for the electric output of 200 MW -- 300 MW, using mixed plutonium/uranium oxide fuel. Along the above lines, research and development will be carried out on reactor physics, sodium technology, machinery and parts, nuclear fuel, etc. (2) Advanced thermal reactor: The prototype advanced thermal reactor, with initial fuel primarily of slightly enriched uranium and heavy water moderation and boiling water cooling, of 165 MW electric output, is brought to its normal operation by the end of fiscal 1978. Along the above lines, research and development will be carried out on reactor physics, machinery and parts, nuclear fuel, etc. (Mori, K

  20. Fast reactor knowledge preservation system: Taxonomy and basic requirements

    International Nuclear Information System (INIS)

    2008-01-01

    The IAEA has taken the initiative to coordinate efforts of Member States in the preservation of knowledge in the area of fast reactors. In the framework of this initiative, the IAEA intends to create an international database compiling information from different Member States on fast reactors through a web portal. Other activities related to this initiative are being designed to accumulate and exchange information on the fast reactor area, to facilitate access to this information by users in different countries and to assist Member States in preserving the experience gained in their countries. The purpose of this publication is to develop a taxonomy of the Fast Reactor Knowledge Preservation System (FRKPS) that will facilitate the preservation of the world's fast reactor knowledge base, to identify basic requirements of this taxonomy on the basis of the experience gained in the fast reactor area, as well as results of previous IAEA activities on fast reactor knowledge preservation. The need for such taxonomy arises from the fact that during the past 15 years there has been stagnation in the development of fast reactors in the industrialized countries that were involved, earlier, in intensive development of this area. All studies on fast reactors have been stopped in countries such as Germany, Italy, the United Kingdom and the United States of America and the only work being carried out is related to the decommissioning of fast reactors. Many specialists who were involved in the studies and development work in this area in these countries have already retired or are close to retirement. In countries such as France, Japan and the Russian Federation that are still actively pursuing the evolution of fast reactor technology, the situation is aggravated by the lack of young scientists and engineers moving into this branch of nuclear power

  1. A Test Platform for Planned Field Operations Using LEGO Mindstorms NXT

    Directory of Open Access Journals (Sweden)

    Gareth Edwards

    2013-11-01

    Full Text Available Testing agricultural operations and management practices associated with different machinery, systems and planning approaches can be both costly and time-consuming. Computer simulations of such systems are used for development and testing; however, to gain the experience of real-world performance, an intermediate step between simulation and full-scale testing should be included. In this paper, a potential common framework using the LEGO Mindstorms NXT micro-tractor platform is described in terms of its hardware and software components. The performance of the platform is demonstrated and tested in terms of its capability of supporting decision making on infield operation planning. The proposed system represents the basic measures for developing a complete test platform for field operations, where route plans, mission plans, multiple-machinery cooperation strategies and machinery coordination can be executed and tested in the laboratory.

  2. 3D printed Lego®-like modular microfluidic devices based on capillary driving.

    Science.gov (United States)

    Nie, Jing; Gao, Qing; Qiu, Jing-Jiang; Sun, Miao; Liu, An; Shao, Lei; Fu, Jian-Zhong; Zhao, Peng; He, Yong

    2018-03-12

    The field of how to rapidly assemble microfluidics with modular components continuously attracts researchers' attention, however, extra efforts must be devoted to solving the problems of leaking and aligning between individual modules. This paper presents a novel type of modular microfluidic device, driven by capillary force. There is no necessity for a strict seal or special alignment, and its open structures make it easy to integrate various stents and reactants. The key rationale for this method is to print different functional modules with a low-cost three-dimensional (3D) printer, then fill the channels with capillary materials and assemble them with plugs like Lego ® bricks. This rapidly reconstructed modular microfluidic device consists of a variety of common functional modules and other personalized modules, each module having a unified standard interface for easy assembly. As it can be printed by a desktop 3D printer, the manufacturing process is simple and efficient, with controllable regulation of the flow channel scale. Through diverse combinations of different modules, a variety of different functions can be achieved, without duplicating the manufacturing process. A single module can also be taken out for testing and analysis. What's more, combined with basic circuit components, it can serve as a low-cost Lego ® -like modular microfluidic circuits. As a proof of concept, the modular microfluidic device has been successfully demonstrated and used for stent degradation and cell cultures, revealing the potential use of this method in both chemical and biological research.

  3. Designing and implementing nervous system simulations on LEGO robots.

    Science.gov (United States)

    Blustein, Daniel; Rosenthal, Nikolai; Ayers, Joseph

    2013-05-25

    We present a method to use the commercially available LEGO Mindstorms NXT robotics platform to test systems level neuroscience hypotheses. The first step of the method is to develop a nervous system simulation of specific reflexive behaviors of an appropriate model organism; here we use the American Lobster. Exteroceptive reflexes mediated by decussating (crossing) neural connections can explain an animal's taxis towards or away from a stimulus as described by Braitenberg and are particularly well suited for investigation using the NXT platform.(1) The nervous system simulation is programmed using LabVIEW software on the LEGO Mindstorms platform. Once the nervous system is tuned properly, behavioral experiments are run on the robot and on the animal under identical environmental conditions. By controlling the sensory milieu experienced by the specimens, differences in behavioral outputs can be observed. These differences may point to specific deficiencies in the nervous system model and serve to inform the iteration of the model for the particular behavior under study. This method allows for the experimental manipulation of electronic nervous systems and serves as a way to explore neuroscience hypotheses specifically regarding the neurophysiological basis of simple innate reflexive behaviors. The LEGO Mindstorms NXT kit provides an affordable and efficient platform on which to test preliminary biomimetic robot control schemes. The approach is also well suited for the high school classroom to serve as the foundation for a hands-on inquiry-based biorobotics curriculum.

  4. History and Educational Potential of LEGO Mindstorms NXT

    Directory of Open Access Journals (Sweden)

    Memet ÜÇGÜL

    2013-01-01

    Full Text Available Abstract: Educational usage of the robotics has accelerated recently because of educational potential of robotics has been recognized by educators and popularity of international robotics tournaments. Many university and schools prepare technology and robotics related summer schools for children. LEGO Mindstorms NXT is the most popular and commonly used robotics set for educational purposes. This robot sets rooted to Seymour Papert’s LOGO studies which have much influence Instructional Technology in 1960’s. This study aims to present a literature review on educational potential of LEGO Mindstorms NXT robotics sets. Robotics mainly used in education for supporting the STEM (Science, Technology, Engineering and Mathematics education. Most of the related studies resulted with positive effects of the robotics activities in STEM education. Robotics also used in education to increase some skills of the children such as discovery learning, critical thinking and social skills.Özet - LEGO Mindstorms NXT’lerin Tarihi ve Eğitsel Potansiyeli: Robotların eğitsel amaçlarla kullanımı giderek artmaktadır. Eğitimcilerin robotların eğitsel potansiyelinin farkına varmaları ve uluslararası robot turnuvalarının popülerlik kazanmasının robotların eğitsel kullanımına katkısı büyüktür. Birçok üniversite ve okul, teknoloji ve robotlar konulu yaz kampları düzenlemektedirler. LEGO Mindstorms NXT en popüler ve en çok kullanılan eğitsel robot setleridir. Bu robot setlerinin geçmişi, Seymour Papert’in LOGO çalışmalarına dayanmaktadır. Bu çalışmaların 1960’larda eğitim teknolojisine büyük etkileri olmuştur. Bu tarama çalışmasının amacı son zamanlarda eğitimcilerin ilgisini çeken, robotların eğitsel amaçlarla kullanımına yönelik çalışmaları inceleyerek, LEGO Mindstorms NXT robot setlerinin  eğitim amaçlı kullanım potansiyellerinin belirlenmesidir. Robotlar eğitimde en çok FTMM (Fen, Teknoloji

  5. Documentation control process of Brazilian multipurpose reactor: conceptual design and basic design

    International Nuclear Information System (INIS)

    Kibrit, Eduardo; Prates, Jose Eduardo; Longo, Guilherme Carneiro; Salvetti, Tereza Cristina

    2015-01-01

    Established in the scope of Plan of Action of the Ministry of Science, Technology and Innovation (PACTI/MCTI) in 2007, the construction of the Brazilian Multipurpose Reactor (RMB) is on the way. This type of reactor has a broad spectrum of applications in the nuclear field and related technologies such as the radioisotopes used as supplies in the production of radiopharmaceuticals, with very much benefit to the Brazilian society being, therefore, the main goal of the Project. RMB Project consists of the following stages: site selection and site evaluation; design (conceptual design, basic design, detailed design and experimental design); construction (procurement, manufacturing; civil construction; electromechanical construction and assembling); commissioning; operation and decommissioning. Each stage requires adaptation of human resources for the stage schedule execution. The implementation of a project of this magnitude requires a complex project management, which covers not only technical, but also administrative areas. Licensing, financial resources, quality and document control systems, engineering are some of the areas involved in project success. The development of the conceptual and basic designs involved the participation of three main engineering companies. INTERTECHNE Consultores S.A. was in charge of conceptual and basic designs for conventional systems of buildings and infrastructure. INVAP S.E. was responsible for preparing the basic design of the reactor core and annexes. MRS Estudos Ambientais Ltda. has prepared documents for environmental licensing. This paper describes the procedures used during conceptual and basic design stages to control design documentation and flow of this documentation, involving the analysis and incorporation of comments from experts, control and storage of a volume of approximately 15,000 documents. (author)

  6. Documentation control process of Brazilian multipurpose reactor: conceptual design and basic design

    Energy Technology Data Exchange (ETDEWEB)

    Kibrit, Eduardo; Prates, Jose Eduardo; Longo, Guilherme Carneiro; Salvetti, Tereza Cristina, E-mail: ekibrit@ipen.br, E-mail: jeprates@ipen.br, E-mail: glongo@ipen.br, E-mail: salvetti@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    Established in the scope of Plan of Action of the Ministry of Science, Technology and Innovation (PACTI/MCTI) in 2007, the construction of the Brazilian Multipurpose Reactor (RMB) is on the way. This type of reactor has a broad spectrum of applications in the nuclear field and related technologies such as the radioisotopes used as supplies in the production of radiopharmaceuticals, with very much benefit to the Brazilian society being, therefore, the main goal of the Project. RMB Project consists of the following stages: site selection and site evaluation; design (conceptual design, basic design, detailed design and experimental design); construction (procurement, manufacturing; civil construction; electromechanical construction and assembling); commissioning; operation and decommissioning. Each stage requires adaptation of human resources for the stage schedule execution. The implementation of a project of this magnitude requires a complex project management, which covers not only technical, but also administrative areas. Licensing, financial resources, quality and document control systems, engineering are some of the areas involved in project success. The development of the conceptual and basic designs involved the participation of three main engineering companies. INTERTECHNE Consultores S.A. was in charge of conceptual and basic designs for conventional systems of buildings and infrastructure. INVAP S.E. was responsible for preparing the basic design of the reactor core and annexes. MRS Estudos Ambientais Ltda. has prepared documents for environmental licensing. This paper describes the procedures used during conceptual and basic design stages to control design documentation and flow of this documentation, involving the analysis and incorporation of comments from experts, control and storage of a volume of approximately 15,000 documents. (author)

  7. A LEGO Mindstorms Brewster angle microscope

    Science.gov (United States)

    Fernsler, Jonathan; Nguyen, Vincent; Wallum, Alison; Benz, Nicholas; Hamlin, Matthew; Pilgram, Jessica; Vanderpoel, Hunter; Lau, Ryan

    2017-09-01

    A Brewster Angle Microscope (BAM) built from a LEGO Mindstorms kit, additional LEGO bricks, and several standard optics components, is described. The BAM was built as part of an undergraduate senior project and was designed, calibrated, and used to image phospholipid, cholesterol, soap, and oil films on the surface of water. A BAM uses p-polarized laser light reflected off a surface at the Brewster angle, which ideally yields zero reflectivity. When a film of different refractive index is added to the surface a small amount of light is reflected, which can be imaged in a microscope camera. Films of only one molecule (approximately 1 nm) thick, a monolayer, can be observed easily in the BAM. The BAM was used in a junior-level Physical Chemistry class to observe phase transitions of a monolayer and the collapse of a monolayer deposited on the water surface in a Langmuir trough. Using a photometric calculation, students observed a change in thickness of a monolayer during a phase transition of 7 Å, which was accurate to within 1 Å of the value determined by more advanced methods. As supplementary material, we provide a detailed manual on how to build the BAM, software to control the BAM and camera, and image processing software.

  8. Scaling limits for the Lego discrepancy

    International Nuclear Information System (INIS)

    Hameren, Andre van; Kleiss, Ronald

    1999-01-01

    For the Lego discrepancy with M bins, which is equivalent with a χ 2 -statistic with M bins, we present a procedure to calculate the moment generating function of the probability distribution perturbatively if M and N, the number of uniformly and randomly distributed data points, become large. Furthermore, we present a phase diagram for various limits of the probability distribution in terms of the standardized variable if M and N become infinite

  9. Concept and basic performance of an in-pile experimental reactor for fast breeder reactors using fast driver core

    International Nuclear Information System (INIS)

    Obara, Toru; Sekimoto, Hiroshi

    1997-01-01

    The possibility of an in-pile experimental reactor for fast breeder reactors using a fast driver core is investigated. The driver core is composed of a particle bed with diluted fuel. The results of various basic analyses show that this reactor could perform as follows: (1) power peaking at the outer boundary of test core does not take place for large test core; (2) the radial power distribution in test fuel pin is expected to be the same as a real reactor; (3) the experiments with short half width pulse is possible; (4) for the ordinary MOX core, enough heating-up is possible for core damage experiments; (5) the positive effects after power burst can be seen directly. These are difficult for conventional thermal in-pile experimental reactors in large power excursion experiments. They are very attractive advantages in the in-pile experiments for fast breeder reactors. (author)

  10. MiniLEGO

    DEFF Research Database (Denmark)

    Frederiksen, Tore Kasper; Jakobsen, Thomas Pelle; Nielsen, Jesper Buus

    2013-01-01

    One of the main tools to construct secure two-party computation protocols are Yao garbled circuits. Using the cut-and-choose technique, one can get reasonably efficient Yao-based protocols with security against malicious adversaries. At TCC 2009, Nielsen and Orlandi [28] suggested to apply cut......-and-choose at the gate level, while previously cut-and-choose was applied on the circuit as a whole. This idea allows for a speed up with practical significance (in the order of the logarithm of the size of the circuit) and has become known as the “LEGO” construction. Unfortunately the construction in [28] is based...... on a specific number-theoretic assumption and requires public-key operations per gate of the circuit. The main technical contribution of this work is a new XOR-homomorphic commitment scheme based on oblivious transfer, that we use to cope with the problem of connecting the gates in the LEGO construction. Our...

  11. Basic research using the 250 KW research reactor triga in Ljubljana, Yugoslavia

    International Nuclear Information System (INIS)

    Dimic, V.

    1983-01-01

    The 25 KW Triga Mark II reactor of J. 'Stefan Institute' was commissioned on May 1966. During the last two years, it has been operated for about 4200 hr/year. According to experience gained with the reactor, most of the cost of reactor operation will be earned through isotope production for local hospitals and industries, performing low cost applied experiments and organizing training courses. The rest was provided through the Research Communities of the Republic of Slovenia. The reactor has been operated for 15 years without major problems and many basic research programmes have been performed. The research is being conducted in the following mainfields: solid state physics, neutron dosimetry, neutron radiography and autoradiography, reactor physics, examination of nuclear fuel using gamma scanning, irradiation of semiconducting materials and neutron activation analysis. (A.J)

  12. An Exploration of the Nanoworld with LEGO Bricks

    Science.gov (United States)

    Campbell, Dean J.; Miller, Josiah D.; Bannon, Stephen J.; Obermaier, Lauren M.

    2011-01-01

    LEGO bricks can be used for a number of demonstrations of chemical structures and properties, especially at the nanoscale level. These bricks can also be used to model instrumentation that probes these structures and properties. Detailed resources about many of these demonstrations are located on the extensive Web site "Exploring the Nanoworld…

  13. Lego Bricks and the Octet Rule: Molecular Models for Biochemical Pathways with Plastic, Interlocking Toy Bricks

    Science.gov (United States)

    Lin, Henry J.; Lehoang, Jennifer; Kwan, Isabel; Baghaee, Anita; Prasad, Priya; Ha-Chen, Stephanie J.; Moss, Tanesha; Woods, Jeremy D.

    2018-01-01

    The 8 studs on a 2 × 4 Lego brick conveniently represent the outer shell of electrons for carbon, nitrogen, and oxygen atoms. We used Lego bricks to model these atoms, which are then joined together to form molecules by following the Lewis octet rule. A variety of small biological molecules can be modeled in this way, such as most amino acids,…

  14. O leigo e o suporte básico de vida El lego y el soporte básico de vida Laypeople and basic life support

    Directory of Open Access Journals (Sweden)

    Aline Maino Pergola

    2009-06-01

    Full Text Available A capacitação do leigo para o atendimento precoce em situações de emergência e instituição do suporte básico de vida (SBV é fundamental para salvar vidas e prevenir seqüelas. O objetivo foi identificar o conhecimento dos leigos sobre SBV. Utililizou-se entrevista estruturada em linguagem não-técnica. A amostra compreendeu 385 sujeitos, a maioria (57,1% do sexo feminino com ensino médio completo e superior incompleto (53,7%. Verificou-se apenas 9,9% conhecem a manobra de respiração boca-a-boca; 84,2% conhecem a técnica de compressão torácica externa (CTE, e destes, 79,9% sabem sua finalidade. Apenas 14,5% sabem posicionar a vítima para realizar a CTE; 82,4% referem uma freqüência menor que 60 CTE/minuto. Por não apresentarem adequada informação e fundamentação das etapas do SBV, os leigos podem prestar atendimento incorreto à vítima de emergência, acarretando prejuízos à reanimação.La capacitación del lego para la atención precoz en situaciones de emergencia e aplicación del soporte básico de vida (SBV es fundamental para salvar vidas y prevenir secuelas. El objetivo fue identificar el conocimiento de los legos sobre SBV. Se utililizó la entrevista estructurada en un lenguague no técnico. La muestra comprendió 385 sujetos, la mayoría (57,1% del sexo femenino con enseñanza media completa y superior incompleta (53,7%; Los que conocen la maniobra de respiración boca a boca son apenas 9,9%; 84,2% conocen la técnica de compresión toráxica externa (CTE y de estos, 79,9% saben su finalidad. Apenas 14,5% saben posicionar a la víctima para realizar la CTE, 82,4% refieren una frecuencia menor que 60 CTE/minuto. Por no presentar adecuada información y fundamentos de las etapas del SBV, los legos pueden prestar una atención incorrecta a la víctima de emergencia, ocasionando perjuicios en la reanimación.Training laypeople to give first aid in emergency situations and offer basic life support (BLS is crucial

  15. METODE BERMAIN LEGO DALAM UPAYA MENUMBUHKEMBANGKAN KECERDASAN KINESTETIK PADA ANAK USIA DINI (Sudi Kasus di Lembaga Pendidikan Manusia Unggul

    Directory of Open Access Journals (Sweden)

    Fitria Yulianti Ningtyas

    2018-01-01

    Full Text Available Penelitian ini membahas tentang upaya menumbuhkembangkan kecerdasan kinestetik pada anak usia dini melalui metode bermain Lego di Lembaga Pendidikan Manusia Unggul. Melalui permainan Lego, anak yang memiliki gaya belajar kinestetik akan terstimulasi kecerdasan dan kemampuannya, terutama kecerdasan kinestetiknya. Sebab pada dasarnya, anak dengan gaya belajar kinestetik, memiliki kelebihan dalam ruang gerak serta berlebih energinya. Sehingga saat belajar, anak membutuhkan ruang yang cukup luas, serta permainan yang menantang. Penelitian ini bertujuan: 1 Untuk mengetahui dan menganalisis bagaimana langkah-langkah dalam menerapkan metode bermain Lego dalam upaya menumbuhkembangkan kecerdasan kinestetik pada anak usia dini di Lembaga Pendidikan Manusia Unggul. 2 Untuk mengetahui dan menganalisis bagaimana pelaksanaan dalam menerapkan metode bermain Lego dalam upaya menumbuhkembangkan kecerdasan kinestetik pada anak usia dini di Lembaga Manusia Unggul. 3 Untuk mengetahui dan menganalisis dampak dan hasil dari penerapan metode bermain Lego dalam upaya menumbuhkembangkan kecerdasan kinestetik pada anak usia dini di Lembaga Pendidikan Manusia Unggul. 4 Untuk mengetahui dan menganalisis apa saja faktor pendukung dan penghambat dalam menerapkan metode bermain Lego dalam upaya menumbuhkembangkan kecerdasan kinestetik pada anak usia dini di Lembaga Manusia Unggul. Penelitian ini menggunakan pendekatan kualitatif naturalistik. Ciri yang menonjol dari penelitian ini adalah cara pengamatan dan pengumpulan datanya dilakukan dalam latar/setting alamiah. Artinya tanpa memanipulasi subyek yang diteliti. Penelitian ini mencakup juga keyakinan terhadap sifat dasar dari realitas (yang diamati, hubungan antara orang yang mencoba mengetahui sesuatu (peneliti dan hal yang mereka coba ketahui (yang diteliti, peranan/pengaruh dari nilai-nilai (yang dianut peneliti dan variable-variabel lainnya yang serupa itu.Kajian data pada penelitian ini didapat dari hasil pengamatan

  16. A LEGO paradigm for virtual accelerator concept

    International Nuclear Information System (INIS)

    Andrianov, S.; Ivanov, A.; Podzyvalov, E.

    2012-01-01

    The paper considers basic features of a Virtual Accelerator concept based on LEGO paradigm. This concept involves three types of components: different mathematical models for accelerator design problems, integrated beam simulation packages (i. e. COSY, MAD, OptiM and others), and a special class of virtual feedback instruments similar to real control systems (EPICS). All of these components should inter-operate for more complete analysis of control systems and increased fault tolerance. The Virtual Accelerator is an information and computing environment which provides a framework for analysis based on these components that can be combined in different ways. Corresponding distributed computing services establish interaction between mathematical models and low level control system. The general idea of the software implementation is based on the Service-Oriented Architecture (SOA) that allows using cloud computing technology and enables remote access to the information and computing resources. The Virtual Accelerator allows a designer to combine powerful instruments for modeling beam dynamics in a friendly way including both self-developed and well-known packages. In the scope of this concept the following is also proposed: the control system identification, analysis and result verification, visualization as well as virtual feedback for beam line operation. The architecture of the Virtual Accelerator system itself and results of beam dynamics studies are presented. (authors)

  17. PENGARUH PENGGUNAAN BUKU AJAR BERBASIS STEM BERBANTUAN LEGO MINDSTORM EV3 TERHADAP PEMAHAMAN KONSEP MOMENTUM SISWA

    Directory of Open Access Journals (Sweden)

    Ratih Mega Ayu Afifah

    2017-10-01

    Full Text Available The purpose of this research is to figure out the effect of using STEM (Science, Technology, Engineering, and Mathematic based textbook that assisted by using LEGO mindstorm EV3 toward the students’s understanding of momentum subject. The design of this research that is pretest-postest group design. The Samples are composed of 12 students from experimental class and 12 students from control class. The results of this research show that the conceptual understanding of experimental class that using STEM-based textbook that assisted by using LEGO mindstorm EV3 is beter than the understanding of control class which using the conventional textbook in the ordinary class. The implication of this research is applying this textbook to measure the other cognitive dimention such as reasoning. Abstrak Tujuan penelitian ini adalah untuk mengetahui pengaruh penggunaan buku ajar berbasis STEM (Science, Technology, Engineering, dan Mathematics berbantuan LEGO mindstorm EV3 dalam pembelajaran fisika terhadap pemahaman konsep siswa pada materi momentum. Penelitian ini menggunakan desain eksperimen pretest postest group design. Sampel penelitian terdiri dari 12  siswa kelompok eksperimen dan 12 siswa kelompok kontrol. Berdasarkan hasil analisis menunjukkan bahwa pemahaman konsep kelompok siswa yang menggunakan buku ajar berbasis STEM berbantuan LEGO mindstorm EV3 secara signifikan lebih meningkat dibandingkan dengan kelompok yang menggunakan buku yang biasa digunakan di sekolah. Hasil penelitian menunjukkan bahwa penggunaan buku ajar berbasis STEM berbantuan robot LEGO mindstorm EV3 dapat meningkatkan pemahaman konsep siswa pada materi momentum. Implikasi pada penelitian ini adalah menerapkan buku ajar tersebut untuk mengukur dimensi kognitif lainnya seperti penalaran.

  18. The Lego Story: Remolding Education Policy and Practice

    Science.gov (United States)

    Pirrie, Anne

    2017-01-01

    The aim of this article is to develop a more nuanced understanding of the complex nature of learning as it relates to both the educational and social aims of education as manifested in contemporary European education policy. The article explores tensions in education policy and practice by exploring the evolution of the global brand Lego. The…

  19. Lightweight Expression of Granular Objects (LEGO) Content Modeling Using the SNOMED CT Observables Model to Represent Nursing Assessment Data.

    Science.gov (United States)

    Johnson, Christie

    2016-01-01

    This poster presentation presents a content modeling strategy using the SNOMED CT Observable Model to represent large amounts of detailed clinical data in a consistent and computable manner that can support multiple use cases. Lightweight Expression of Granular Objects (LEGOs) represent question/answer pairs on clinical data collection forms, where a question is modeled by a (usually) post-coordinated SNOMED CT expression. LEGOs transform electronic patient data into a normalized consumable, which means that the expressions can be treated as extensions of the SNOMED CT hierarchies for the purpose of performing subsumption queries and other analytics. Utilizing the LEGO approach for modeling clinical data obtained from a nursing admission assessment provides a foundation for data exchange across disparate information systems and software applications. Clinical data exchange of computable LEGO patient information enables the development of more refined data analytics, data storage and clinical decision support.

  20. Use of LEGO as a therapeutic medium for improving social competence.

    Science.gov (United States)

    LeGoff, Daniel B

    2004-10-01

    A repeated-measures, waiting list control design was used to assess efficacy of a social skills intervention for autistic spectrum children focused on individual and group LEGO play. The intervention combined aspects of behavior therapy, peer modeling and naturalistic communication strategies. Close interaction and joint attention to task play an important role in both group and individual therapy activities. The goal of treatment was to improve social competence (SC) which was construed as reflecting three components: (1) motivation to initiate social contact with peers; (2) ability to sustain interaction with peers for a period of time: and (3) overcoming autistic symptoms of aloofness and rigidity. Measures for the first two variables were based on observation of subjects in unstructured situations with peers; and the third variable was assessed using a structured rating scale, the SI subscale of the GARS. Results revealed significant improvement on all three measures at both 12 and 24 weeks with no evidence of gains during the waiting list period. No gender differences were found on outcome, and age of clients was not correlated with outcome. LEGO play appears to be a particularly effective medium for social skills intervention, and other researchers and clinicians are encouraged to attempt replication of this work, as well as to explore use of LEGO in other methodologies, or with different clinical populations.

  1. LEGO therapy and the social use of language programme: an evaluation of two social skills interventions for children with high functioning autism and Asperger Syndrome.

    Science.gov (United States)

    Owens, Gina; Granader, Yael; Humphrey, Ayla; Baron-Cohen, Simon

    2008-11-01

    LEGO therapy and the Social Use of Language Programme (SULP) were evaluated as social skills interventions for 6-11 year olds with high functioning autism and Asperger Syndrome. Children were matched on CA, IQ, and autistic symptoms before being randomly assigned to LEGO or SULP. Therapy occurred for 1 h/week over 18 weeks. A no-intervention control group was also assessed. Results showed that the LEGO therapy group improved more than the other groups on autism-specific social interaction scores (Gilliam Autism Rating Scale). Maladaptive behaviour decreased significantly more in the LEGO and SULP groups compared to the control group. There was a non-significant trend for SULP and LEGO groups to improve more than the no-intervention group in communication and socialisation skills.

  2. Enriching K-12 Science and Mathematics Education Using LEGOs

    Science.gov (United States)

    Williams, Keeshan; Igel, Irina; Poveda, Ronald; Kapila, Vikram; Iskander, Magued

    2012-01-01

    This paper presents a series of illustrative LEGO Mindstorms-based science and math activities, developed under an NSF GK-12 Fellows project, for elementary, middle, and high school grades. The activities, developed by engineering and science graduate Fellows in partnership with K-12 teachers, are grade appropriate, address pertinent learning…

  3. Build Your Own Particle Detector. Education and outreach through ATLAS LEGO models and events

    CERN Document Server

    AUTHOR|(INSPIRE)INSPIRE-00220289; The ATLAS collaboration

    2016-01-01

    To support the outreach activities of ATLAS institutes and to grasp people’s attention in science exhibitions and during public events, a very detailed model of the experiment built entirely out of LEGO bricks as well as an outreach programme using LEGO bricks to get people to think about particle detectors and involve them into a conversation about particle physics in general have been created. A large LEGO model, consisting of about 9500 pieces, has been exported to more than 55 ATLAS institutes and has been used in numerous exhibitions to explain the proportion and composition of the experiment to the public. As part of the Build Your Own Particle Detector programme (byopd.org) more than 15 events have been conducted, either involving a competition to design and build the best particle detector from a random pile of pieces or to take part in the construction of one of the large models, as part of a full day outreach event. Recently, miniature models of all four main LHC experiments, that will be used at ...

  4. LEGO bricks used as chemotactic chambers: evaluation by a computer-assisted image analysis technique.

    Science.gov (United States)

    Azzarà, A; Chimenti, M

    2004-01-01

    One of the main techniques used to explore neutrophil motility, employs micropore filters in chemotactic chambers. Many new models have been proposed, in order to perform multiple microassays in a rapid, inexpensive and reproducible way. In this work, LEGO bricks have been used as chemotactic chambers in the evaluation of neutrophil random motility and chemotaxis and compared with conventional Boyden chambers in a "time-response" experiment. Neutrophil motility throughout the filters was evaluated by means of an image-processing workstation, in which a dedicated algorithm recognizes and counts the cells in several fields and focal planes throughout the whole filter; correlates counts and depth values; performs a statistical analysis of data; calculates the true value of neutrophil migration; determines the distribution of cells; and displays the migration pattern. By this method, we found that the distances travelled by the cells in conventional chambers and in LEGO bricks were perfectly identical, both in random migration and under chemotactic conditions. Moreover, no interference with the physiological behaviour of neutrophils was detectable. In fact, the kinetics of migration was identical both in random migration (characterized by a gaussian pattern) and in chemotaxis (characterized by a typical stimulation peak, previously identified by our workstation). In conclusion, LEGO bricks are extremely precise devices. They are simple to use and allow the use of small amounts of chemoattractant solution and cell suspension, supplying by itself a triplicate test. LEGO bricks are inexpensive, fast and suitable for current diagnostic activity or for research investigations in every laboratory.

  5. The KINA neutronic module of the LEGO code for steady-state and transient PWR plant simulations

    International Nuclear Information System (INIS)

    Nicolopoulos, D.; Pollacchini, L.; Vimercati, G.; Spelta, S.

    1989-01-01

    The Automation Research Center (CRA) of ENEl has implemented some models for analyzing both incidental and operational transients in PWR power plants. For such models an axial neutron kinetics module characterized by high computational efficency with adequate results accuracy was called for. CISE has been entrusted with the task of implementing such a module named KINA and based on IQS (Improved Quasi Static) method, to be included in the library of LEGO modular code used by CRA to set up PWR power models. Moreover, The KINA module has been adapted to the neutron constants computing model developed by the EdF-SEPTEN, which has been using and improving the LEGO code for a long time in cooperation with ENEL-CRA. In this paper, after some remarks on the LEGO code, a general description of KINA neutronic module is given. The resylts of a preliminary validation activity of KINA for an EdF 1300 MWe PWR plant are also presented

  6. Another brick in the whole: estrategias de adaptación, remediación y transmediación en LEGO Batman: La Película

    Directory of Open Access Journals (Sweden)

    Sergio ALBALADEJO-ORTEGA

    2018-01-01

    Full Text Available El estreno en 2014 de La Lego Película (The Lego Movie, Phil Lord y Chris Miller supuso un importante hito en la historia de la empresa danesa LEGO, erigiendo el filme como pieza clave de la estrategia transmediática que empezaba a tomar forma en el ámbito cinematográfico. Aquel filme, en el que el personaje de Batman gozaba de un especial protagonismo, ha dado paso a un particular spin-off que, bajo el título LEGO Batman: La Película (The LEGO Batman Movie, Chris McKay, 2017, repite algunas de las fórmulas puestas en práctica en La Lego Película e introduce otras nuevas de igual o mayor interés desde un punto de vista intertextual. Este artículo se aproxima al largometraje del superhéroe de DC Comics atendiendo a las particulares estrategias de adaptación, remediación y transmediación que lleva a cabo. A través del análisis de los componentes narrativos que constituyen la propuesta del filme, así como de su puesta en relación con los presentes en los textos impresos, audiovisuales y videolúdicos pertenecientes a la franquicia LEGO Batman, se estudian las distintas estrategias que posibilitan la interconexión entre ellos y moldean el ‘macrorrelato’ (Scolari, 2009 que, de manera paradigmática, toma forma en la narrativa transmediática resultante.

  7. Maternal Experience of Lego Therapy in Families with Children with Autism Spectrum Conditions: What Is the Impact on Family Relationships?

    Science.gov (United States)

    Peckett, Helen; MacCallum, Fiona; Knibbs, Jacky

    2016-01-01

    This study aimed to explore mothers' experience of implementing Lego Therapy at home within the family. Following a Lego Therapy training session, mothers carried out hourly sessions with their child with an autism spectrum condition and the child's sibling, once a week, for 6 weeks. Mothers were interviewed following the intervention, and the…

  8. Modelamiento y programación de un juego de legos en un entorno de brealidad virtual

    OpenAIRE

    Arboleda, Freddy; Laica, Ricardo; Loor, Magdalena; García, Sixto

    2010-01-01

    This project seeks by the use of the techniques of Virtual Reality to create a virtual world of a traditional game of Lego blocks, in order to check the applicability of the concepts learned throughout the topic. The present abstract specifies the general ideas on the modeling, design and implementation of an application of Virtual Reality of Lego blocks. First, we focus in the creation of the 3D objects and scenes, which are going to constitute the virtual environment. Later, we are going t...

  9. LEGO-based Robotics in Higher Education: 15 Years of Student Creativity

    Directory of Open Access Journals (Sweden)

    Ethan Danahy

    2014-02-01

    Full Text Available Our goal in this article is to reflect on the role LEGO robotics has played in college engineering education over the last 15 years, starting with the introduction of the RCX in 1998 and ending with the introduction of the EV3 in 2013. By combining a modular computer programming language with a modular building platform, LEGO Education has allowed students (of all ages to become active leaders in their own education as they build everything from animals for a robotic zoo to robots that play children's games. Most importantly, it allows all students to develop different solutions to the same problem to provide a learning community. We look first at how the recent developments in the learning sciences can help in promoting student learning in robotics. We then share four case studies of successful college-level implementations that build on these developments.

  10. First Steps into Practical Engineering for Freshman Students Using MATLAB and LEGO Mindstorms Robots

    Directory of Open Access Journals (Sweden)

    A. Behrens

    2008-01-01

    Full Text Available Besides lectures on basic theoretical topics, contemporary teaching and learning concepts for first semester students give more and more consideration to practically motivated courses. In this context, a new first-year introductory course in practical engineering has been established in the first semester curriculum of Electrical Engineering at RWTH Aachen University, Germany. Based on a threefold learning concept, programming skills in MATLAB are taught to 309 students within a full-time block course laboratory. The students are encouraged to transfer known mathematical basics to program algorithms and real-world applications performed by 100 LEGO Mindstorms robots. A new MATLAB toolbox and twofold project tasks have been developed for this purpose by a small team of supervisors. The students are supervised by over 60 tutors at 23 institutes, and are encouraged to create their own robotics applications. We describe how the laboratory motivates the students to act and think like engineers and to solve real-world issues with limited resources. The evaluation results show that the proposed practical course concept successfully boosts students’ motivation, advances their programming skills, and encourages the peer learning process. 

  11. Long-term LEGO therapy with humanoid robot for children with ASD

    NARCIS (Netherlands)

    Barakova, E.I.; Bajracharya, P.; Willemsen, M.H.J.; Lourens, T.; Huskens, B.

    2015-01-01

    To utilise the knowledge gained from highly specialised domains as autism therapy to robot-based interactive training platforms, an innovative design approach is needed. We present the process of content creation and co-design of LEGO therapy for children with autism spectrum disorders performed by

  12. "Creative Blocs": Action Research Study on the Implementation of Lego as a Tool for Reflective Practice with Social Care Practitioners

    Science.gov (United States)

    Cavaliero, Tamsin

    2017-01-01

    The aim of this study is to investigate whether Lego could be used as a tool for reflective practice with social care practitioners (SCPs) and student practitioners. This article outlines an action research study conducted in an institute of higher education in Ireland. Findings from this study suggest that Lego can be used to support student…

  13. Lentiviral gene ontology (LeGO) vectors equipped with novel drug-selectable fluorescent proteins: new building blocks for cell marking and multi-gene analysis.

    Science.gov (United States)

    Weber, K; Mock, U; Petrowitz, B; Bartsch, U; Fehse, B

    2010-04-01

    Vector-encoded fluorescent proteins (FPs) facilitate unambiguous identification or sorting of gene-modified cells by fluorescence-activated cell sorting (FACS). Exploiting this feature, we have recently developed lentiviral gene ontology (LeGO) vectors (www.LentiGO-Vectors.de) for multi-gene analysis in different target cells. In this study, we extend the LeGO principle by introducing 10 different drug-selectable FPs created by fusing one of the five selection marker (protecting against blasticidin, hygromycin, neomycin, puromycin and zeocin) and one of the five FP genes (Cerulean, eGFP, Venus, dTomato and mCherry). All tested fusion proteins allowed both fluorescence-mediated detection and drug-mediated selection of LeGO-transduced cells. Newly generated codon-optimized hygromycin- and neomycin-resistance genes showed improved expression as compared with their ancestors. New LeGO constructs were produced at titers >10(6) per ml (for non-concentrated supernatants). We show efficient combinatorial marking and selection of various cells, including mesenchymal stem cells, simultaneously transduced with different LeGO constructs. Inclusion of the cytomegalovirus early enhancer/chicken beta-actin promoter into LeGO vectors facilitated robust transgene expression in and selection of neural stem cells and their differentiated progeny. We suppose that the new drug-selectable markers combining advantages of FACS and drug selection are well suited for numerous applications and vector systems. Their inclusion into LeGO vectors opens new possibilities for (stem) cell tracking and functional multi-gene analysis.

  14. Does Lego Training Stimulate Pupils' Ability to Solve Logical Problems?

    Science.gov (United States)

    Lindh, Jorgen; Holgersson, Thomas

    2007-01-01

    The purpose of this study is to investigate the effect of a one-year regular robotic toys (lego) training on school pupils' performance. The underlying pedagogical perspective is the "constructionist theory," where the main idea is that knowledge is constructed in the mind of the pupil by active learning. The investigation has been made…

  15. The Serious Use of Play and Metaphor: Legos and Labyrinths

    Science.gov (United States)

    James, Alison; Brookfield, Stephen

    2013-01-01

    In this paper the authors wish to examine kinesthetic forms of learning involving the body and the physical realm. The authors look at two particular techniques; using Legos to build metaphorical models and living the physical experience of metaphors in the shape of labyrinth-walking and its attendant activities. The authors begin by discussing…

  16. Towards Lego Snapping; Integration of Carbon Nanotubes and Few-Layer Graphene

    Science.gov (United States)

    Nasseri, Mohsen; Boland, Mathias; Farrokhi, M. Javad; Strachan, Douglas

    Integration of semiconducting, conducting, and insulating nanomaterials into precisely aligned complicated systems is one of the main challenges to the ultimate size scaling of electronic devices, which is a key goal in nanoscience and nanotechnology. This integration could be made more effective through controlled alignment of the crystallographic lattices of the nanoscale components. Of the vast number of materials of atomically-thin materials, two of the sp2 bonded carbon structures, graphene and carbon nanotubes, are ideal candidates for this type of application since they are built from the same backbone carbon lattice. Here we report carbon nanotube and graphene hybrid nanostructures fabricated through their catalytic synthesis and etching. The growth formations we have investigated through various high-resolution microscopy techniques provide evidence of lego-snapped interfaces between nanotubes and graphene into device-relevant orientations. We will finish with a discussion of the various size and energy regimes relevant to these lego-snapped interfaces and their implications on developing these integrated formations.

  17. A multicolor panel of novel lentiviral "gene ontology" (LeGO) vectors for functional gene analysis.

    Science.gov (United States)

    Weber, Kristoffer; Bartsch, Udo; Stocking, Carol; Fehse, Boris

    2008-04-01

    Functional gene analysis requires the possibility of overexpression, as well as downregulation of one, or ideally several, potentially interacting genes. Lentiviral vectors are well suited for this purpose as they ensure stable expression of complementary DNAs (cDNAs), as well as short-hairpin RNAs (shRNAs), and can efficiently transduce a wide spectrum of cell targets when packaged within the coat proteins of other viruses. Here we introduce a multicolor panel of novel lentiviral "gene ontology" (LeGO) vectors designed according to the "building blocks" principle. Using a wide spectrum of different fluorescent markers, including drug-selectable enhanced green fluorescent protein (eGFP)- and dTomato-blasticidin-S resistance fusion proteins, LeGO vectors allow simultaneous analysis of multiple genes and shRNAs of interest within single, easily identifiable cells. Furthermore, each functional module is flanked by unique cloning sites, ensuring flexibility and individual optimization. The efficacy of these vectors for analyzing multiple genes in a single cell was demonstrated in several different cell types, including hematopoietic, endothelial, and neural stem and progenitor cells, as well as hepatocytes. LeGO vectors thus represent a valuable tool for investigating gene networks using conditional ectopic expression and knock-down approaches simultaneously.

  18. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    Baeten, P.

    2006-01-01

    The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

  19. Jules Horowitz Reactor, basic design

    International Nuclear Information System (INIS)

    Bergamaschi, Y.; Bouilloux, Y.; Chantoin, P.; Guigon, B.; Bravo, X.; Germain, C.; Rommens, M.; Tremodeux, P.

    2003-01-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it. It has the ambition to provide the necessary nuclear data and maintain a fission research capacity in Europe after 2010. This capacity should be service-oriented. It will be established in Cadarache. The Jules Horowitz reactor will also: - represent a significant step in term of performances and experimental capabilities, - be designed with a high flexibility, in order to satisfy the current demand from European industry, research and be able to accommodate future requirements, - reach a high level of safety, according to the best current practice. This paper will present the main functionalities and the design options resulting from the 'preliminary design' studies. (authors)

  20. Jules Horowitz reactor, basic design

    International Nuclear Information System (INIS)

    Bergamaschi, Y.; Bouilloux, Y.; Chantoin, P.; Guigon, B.; Bravo, X.; Germain, C.; Rommens, M.; Tremodeux, P.

    2002-01-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it. It has the ambition to provide the necessary nuclear data and maintain a fission research capacity in Europe after 2010. This capacity should be service-oriented. It will be established in Cadarache. The Jules Horowitz reactor will also: represent a significant step in term of performances and experimental capabilities; be designed with a high flexibility, in order to satisfy the current demand from European industry, research and be able to accommodate future requirements; reach a high level of safety, according to the best current practice. This paper will present the main functionalities and the design options resulting from the 'preliminary design' studies. (author)

  1. PENERAPAN LEGO BRICKS DALAM PEMBELAJARAN SEBAGAI STRATEGI UNTUK MENINGKATKAN KECERDASAN MATEMATIS SISWA DALAM MENGHITUNG BILANGAN BERPANGKAT

    Directory of Open Access Journals (Sweden)

    Mutia Rahma Setyani

    2017-12-01

    Full Text Available Penelitian ini bertujuan untuk mengetahui hasil pembelajaran dan mendeskripsikan kecerdasan matematis siswa dalam menghitung bilangan berpangkat setelah menggunakan lego bricks pada siswa kelas III Tahassus MIS Ta’allamul Huda. Penelitian ini menggunakan Penelitian Tindakan Kelas ini dengan model pembelajaran Cooperative Learning. Subjek penelitian adalah siswa kelas III ahassus MIS a’allamul Huda yang berjumlah 24 siswa. Data dikumpulkan melalui observasi dan wawancara, selanjutnya dianalisis secara kualitatif. Hasil penelitian menunjukkan bahwa keberhasilan penerapan lego bricks pada perhitungan bilangan berpangkat meningkat pada setiap siklusnya. Pada tahap Pra Siklus, hanya 40% siswa yang lulus dalam mengerjakan soal-soal dari bilangan berpangkat, kemudian pada Siklus I berdasarkan hasil observasi didapatkan kenaikan yang signifikan yaitu 80% siswa yang lulus dalam mengerjakan soal mengenai bilangan berpangkat. Masih ada 20% siswa yang masih kesulitan dalam mengerjakan soal tersebut. Selanjutnya setelah dilakukan perbaikan, pada Siklus II didapat kenaikan yang luar biasa yaitu seluruh kelompok siswa lulus dalam mengerjakan soal mengenai bilangan berpangkat. Hal tersebut dibuktikan kembali melalui hasil post test pada tahap Pasca Siklus dimana nilai seluruh siswa berada diatas kriteria ketuntasan minimum, yaitu 85-100 sehingga penerapan lego bricks untuk meningkatkan kecerdasan matematis siswa dalam menghitung bilangan berpangkat dikatakan berhasil.

  2. Propagation of uncertainties from basic data to key parameters of nuclear reactors

    International Nuclear Information System (INIS)

    Kodeli, I.

    2010-01-01

    The author reports the development of a set of computing software (SUSD3D) and of libraries of nuclear data covariance matrices to assess sensitivities of parameters with respect to basic nuclear data, and the corresponding uncertainties, notably for radiation transport for which uncertainty has various origins: reactivity coefficients or neutron and gamma ray flows. He reports the application to fusion and fission reactors

  3. Organizational System for the LEGO WeDo 2.0 Robotics System

    Science.gov (United States)

    Dolecheck, Suzann Hagan; Ewers, Timothy

    2017-01-01

    In this article, we explain an organizational system for the new LEGO Education WeDo 2.0 Core Set used in 4-H robotics; in school enrichment, afterschool, and other youth robotics programs; and by hobbyists. The system presented is for organizing WeDo parts into a translucent parts tray that includes part names and numbers. The article provides…

  4. A Lego Mindstorms NXT based test bench for multiagent exploratory systems and distributed network partitioning

    Science.gov (United States)

    Patil, Riya Raghuvir

    Networks of communicating agents require distributed algorithms for a variety of tasks in the field of network analysis and control. For applications such as swarms of autonomous vehicles, ad hoc and wireless sensor networks, and such military and civilian applications as exploring and patrolling a robust autonomous system that uses a distributed algorithm for selfpartitioning can be significantly helpful. A single team of autonomous vehicles in a field may need to self-dissemble into multiple teams, conducive to completing multiple control tasks. Moreover, because communicating agents are subject to changes, namely, addition or failure of an agent or link, a distributed or decentralized algorithm is favorable over having a central agent. A framework to help with the study of self-partitioning of such multi agent systems that have most basic mobility model not only saves our time in conception but also gives us a cost effective prototype without negotiating the physical realization of the proposed idea. In this thesis I present my work on the implementation of a flexible and distributed stochastic partitioning algorithm on the LegoRTM Mindstorms' NXT on a graphical programming platform using National Instruments' LabVIEW(TM) forming a team of communicating agents via NXT-Bee radio module. We single out mobility, communication and self-partition as the core elements of the work. The goal is to randomly explore a precinct for reference sites. Agents who have discovered the reference sites announce their target acquisition to form a network formed based upon the distance of each agent with the other wherein the self-partitioning begins to find an optimal partition. Further, to illustrate the work, an experimental test-bench of five Lego NXT robots is presented.

  5. Expressivity in Open-ended Constructive Play: Building and Playing Musical Lego Instruments

    DEFF Research Database (Denmark)

    Jakobsen, Kasper; Stougaard, Jeppe; Petersen, Marianne Graves

    2016-01-01

    This paper presents the findings from a case study in designing for open-ended constructive play for children. The study is based on a workshop where more that 150 children in ages 3-13 built and played their own musical instruments from Lego. The children used different sensors for playing...

  6. The educational affordances of Lego-based play in primary school

    Directory of Open Access Journals (Sweden)

    Luisa Salmaso

    2013-12-01

    Full Text Available Questo articolo presenta un’esperienza didattica attuata in una classe prima e in una classe seconda della Scuola Primaria mediante l’utilizzo di mattoncini Lego. Al termine di questo percorso è stato possibile delineare alcuni elementi utili per sostenere l’efficacia del gioco a favore dello sviluppo delle abilità visuo-spaziali e di pianificazione, anche in una prospettiva inclusiva e di pari opportunità di genere.

  7. Basic experiments of reactor physics using the critical assembly TCA

    International Nuclear Information System (INIS)

    Obara, Toru; Igashira, Masayuki; Sekimoto, Hiroshi; Nakajima, Ken; Suzaki, Takenori.

    1994-02-01

    This report is based on lectures given to graduate students of Tokyo Institute of Technology. It covers educational experiments conducted with the Tank-Type Critical Assembly (TCA) at Japan Atomic Energy Research Institute in July, 1993. During this period, the following basic experiments on reactor physics were performed: (1) Critical approach experiment, (2) Measurement of neutron flux distribution, (3) Measurement of power distribution, (4) Measurement of fuel rod worth distribution, (5) Measurement of safety sheet worth by the rod drop method. The principle of experiments, experimental procedure, and analysis of results are described in this report. (author)

  8. Fast generation of macro basis functions for LEGO through the adaptive cross approximation

    NARCIS (Netherlands)

    Lancellotti, V.

    2015-01-01

    We present a method for the fast generation of macro basis functions in the context of the linear embedding via Green's operators approach (LEGO) which is a domain decomposition technique based on the combination of electromagnetic bricks in turn described by means of scattering operators. We show

  9. ‘Everything is awesome’ : The LEGO movie and the affective politics of security

    NARCIS (Netherlands)

    Goggin, J.

    2017-01-01

    Scholarship on the finance-security nexus has typically been concerned with ‘first order’ phenomena, such as the interpenetration of the finance and security sectors. This article contributes to the debate by turning to an apparent epiphenomenon, namely The LEGO Movie, and using it to address some

  10. Test reactor: basic to U.S. breeder reactor development

    International Nuclear Information System (INIS)

    Miller, B.J.; Harness, A.J.

    1975-01-01

    Long-range energy planning in the U. S. includes development of a national commercial breeder reactor program. U. S. development of the LMFBR is following a conservative sequence of extensive technology development through use of test reactors and demonstration plants prior to construction of commercial plants. Because materials and fuel technology development is considered the first vital step in this sequence, initial U. S. efforts have been directed to the design and construction of a unique test reactor. The Fast Flux Test Facility, FFTF, is a 400 MW(t) reactor with driver fuel locations, open test locations, and closed loops for higher risk experiments. The FFTF will provide a prototypic LMFBR core environment with sufficient instrumentation for detailed core environmental characterization and a testing capability substituted for breeder capability. The unique comprehensive fuel and materials testing capability of the FFTF will be key to achieving long-range objectives of increased power density, improved breeding gain and shorter doubling times. (auth)

  11. Culture's building blocks: investigating cultural evolution in a LEGO construction task.

    Science.gov (United States)

    McGraw, John J; Wallot, Sebastian; Mitkidis, Panagiotis; Roepstorff, Andreas

    2014-01-01

    ONE OF THE MOST ESSENTIAL BUT THEORETICALLY VEXING ISSUES REGARDING THE NOTION OF CULTURE IS THAT OF CULTURAL EVOLUTION AND TRANSMISSION: how a group's accumulated solutions to invariant challenges develop and persevere over time. But at the moment, the notion of applying evolutionary theory to culture remains little more than a suggestive trope. Whereas the modern synthesis of evolutionary theory has provided an encompassing scientific framework for the selection and transmission of biological adaptations, a convincing theory of cultural evolution has yet to emerge. One of the greatest challenges for theorists is identifying the appropriate time scales and units of analysis in order to reduce the intractably large and complex phenomenon of "culture" into its component "building blocks." In this paper, we present a model for scientifically investigating cultural processes by analyzing the ways people develop conventions in a series of LEGO construction tasks. The data revealed a surprising pattern in the selection of building bricks as well as features of car design across consecutive building sessions. Our findings support a novel methodology for studying the development and transmission of culture through the microcosm of interactive LEGO design and assembly.

  12. A line follower robot implementation using Lego's Mindstorms Kit and Q-Learning

    Directory of Open Access Journals (Sweden)

    Hector-Gabriel Acosta-Mesa

    2012-03-01

    Full Text Available Un problema común al trabajar con robots móviles es que la fase de programación puede ser un proceso largo, costoso y difícil para los programadores. Los Algoritmos de Aprendizaje por Refuerzo ofrecen uno de los marcos de trabajo más generales en el ámbito de aprendizaje de máquina. Este trabajo presenta un enfoque usando el algoritmo de Q-Learning en un robot Lego para que aprenda "por sí mismo" a seguir una línea negra dibujada en una superficie blanca. El entorno de programación utilizado en este trabajo es Matlab.A common problem working with mobile robots is that programming phase could be a long, expensive and heavy process for programmers. The reinforcement learning algorithms offer one of the most general frameworks in learning subjects. This work presents an approach using the Q-Learning algorithm on a Lego robot in order for it to learn by itself how to follow a blackline drawn down on a white surface, using Matlab [5] as programming environment.

  13. Teaching of Computer Science Topics Using Meta-Programming-Based GLOs and LEGO Robots

    Science.gov (United States)

    Štuikys, Vytautas; Burbaite, Renata; Damaševicius, Robertas

    2013-01-01

    The paper's contribution is a methodology that integrates two educational technologies (GLO and LEGO robot) to teach Computer Science (CS) topics at the school level. We present the methodology as a framework of 5 components (pedagogical activities, technology driven processes, tools, knowledge transfer actors, and pedagogical outcomes) and…

  14. Long-Term Outcome of Social Skills Intervention Based on Interactive LEGO[C] Play

    Science.gov (United States)

    Legoff, Daniel B.; Sherman, Michael

    2006-01-01

    LEGO[C] building materials have been adapted as a therapeutic modality for increasing motivation to participate in social skills intervention, and providing a medium through which children with social and communication handicaps can effectively interact. A 3 year retrospective study of long-term outcome for autistic spectrum children participating…

  15. Comparison of the LEGO Mindstorms NXT and EV3 Robotics Education Platforms

    Science.gov (United States)

    Sherrard, Ann; Rhodes, Amy

    2014-01-01

    The release of the latest LEGO Mindstorms EV3 robotics platform in September 2013 has provided a dilemma for many youth robotics leaders. There is a need to understand the differences in the Mindstorms NXT and EV3 in order to make future robotics purchases. In this article the differences are identified regarding software, hardware, sensors, the…

  16. Modular Lego-Electronics

    KAUST Repository

    Shaikh, Sohail F.

    2017-10-24

    Electronic system components have thousands of individual field effect transistors (FETs) interconnected executing dedicated functions. Assembly yield of >80% will guarantee system failure since a single interconnect failure will result in undesired performance. Hence, a paradigm shift is needed in the self-assembly or integration of state-of-the-art integrated circuits (ICs) for a physically compliant system. Traditionally, most ICs share same geometry with only variations in dimensions and packaging. Here, a generic manufacturable method of converting state-of-the-art complementary metal oxide semiconductor-based ICs into modular Lego-electronics is shown with unique geometry that is physically identifiable to ease manufacturing and enhance throughput. Various geometries at the backside of the silicon die and on the destination site having the same geometry with relaxed dimension (up to 50 µm extra) allow targeted site binding like DNA assembly. Different geometries, angles, and heights for different modules provide a unique identity to each of the ICs. A two-level geometric combination presented here helps in maintaining the uniqueness of individual module to assemble at exact matching site like a perfect lock-and-key model. The assembled ICs offer uncompromised electrical performance, higher yield, and fabrication ease. In future, this method can further be expanded for fluidic assisted self-assembly.

  17. Business Process Innovation: The LEGO Case

    DEFF Research Database (Denmark)

    Møller, Charles; Hansen, P.K.

    2006-01-01

    Most organizations today are required not only to establish effective business processes but they are required to accommodate for changing business conditions at an increasing rate. Many business processes extend beyond the boundary of the enterprise into the supply chain and the information...... process innovation (BPI) in future organizations. This paper explores the applicability of one particular methodology for Business Process Innovation to deal with the challenge that the LEGO organization is facing with the alignment of their product development process and their supply chain. The paper...... infrastructure therefore is critical. Today nearly every business relies on their Enterprise System (ES) for process integration and the future generations of Enterprise Systems will increasingly be driven by business process models. Consequently process modelling and improvement will become vital for business...

  18. Basic concept of fuel safety design and assessment for sodium-cooled fast reactor

    International Nuclear Information System (INIS)

    Nakae, Nobuo; Baba, Toshikazu; Kamimura, Katsuichiro

    2013-03-01

    'Philosophy in Safety Evaluation of Fast Breeder Reactors' was published as a guideline for safety design and safety evaluation of Sodium-Cooled Fast Reactor in Japan. This guideline points out that cladding creep and swelling due to internal pressure should be taken into account since the fuel is used under high temperature and high burnup, and that fuel assembly deformation and the prevention from coolant channel blockage should be taken into account in viewpoints of nuclear and thermal hydraulic design. However, the requirements including their criteria and evaluation items are not described. Two other domestic guidelines related to core design are applied for fuel design of fast reactor, but the description is considered to not be enough to practically use. In addition, technical standard for nuclear fuel used in power reactors is also applied for fuel inspection. Therefore, the technical standard and guideline for fuel design and safety evaluation are considered to be very important issue for nuclear safety regulation. This document has been developed according to the following steps: The guidelines and the technical standards, which are prepared in foreign countries and international organization, were reviewed. The technical background concerning fuel design and safety evaluation for fast reactor was collected and summarized in the world wide scale. The basic concept of fuel safety design and assessment for sodium-cooled fast reactor was developed by considering a wide range of views of the specialists in Japan. In order to discuss the content with foreign specialists IAEA Consultancy Meetings have been held on January, 2011 and January, 2012. The participants of the meeting came from USA, UK, EC, India, China and South Korea. The specialists of IAEA and JNES were also joined. Although this document is prepared for application to 'Monju'(prototype LMFR), it may be applied to experimental, demonstration and commercial types of LMFR after revising it by taking

  19. DIME Students Show Off their Lego(TM) Challenge Creation

    Science.gov (United States)

    2002-01-01

    Two students show the Lego (TM) Challenge device they designed and built to operate in the portable drop tower demonstrator as part of the second Dropping in a Microgravity Environment (DIME) competition held April 23-25, 2002, at NASA's Glenn Research Center. Competitors included two teams from Sycamore High School, Cincinnati, OH, and one each from Bay High School, Bay Village, OH, and COSI Academy, Columbus, OH. DIME is part of NASA's education and outreach activities. Details are on line at http://microgravity.grc.nasa.gov/DIME_2002.html.

  20. Introduction to autonomous mobile robotics using Lego Mindstorms NXT

    Science.gov (United States)

    Akın, H. Levent; Meriçli, Çetin; Meriçli, Tekin

    2013-12-01

    Teaching the fundamentals of robotics to computer science undergraduates requires designing a well-balanced curriculum that is complemented with hands-on applications on a platform that allows rapid construction of complex robots, and implementation of sophisticated algorithms. This paper describes such an elective introductory course where the Lego Mindstorms NXT kits are used as the robot platform. The aims, scope and contents of the course are presented, and the design of the laboratory sessions as well as the term projects, which address several core problems of robotics and artificial intelligence simultaneously, are explained in detail.

  1. The Impact of Lean Thinking on Workforce Motivation: A Success Factor at LEGO Manufacturing Ltd.

    Directory of Open Access Journals (Sweden)

    Oláh Judit

    2017-06-01

    Full Text Available Several enterprises have tried to introduce the lean approach in order to enhance competitiveness. However, the only successful ones were the companies which understood that lean is not only about methods and tools, but the people using them: employees. The only way an enterprise can become a lean organisation is if all of its members deeply identify with the organisation’s principles, which is then manifested in all decisions and actions of the organisation. The aim of this study is to present the practical use of the lean approach in the Nyíregyháza plant of LEGO. Based on the questionnaire results and our observations, we present the current situation of LEGO in accordance with the same points and compare it to an ideal situation. We then make improvement recommendations in all cases when negative changes were observed.

  2. Highly Manufacturable Deep (Sub-Millimeter) Etching Enabled High Aspect Ratio Complex Geometry Lego-Like Silicon Electronics

    KAUST Repository

    Ghoneim, Mohamed T.; Hussain, Muhammad Mustafa

    2017-01-01

    A highly manufacturable deep reactive ion etching based process involving a hybrid soft/hard mask process technology shows high aspect ratio complex geometry Lego-like silicon electronics formation enabling free-form (physically flexible

  3. Using LEGO NXT Mobile Robots with LabVIEW for Undergraduate Courses on Mechatronics

    Science.gov (United States)

    Gomez-de-Gabriel, J. M.; Mandow, A.; Fernandez-Lozano, J.; Garcia-Cerezo, A.

    2011-01-01

    The paper proposes lab work and student competitions based on the LEGO NXT Mindstorms kits and standard LabVIEW. The goal of this combination is to stimulate design and experimentation with real hardware and representative software in courses where mobile robotics is adopted as a motivating platform to introduce mechatronics competencies. Basic…

  4. Basic studies for molten-salt reactor engineering in Japan

    International Nuclear Information System (INIS)

    Ishiguro, R.; Sugiyama, K.; Sakashita, H.

    1985-01-01

    A research project of nuclear engineering for the molten-salt reactor is underway which is supported by the Grant-in-Aid for Scientific Research of the Ministry of Education of Japan. At present, the major effort is devoted only to basic engineering problems because of the limited amount of the grant. The reporters introduce these and related studies that have been carrying out in Japanese universities. Discussions on the following four subjects are summerized in this report: a) Vapour explosion when hight temperature molten-salts are brought into direct contact with water. b) Measurements of exact thermophysical properties of molten-salt. c) Free convection heat transfer with uniform internal heat generation and a constant heating rate from the bottem. d) Stability of frozen salt film on the container surface. (author)

  5. Electromagnetic modelling of large complex 3-D structures with LEGO and the eigencurrent expansion method

    NARCIS (Netherlands)

    Lancellotti, V.; Hon, de B.P.; Tijhuis, A.G.

    2009-01-01

    Linear embedding via Green's operators (LEGO) is a computational method in which the multiple scattering between adjacent objects - forming a large composite structure - is determined through the interaction of simple-shaped building domains, whose electromagnetic (EM) behavior is accounted for by

  6. Improving the Teaching of Discrete-Event Control Systems Using a LEGO Manufacturing Prototype

    Science.gov (United States)

    Sanchez, A.; Bucio, J.

    2012-01-01

    This paper discusses the usefulness of employing LEGO as a teaching-learning aid in a post-graduate-level first course on the control of discrete-event systems (DESs). The final assignment of the course is presented, which asks students to design and implement a modular hierarchical discrete-event supervisor for the coordination layer of a…

  7. Form, Content, and Gender Differences in Lego[R] Block Creations by Japanese Adolescents

    Science.gov (United States)

    Kato, Daiki; Morita, Miyako

    2009-01-01

    This study examined general features of Lego block creations produced by Japanese adolescents with no known mental health disorders. The block creations of 33 participants were assessed for form, content, and gender differences. Time spent on the task, amount of area covered, and quantity and types of blocks used were measured and correlated with…

  8. Culture’s building blocks: investigating cultural evolution in a LEGO construction task

    Science.gov (United States)

    McGraw, John J.; Wallot, Sebastian; Mitkidis, Panagiotis; Roepstorff, Andreas

    2014-01-01

    One of the most essential but theoretically vexing issues regarding the notion of culture is that of cultural evolution and transmission: how a group’s accumulated solutions to invariant challenges develop and persevere over time. But at the moment, the notion of applying evolutionary theory to culture remains little more than a suggestive trope. Whereas the modern synthesis of evolutionary theory has provided an encompassing scientific framework for the selection and transmission of biological adaptations, a convincing theory of cultural evolution has yet to emerge. One of the greatest challenges for theorists is identifying the appropriate time scales and units of analysis in order to reduce the intractably large and complex phenomenon of “culture” into its component “building blocks.” In this paper, we present a model for scientifically investigating cultural processes by analyzing the ways people develop conventions in a series of LEGO construction tasks. The data revealed a surprising pattern in the selection of building bricks as well as features of car design across consecutive building sessions. Our findings support a novel methodology for studying the development and transmission of culture through the microcosm of interactive LEGO design and assembly. PMID:25309482

  9. Culture’s building blocks: investigating cultural evolution in a LEGO construction task

    Directory of Open Access Journals (Sweden)

    John Joseph Mcgraw

    2014-09-01

    Full Text Available One of the most essential but theoretically vexing issues regarding the notion of culture is that of cultural evolution and transmission: how a group’s accumulated solutions to invariant challenges develop and persevere over time. But at the moment, the notion of applying evolutionary theory to culture remains little more than a suggestive trope. Whereas the modern synthesis of evolutionary theory has provided an encompassing scientific framework for the selection and transmission of biological adaptations, a convincing theory of cultural evolution has yet to emerge. One of the greatest challenges for theorists is identifying the appropriate time scales and units of analysis in order to reduce the intractably large and complex phenomenon of culture into its component building blocks. In this paper, we present a model for scientifically investigating cultural processes by analyzing the ways people develop conventions in a series of LEGO construction tasks. The data revealed a surprising pattern in the selection of building bricks as well as features of car design across consecutive building sessions. Our findings support a novel methodology for studying the development and transmission of culture through the microcosm of interactive LEGO design and assembly.

  10. LEGO[R] Therapy and the Social Use of Language Programme: An Evaluation of Two Social Skills Interventions for Children with High Functioning Autism and Asperger Syndrome

    Science.gov (United States)

    Owens, Gina; Granader, Yael; Humphrey, Ayla; Baron-Cohen, Simon

    2008-01-01

    LEGO[R] therapy and the Social Use of Language Programme (SULP) were evaluated as social skills interventions for 6-11 year olds with high functioning autism and Asperger Syndrome. Children were matched on CA, IQ, and autistic symptoms before being randomly assigned to LEGO or SULP. Therapy occurred for 1 h/week over 18 weeks. A no-intervention…

  11. The Use of Lego Technologies in Elementary Teacher Preparation

    Science.gov (United States)

    Hadjiachilleos, Stella; Avraamidou, Lucy; Papastavrou, Stavros

    2013-10-01

    The need to reform science teacher preparation programs has been pointed out in research (Bryan and Abell in J Res Sci Teach 36:121-140, 1999; Bryan and Atwater in Sci Educ 8(6):821-839, 2002; Harrington and Hathaway in J Teach Educ 46(4):275-284, 1995). Science teachers are charged with the responsibility of incorporating both cognitive and non-cognitive parameters in their everyday teaching practices. This often results in their reluctance to teach science because they often lack disciplinary and/or pedagogical expertise required to promote science learning. The purpose of this study is to propose an alternative instructional approach in which Lego vehicles were used as a tool to promote pre-service elementary teachers' development and to examine whether there are non-cognitive parameters that promote or obstruct them from using Lego Technologies as a teaching tool. The context of the study was defined by a teacher preparation program of a private university in a small Mediterranean country. A sample of 28 pre-service elementary teachers, working in five 5-6-member groups were involved in scientific inquiries, during which they had to use vehicles in order to solve scientific problems related to concepts such as gear functioning, force, and motion. The nature of their cognitive engagement in the scientific inquiry process, non-cognitive parameters contributing to their cognitive engagement, and the impact of their involvement in the process on their development were examined through qualitative analysis of pre- and post-inquiry interviews, presentations of their solutions to the scientific problems and of their personal reflective journals.

  12. On the Development of Creativity and Cooperation Skills in Indigenous Elementary School Students During a LEGO Mindstorms NXT Course

    Directory of Open Access Journals (Sweden)

    Jenyi Chao

    2013-06-01

    Full Text Available The objective of the nine-year integrated curriculum in Taiwan is to cultivate the ten basic competencies of students. Nations around the world have also accentuated the importance of key competencies in citizens, and it is hoped that through education, civic literacy can be enhanced. Among the basic competencies, many nations value the abilities to use technology, to be creative, and cooperative. This study investigated the development of two abilities, creativity and cooperation, in indigenous students while they learned basic mechanical concepts in a LEGO Mindstorms NXT course, which comprised nine units, during the 2010-2011 school year. Indigenous Atayal culture and teaching strategies involving collaborative problem solving were integrated into the course. The participants were 24 third graders from an elementary school serving the Atayal Tribes of Nan-ao, Ilan County. Data was collected through pretests, posttests, and classroom observations. The findings of this study are as follows. (1 The scores of the pretests and posttests indicate that the basic mechanical concepts of the students improved significantly. (2 The results of the figural Torrance Tests of Creative Thinking showed that the students improved significantly in fluency, originality, elaboration, openness, and creative potential. (3 In learning, cooperating, and the division of labor, the students were able to perform their respective duties; in discussion, problem-solving, and presentation, they required some guidance from the teacher; in reflection, assessment, and summary, the students displayed high levels of interest and creative performance.

  13. Integrated learning of mathematics, science and technology concepts through LEGO/Logo projects

    Science.gov (United States)

    Wu, Lina

    This dissertation examined integrated learning in the domains of mathematics, science and technology based on Piaget's constructivism, Papert's constructionism, and project-based approach to education. Ten fifth grade students were involved in a two-month long after school program where they designed and built their own computer-controlled LEGO/Logo projects that required the use of gears, ratios and motion concepts. The design of this study centered on three notions of integrated learning: (1) integration in terms of what educational materials/settings provide, (2) integration in terms of students' use of those materials, and (3) integration in the psychological sense. In terms of the first notion, the results generally showed that the LEGO/Logo environment supported the integrated learning of math, science and technology concepts. Regarding the second notion, the students all completed impressive projects of their own design. They successfully combined gears, motors, and LEGO parts together to create motion and writing control commands to manipulate the motion. But contrary to my initial expectations, their successful designs did not require numerical reasoning about ratios in designing effective gear systems. When they did reason about gear relationships, they worked with "qualitative" ratios, e.g., "a larger driver gear with a smaller driven gear increases the speed." In terms of the third notion of integrated learning, there was evidence in all four case study students of the psychological processes involved in linking mathematical, scientific, and/or technological concepts together to achieve new conceptual units. The students not only made connections between ideas and experiences, but also recognized decisive patterns and relationships in their project work. The students with stronger overall project performances showed more evidence of synthesis than the students with relatively weaker performances did. The findings support the conclusion that all three

  14. Highly Manufacturable Deep (Sub-Millimeter) Etching Enabled High Aspect Ratio Complex Geometry Lego-Like Silicon Electronics

    KAUST Repository

    Ghoneim, Mohamed T.

    2017-02-01

    A highly manufacturable deep reactive ion etching based process involving a hybrid soft/hard mask process technology shows high aspect ratio complex geometry Lego-like silicon electronics formation enabling free-form (physically flexible, stretchable, and reconfigurable) electronic systems.

  15. Basic design and economical evaluation of Gas Turbine High Temperature Reactor 300 (GTHTR300)

    International Nuclear Information System (INIS)

    Kazuhiko, Kunitomi; Shusaku, Shiozawa; Xing, Yan

    2007-01-01

    High Temperature Gas-cooled Reactor (HTGR) combined with a direct cycle gas turbine offers one of the most promising nuclear electricity generation options after 2010. Japan Atomic Energy Agency has been engaging in the basic design and development of Gas Turbine High Temperature Reactor 300 (GTHTR300) since 2003. Costs of capital, fuel, and operation and maintenance have been estimated. The capital cost of the GTHTR300 is lower than that of the existing light water reactor (LWR) because the generation efficiency is considerably higher whereas the construction cost is lower owing to the design simplicity of the gas turbine power conversion unit and the reactor safety system. The fuel cost is shown to equal that of LWR. The operation and maintenance cost has a slight advantage due to the use of chemically inert helium coolant. In sum, the cost of electricity for the GTHTR300 is estimated to be below US 3.3 cents/kWh (4 yen/kWh), which is about two-third of that of current LWRs in Japan. The results confirm that the net power generation cost of the GTHTR300 is much lower than that of the LWR, indicating that the GTHTR300 plant consisting of small-scale reactor units can be economically competitive to the latest large-scale LWR. (authors)

  16. Basic Characteristics of Human Erroneous Actions during Test and Maintenance Activities Leading to Unplanned Reactor Trips

    International Nuclear Information System (INIS)

    Kim, Jae Whan; Park, Jin Kyun

    2010-01-01

    Test and maintenance (T and M) activities of nuclear power plants are essential for sustaining the safety of a power plant and maintaining the reliability of plant systems and components. However, the potential of human errors during T and M activities has also the potential to induce unplanned reactor trips or power derate or making safety-related systems unavailable. According to the major incident/accident reports of nuclear power plants in Korea, contribution of human errors takes up about 20% of the total events. The previous study presents that most of human-related unplanned reactor trip events during normal power operation are associated with T and M activities (63%), which are comprised of plant maintenance activities such as a 'periodic preventive maintenance (PPM)', a 'planned maintenance (PM)' and a 'corrective maintenance (CM)'. This means that T and M activities should be a major subject for reducing the frequency of human-related unplanned reactor trips. This paper aims to introduce basic characteristics of human erroneous actions involved in the test and maintenance-induced unplanned reactor trip events that have occurred between 1986 and 2006 in Korean nuclear power plants. The basic characteristics are described by dividing human erroneous actions into planning-based errors and execution-based errors. For the events associated with planning failures, they are, firstly, classified according to existence of the work procedure and then described for what aspects of the procedure or work plan have deficiency or problem. On the other hand, for the events associated with execution failures, they are described from the aspect of external error modes

  17. A Simple, Small-Scale Lego Colorimeter with a Light-Emitting Diode (LED) Used as Detector

    Science.gov (United States)

    Asheim, Jonas; Kvittingen, Eivind V.; Kvittingen, Lise; Verley, Richard

    2014-01-01

    This article describes how to construct a simple, inexpensive, and robust colorimeter from a few Lego bricks, in which one light-emitting diode (LED) is used as a light source and a second LED as a light detector. The colorimeter is suited to various grades and curricula.

  18. A LEGO Watt balance: An apparatus to determine a mass based on the new SI

    Science.gov (United States)

    Chao, L. S.; Schlamminger, S.; Newell, D. B.; Pratt, J. R.; Seifert, F.; Zhang, X.; Sineriz, G.; Liu, M.; Haddad, D.

    2015-11-01

    A global effort to redefine our International System of Units (SI) is underway, and the change to the new system is expected to occur in 2018. Within the newly redefined SI, the present base units will still exist but be derived from fixed numerical values of seven reference constants. In particular, the unit of mass (the kilogram) will be realized through a fixed value of the Planck constant h. A so-called watt balance, for example, can then be used to realize the kilogram unit of mass within a few parts in 108. Such a balance has been designed and constructed at the National Institute of Standards and Technology. For educational outreach and to demonstrate the principle, we have constructed a LEGO tabletop watt balance capable of measuring a gram-level masses to 1% relative uncertainty. This article presents the design, construction, and performance of the LEGO watt balance and its ability to determine h.

  19. Basic research using the 250 kW research reactor of the Jozef Stefan Institute

    International Nuclear Information System (INIS)

    Dimic, V.

    1984-01-01

    The 250 kW TRIGA Mark II reactor is a light water reactor with solid fuel elements in which the zirconium hydride moderator is homogeneously distributed between enriched uranium. The reactor therefore has a large prompt negative temperature coefficient of reactivity; the fuel also has a very high retention of radioactive fission products. The experimental facilities include a rotary specimen rack, a central in-core radiation thimble, a pneumatic transfer system and pulsing capability. Other experimental facilities include two radial and two tangential beam tubes, a graphite thermal column and a graphite thermalizing column. At the steady state power of 250 kW the peak flux is 1x10 13 n/cm 2 in the central test position. In addition, pulsing to about 2000 MW is usually provided giving peak fluxes of about 2x10 16 n/cm 2 sec. All TRIGA reactors produce a core-average thermal neutron flux of about 10 7 n.v. per watt. Only with very large accelerators can such high fluxes be achieved. The types of research could be summarized as follows: thermal neutron scattering, neutron radiography, neutron and nuclear physics, activation analysis, radiochemistry, biology and medicine, and teaching and training. Typical applied research with a 250 kW reactor has been conducted in medicine, in biology, archaeology, metallurgy and materials science, engineering and criminology. It is well known that research reactors have been used routinely to produce isotopes for industry and medicine. We can conclude that the 250 kW TRIGA reactor is a useful and wide ranging source of radiation for basic and applied research. The operation cost for this instrument is relatively low. (author)

  20. Investigation of the basic reactor physics characteristics of the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Huy, Ngo Quang [Centre for Nuclear Technique Application, Ho Chi Minh City (Viet Nam); Thong, Ha Van; Khang, Ngo Phu [Nuclear Research Inst., Da Lat (Viet Nam)

    1994-10-01

    The Dalat nuclear research reactor was reconstructed from TRIGA MARK II reactor, built in 1963 with nominal power of 250 KW, and reached its planned nominal power of 500 kW for the first time in Feb. 1984. The Dalat reactor has some characteristics distinct from the former TRIGA reactor. Investigation of its characteristics is carried out by the determination of the reactor physics parameters. This paper represents the experimental results obtained for the effective fraction of the delayed photoneutrons, the extraneous neutron source left after the reactor is shut down, the lowest power levels of reactor critical states, the relative axial and radial distributions of thermal neutrons, the safe positive reactivity inserted into the reactor at deep subcritical state, the reactivity temperature coefficient of water, the temperature on the surface of the fuel elements, etc. (author). 10 refs., 10 figs., 2 tabs.

  1. μOrgano: A Lego®-Like Plug & Play System for Modular Multi-Organ-Chips.

    Directory of Open Access Journals (Sweden)

    Peter Loskill

    Full Text Available Human organ-on-a-chip systems for drug screening have evolved as feasible alternatives to animal models, which are unreliable, expensive, and at times erroneous. While chips featuring single organs can be of great use for both pharmaceutical testing and basic organ-level studies, the huge potential of the organ-on-a-chip technology is revealed by connecting multiple organs on one chip to create a single integrated system for sophisticated fundamental biological studies and devising therapies for disease. Furthermore, since most organ-on-a-chip systems require special protocols with organ-specific media for the differentiation and maturation of the tissues, multi-organ systems will need to be temporally customizable and flexible in terms of the time point of connection of the individual organ units. We present a customizable Lego®-like plug & play system, μOrgano, which enables initial individual culture of single organ-on-a-chip systems and subsequent connection to create integrated multi-organ microphysiological systems. As a proof of concept, the μOrgano system was used to connect multiple heart chips in series with excellent cell viability and spontaneously physiological beat rates.

  2. μOrgano: A Lego®-Like Plug & Play System for Modular Multi-Organ-Chips.

    Science.gov (United States)

    Loskill, Peter; Marcus, Sivan G; Mathur, Anurag; Reese, Willie Mae; Healy, Kevin E

    2015-01-01

    Human organ-on-a-chip systems for drug screening have evolved as feasible alternatives to animal models, which are unreliable, expensive, and at times erroneous. While chips featuring single organs can be of great use for both pharmaceutical testing and basic organ-level studies, the huge potential of the organ-on-a-chip technology is revealed by connecting multiple organs on one chip to create a single integrated system for sophisticated fundamental biological studies and devising therapies for disease. Furthermore, since most organ-on-a-chip systems require special protocols with organ-specific media for the differentiation and maturation of the tissues, multi-organ systems will need to be temporally customizable and flexible in terms of the time point of connection of the individual organ units. We present a customizable Lego®-like plug & play system, μOrgano, which enables initial individual culture of single organ-on-a-chip systems and subsequent connection to create integrated multi-organ microphysiological systems. As a proof of concept, the μOrgano system was used to connect multiple heart chips in series with excellent cell viability and spontaneously physiological beat rates.

  3. The malleability of spatial ability under treatment of a FIRST LEGO League-based robotics unit

    Science.gov (United States)

    Coxon, Steven Vincent

    Spatial ability is important to science, technology, engineering, and math (STEM) success, but spatial talents are rarely developed in schools. Likewise, the gifted may become STEM innovators, but they are rarely provided with pedagogy appropriate to develop their abilities in schools. A stratified random sample of volunteer participants (n=75) ages 9-14 was drawn from 16 public school districts' gifted programs, including as many females (n=28) and children from groups traditionally underrepresented in gifted programs (n=18) as available. Participants were randomly divided into an experimental (n=38) and a control group (n=37) for an intervention study. All participants took the CogAT (form 6) Verbal Battery and the Project TALENT Spatial Ability Assessments. The experimental group participated in a simulation of the FIRST LEGO League (FLL) competition for 20 hours total over five consecutive days. All participants took the spatial measure another time. Experimental males evidenced significant and meaningful gains in measured spatial ability (Cohen's d = 0.87). Females did not evidence significant gains in measured spatial ability. This may be due to sampling error, gender differences in prior experience with LEGO, or differences in facets of spatial ability in the treatment or measurements. Further research studies with larger samples of females, other treatments and measurement tools, and longer treatment periods are recommended. The literature review revealed that FLL is beneficial for STEM engagement in both genders and its use in schools is recommended. The present study provides additional evidence for FLL's usefulness in increasing the number of individuals in the STEM pipeline. Keywords: spatial, gilled, talent, robotics, FIRST LEGO League, science

  4. Basic researches on thermo-hydraulic non-equilibrium phenomena related to nuclear reactor safety

    International Nuclear Information System (INIS)

    Sakurai, Akira; Kataoka, Isao; Aritomi, Masanori.

    1989-01-01

    A review was made of recent developments of fundamental researches on thermo-hydraulic non-equilibrium phenomena related to light water reactor safety, in relation to problems to be solved for the improvement of safety analysis codes. As for the problems related to flow con ditions, fundamental researches on basic conservation equations and constitutive equations for transient two-phase flow were reviewed. Regarding to the problems related to thermal non-equilibrium phenomena, fundamental researches on film boiling in pool and forced convection, transient boiling heat transfer and flow behavior caused by pressure transients were reviewed. (author)

  5. 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.

  6. Highly Manufacturable Deep (Sub-Millimeter) Etching Enabled High Aspect Ratio Complex Geometry Lego-Like Silicon Electronics.

    Science.gov (United States)

    Ghoneim, Mohamed Tarek; Hussain, Muhammad Mustafa

    2017-04-01

    A highly manufacturable deep reactive ion etching based process involving a hybrid soft/hard mask process technology shows high aspect ratio complex geometry Lego-like silicon electronics formation enabling free-form (physically flexible, stretchable, and reconfigurable) electronic systems. © 2017 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  7. LEGO Mindstorms NXT for elderly and visually impaired people in need: A platform.

    Science.gov (United States)

    Al-Halhouli, Ala'aldeen; Qitouqa, Hala; Malkosh, Nancy; Shubbak, Alaa; Al-Gharabli, Samer; Hamad, Eyad

    2016-07-27

    This paper presents the employment of LEGO Mindstorms NXT robotics as core component of low cost multidisciplinary platform for assisting elderly and visually impaired people. LEGO Mindstorms system offers a plug-and-play programmable robotics toolkit, incorporating construction guides, microcontrollers and sensors, all connected via a comprehensive programming language. It facilitates, without special training and at low cost, the use of such device for interpersonal communication and for handling multiple tasks required for elderly and visually impaired people in-need. The research project provides a model for larger-scale implementation, tackling the issues of creating additional functions in order to assist people in-need. The new functions were built and programmed using MATLAB through a user friendly Graphical User Interface (GUI). Power consumption problem, besides the integration of WiFi connection has been resolved, incorporating GPS application on smart phones enhanced the guiding and tracking functions. We believe that developing and expanding the system to encompass a range of applications beyond the initial design schematics to ease conducting a limited number of pre-described protocols. However, the beneficiaries for the proposed research would be limited to elderly people who require assistance within their household as assistive-robot to facilitate a low-cost solution for a highly demanding health circumstance.

  8. Protein Assembly and Building Blocks: Beyond the Limits of the LEGO Brick Metaphor.

    Science.gov (United States)

    Levy, Yaakov

    2017-09-26

    Proteins, like other biomolecules, have a modular and hierarchical structure. Various building blocks are used to construct proteins of high structural complexity and diverse functionality. In multidomain proteins, for example, domains are fused to each other in different combinations to achieve different functions. Although the LEGO brick metaphor is justified as a means of simplifying the complexity of three-dimensional protein structures, several fundamental properties (such as allostery or the induced-fit mechanism) make deviation from it necessary to respect the plasticity, softness, and cross-talk that are essential to protein function. In this work, we illustrate recently reported protein behavior in multidomain proteins that deviates from the LEGO brick analogy. While earlier studies showed that a protein domain is often unaffected by being fused to another domain or becomes more stable following the formation of a new interface between the tethered domains, destabilization due to tethering has been reported for several systems. We illustrate that tethering may sometimes result in a multidomain protein behaving as "less than the sum of its parts". We survey these cases for which structure additivity does not guarantee thermodynamic additivity. Protein destabilization due to fusion to other domains may be linked in some cases to biological function and should be taken into account when designing large assemblies.

  9. Survey of Basic Red 18 Dye Removal Using Biofilm Formed on Granular Bagass in Continuous Aerobic Reactor

    Directory of Open Access Journals (Sweden)

    Ferdos Kord Mostafapour

    2015-12-01

    Full Text Available Dyes comprising a major pollutant in the effluent from textile plants are mostly toxic, carcinogenic, mutagenic, and non-biodegradable. This experimental-laboratory study was carried out using a biofilm formed on a granular bagass bed in a continuous aerobic reactor to investigate the kinetic coefficients of the aerobic reactor as well as the effects of color concentration (30-200 mg/l, hydraulic retention time (2-8 h, and BOD concentration (200-100 mg /l on the removal of Basic Red (18 from textile effluents. The results revealed a maximum removal efficiency of 90% for an initial color concentration of 30 mg/l and a hydraulic retention time of 8 hours. A color removal efficiency of 86% was recorded for an influent BOD concentration of 200 mg/l. Also, maximum substrate utilization rate (K for organic loadings of 100 and 200 mg/L were 0.23 and 1.41 while the half velocity constant values were 44.85 and 19.39, respectively. Moreover, for the same organic loadings, the values of 0.35 and 0.5 were recorded for decay coefficient (Kd and 37.36, 4.83 for maximum specific growth rate coefficient (μm, respectively. Based on the findings of this study, it may be claimed that the biofilm formed on a granular bagass bed in a continuous aerobic reactor has a good Basic Red (18 removal efficiency.

  10. Preliminary analysis of basic reactor physics of the Dual Fluid Reactor - 15270

    International Nuclear Information System (INIS)

    Wang, X.; Macian-Juan, R.; Seidl, M.

    2015-01-01

    The Dual Fluid Reactor (DFR) is a novel fast nuclear reactor concept invented by the IFK based on the Generation IV Molten Salt Reactor and the Liquid Metal Cooled Reactor. The DFR uses a chloride based molten fuel salt in order to harden the neutron spectrum. The molten fuel salt is cooled with a separated liquid lead loop, which in principle allows for higher power densities and better breeding performance. The DFR does not combine heat removal and breeding into a single circuit but separates the two functions into two independent circuits. Since there are attractive features mentioned in this design, the main task of this paper is to verify the model of the whole reactor based on this concept. For this purpose several calculations are presented, including steady state calculations, sensitivity calculations with regard to the nuclide cross sections, the temperature and geometry coefficient of k eff as well as the burnup calculation. The Monte Carlo calculation codes MCNP, SERPENT and SCALE are used for the analysis. As expected the study shows a significant negative reactivity feedback with temperature in the overall fission zone. For the coupled coolant and reflector design the temperature feedback is rather small for practical purposes such as reactor control during normal operation. In the view of these results the DFR in principle can be self-regulated totally by the temperature change of its own fuel salt and consequently can rely on fully passive safety systems for accident management

  11. Reactor Physics Training

    International Nuclear Information System (INIS)

    Baeten, P.

    2007-01-01

    University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

  12. The Effects of Integrating LEGO Robotics into a Mathematics Curriculum to Promote the Development of Proportional Reasoning

    Science.gov (United States)

    Casler-Failing, Shelli L.

    2017-01-01

    This mixed methods, action research case study sought to investigate the effects of incorporating LEGO robotics into a seventh grade mathematics curriculum focused on the development of proportional reasoning through the lens of Social Constructivist Theory. Quantitative data was collected via pre- and post-tests from the mathematics class of six…

  13. Using Lego robots to estimate cognitive ability in children who have severe physical disabilities.

    Science.gov (United States)

    Cook, Albert M; Adams, Kim; Volden, Joanne; Harbottle, Norma; Harbottle, Cheryl

    2011-01-01

    To determine whether low-cost robots provide a means by which children with severe disabilities can demonstrate understanding of cognitive concepts. Ten children, ages 4 to 10, diagnosed with cerebral palsy and related motor conditions, participated. Participants had widely variable motor, cognitive and receptive language skills, but all were non-speaking. A Lego Invention 'roverbot' was used to carry out a range of functional tasks from single-switch replay of pre-stored movements to total control of the movement in two dimensions. The level of sophistication achieved on hierarchically arranged play tasks was used to estimate cognitive skills. The 10 children performed at one of the six hierarchically arranged levels from 'no interaction' through 'simple cause and effect' to 'development and execution of a plan'. Teacher interviews revealed that children were interested in the robot, enjoyed interacting with it and demonstrated changes in behaviour and social and language skills following interaction. Children with severe physical disabilities can control a Lego robot to perform un-structured play tasks. In some cases, they were able to display more sophisticated cognitive skills through manipulating the robot than in traditional standardised tests. Success with the robot could be a proxy measure for children who have cognitive abilities but cannot demonstrate them in standard testing.

  14. Culture’s building blocks: Investigating cultural evolution in a LEGO construction task

    DEFF Research Database (Denmark)

    McGraw, John J.; Wallot, Sebastian; Mitkidis, Panagiotis

    2014-01-01

    to culture remains little more than a suggestive trope. Whereas the modern synthesis of evolutionary theory has provided an encompassing scientific framework for the selection and transmission of biological adaptations, a convincing theory of cultural evolution has yet to emerge. One of the greatest...... the ways people develop conventions in a series of LEGO construction tasks. The data revealed a surprising pattern in the selection of building bricks as well as features of car design across consecutive building sessions. Our findings support a novel methodology for studying the development...

  15. Investigation of Self-assembly Structure and Properties of a Novel Designed Lego-type Peptide with Double Amphiphilic Surfaces

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Liang [Sichuan University, Sichuan (China); Zhao, Xiao Jun [Massachusetts Institute of Technology, Cambridge (United States)

    2010-12-15

    A typically designed 'Peptide Lego' has two distinct surfaces: a hydrophilic side that contains the complete charge distribution and a hydrophobic side. In this article, we describe the fabrication of a unique lego-type peptide with the AEAEYAKAK sequence. The novel peptide with double amphiphilic surfaces is different from typical peptides due to special arrangement of the residues. The results of CD, FT-IR, AFM and DLS demonstrate that the peptide with the random coil characteristic was able to form stable nanostructures that were mediated by non-covalent interactions in an aqueous solution. The data further indicated that despite its different structure, the peptide was able to undergo self-assembly similar to a typical peptide. In addition, the use of hydrophobic pyrene as a model allowed the peptide to provide a new type of potential nanomaterial for drug delivery. These efforts collectively open up a new direction in the fabrication of nanomaterials that are more perfect and versatile.

  16. Investigation of Self-assembly Structure and Properties of a Novel Designed Lego-type Peptide with Double Amphiphilic Surfaces

    International Nuclear Information System (INIS)

    Wang, Liang; Zhao, Xiao Jun

    2010-01-01

    A typically designed 'Peptide Lego' has two distinct surfaces: a hydrophilic side that contains the complete charge distribution and a hydrophobic side. In this article, we describe the fabrication of a unique lego-type peptide with the AEAEYAKAK sequence. The novel peptide with double amphiphilic surfaces is different from typical peptides due to special arrangement of the residues. The results of CD, FT-IR, AFM and DLS demonstrate that the peptide with the random coil characteristic was able to form stable nanostructures that were mediated by non-covalent interactions in an aqueous solution. The data further indicated that despite its different structure, the peptide was able to undergo self-assembly similar to a typical peptide. In addition, the use of hydrophobic pyrene as a model allowed the peptide to provide a new type of potential nanomaterial for drug delivery. These efforts collectively open up a new direction in the fabrication of nanomaterials that are more perfect and versatile

  17. Collection of Summaries of reports on result of research at basic experiment device for nuclear fusion reactor blanket design, 1994

    International Nuclear Information System (INIS)

    1995-07-01

    The development of nuclear fusion reactors reached such stage that the generation of fusion power output comparable with the input power into core plasma is possible. At present, the engineering design of the international thermonuclear fusion experimental reactor, ITER, is advanced by the cooperation of Japan, USA, Europe and Russia, aiming at the start of operation at the beginning of 21st century. This meeting for reporting the results has been held every year, and this time, it was held on May 19, 1995 at University of Tokyo with the theme ''The interface properties of fusion reactor materials and the control of particle transport''. About 50 participants from academic, governmental and industrial circles discussed actively on the theme. Three lectures on the topics of fusion reactor engineering and materials and seven lectures on the basic experiment of fusion reactor blanket design related to the next period project were given at the meeting. (K.I.)

  18. How the LEGO Group Is Embarking on Architectural Path Constitution to Transform Its Information Infrastructure into a Digital Platform

    DEFF Research Database (Denmark)

    Törmer, Robert Lorenz

    2018-01-01

    Traditional companies are increasingly turning towards platform strategies to gain speed in the development of digital value propositions and prepare for the challenges arising from digitalization. This paper reports on the digitalization journey of the LEGO Group to elaborate how brick-and-mortar...

  19. High School Students' Views on the PBL Activities Supported via Flipped Classroom and LEGO Practices

    Science.gov (United States)

    Cukurbasi, Baris; Kiyici, Mubin

    2018-01-01

    The purpose of this study was to investigate the high school students' views on instructions based on Flipped Classroom Model (FC) and LEGO applications. The case study, which is one of the qualitative research methods, was used within the scope of the study, the duration of which was 7 weeks. In order to choose the research group of the study,…

  20. The Effect on Pupils' Science Performance and Problem-Solving Ability through Lego: An Engineering Design-Based Modeling Approach

    Science.gov (United States)

    Li, Yanyan; Huang, Zhinan; Jiang, Menglu; Chang, Ting-Wen

    2016-01-01

    Incorporating scientific fundamentals via engineering through a design-based methodology has proven to be highly effective for STEM education. Engineering design can be instantiated for learning as they involve mental and physical stimulation and develop practical skills especially in solving problems. Lego bricks, as a set of toys based on design…

  1. Using Python to Program LEGO MINDSTORMS® Robots: The PyNXC Project

    Directory of Open Access Journals (Sweden)

    2010-04-01

    Full Text Available

    LEGO MINDSTORMS® NXT (Lego Group, 2006 is a perfect platform for introducing programming concepts, and is generally targeted toward children from age 8-14.  The language which ships with the MINDSTORMS®, called NXTg, is a graphical language based on LabVIEW (Jeff Kodosky, 2010.  Although there is much value in graphical languages, such as LabVIEW, a text-based alternative can be targeted at an older audiences and serve as part of a more general introduction to modern computing.  Other languages, such as NXC (Not Exactly C (Hansen, 2010 and PbLua (Hempel, 2010, fit this description.  Here we introduce PyNXC, a subset of the Python language which can be used to program the NXT MINDSTORMS®.  We present results using PyNXC, comparisons with other languages, and some challenges and future possible extensions.


     

  2. RA Reactor

    International Nuclear Information System (INIS)

    1978-02-01

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation [sr

  3. Mechatronics Education: From Paper Design to Product Prototype Using LEGO NXT Parts

    Science.gov (United States)

    Lofaro, Daniel M.; Le, Tony Truong Giang; Oh, Paul

    The industrial design cycle starts with design then simulation, prototyping, and testing. When the tests do not match the design requirements the design process is started over again. It is important for students to experience this process before they leave their academic institution. The high cost of the prototype phase, due to CNC/Rapid Prototype machine costs, makes hands on study of this process expensive for students and the academic institutions. This document shows that the commercially available LEGO NXT Robot kit is a viable low cost surrogate to the expensive industrial CNC/Rapid Prototype portion of the industrial design cycle.

  4. Building a Lego wall: Sequential action selection.

    Science.gov (United States)

    Arnold, Amy; Wing, Alan M; Rotshtein, Pia

    2017-05-01

    The present study draws together two distinct lines of enquiry into the selection and control of sequential action: motor sequence production and action selection in everyday tasks. Participants were asked to build 2 different Lego walls. The walls were designed to have hierarchical structures with shared and dissociated colors and spatial components. Participants built 1 wall at a time, under low and high load cognitive states. Selection times for correctly completed trials were measured using 3-dimensional motion tracking. The paradigm enabled precise measurement of the timing of actions, while using real objects to create an end product. The experiment demonstrated that action selection was slowed at decision boundary points, relative to boundaries where no between-wall decision was required. Decision points also affected selection time prior to the actual selection window. Dual-task conditions increased selection errors. Errors mostly occurred at boundaries between chunks and especially when these required decisions. The data support hierarchical control of sequenced behavior. (PsycINFO Database Record (c) 2017 APA, all rights reserved).

  5. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

    This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

  6. Collection of summaries of reports on result of research at basic experiment device for nuclear fusion reactor blanket design, 1995

    International Nuclear Information System (INIS)

    1996-07-01

    This report meeting was held on May 22, 1995 at University of Tokyo by about 40 participants. As the topics on the fusion reactor engineering research in Japan, lectures were given on the present state and future of nuclear fusion networks and on the strong magnetic field tokamak using electromagnetic force-balanced coils being planned. Thereafter, the reports of the results of the researches which were carried out by using this experimental facility were made, centering around the subject related to the future conception 'The interface properties of fusion reactor materials and particle transport control'. The publication was made on the future conception of the basic experiment setup for fusion reactor blanket design, the application of high temperature superconductors to the advancement of nuclear fusion reactors, the modeling of the dynamic irradiation behavior of fusion reactor materials, the interface particle behavior in plasma-wall interaction, the behavior of tritium on the surface of breeding materials, and breeding materials and the behavior of tritium in plasma-wall interaction. (K.I.)

  7. Proposals of new basic concepts on safety and radioactive waste and of new High Temperature Gas-cooled Reactor based on these basic concepts

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Masuro, E-mail: ogawa.masuro@jaea.go.jp

    2016-11-15

    Highlights: • The author proposed new basic concepts on safety and radioactive waste. • A principle of ‘continue confining’ to realize the basic concept on safety is also proposed. • It is indicated that only a HTGR can attain the conditions required from the principle. • Technologies to realize the basic concept on radioactive waste are also discussed. • A New HTGR system based on the new basic concepts is proposed. - Abstract: A new basic concept on safety of ‘Not causing any serious catastrophe by any means’ and a new basic concept on radioactive waste of ‘Not returning any waste that possibly affects the environment’ are proposed in the present study, aiming at nuclear power plants which everybody can accept, in consideration of the serious catastrophe that happened at Fukushima Japan in 2011. These new basic concepts can be found to be valid in comparison with basic concepts on safety and waste in other industries. The principle to realize the new basic concept on safety is, as known well as the inherent safety, to use physical phenomena such as Doppler Effect and so on which never fail to work even if all equipment and facilities for safety lose their functions. In the present study, physical phenomena are used to ‘continue confining’, rather than ‘confine’, because the consequence of emission of radioactive substances to the environment cannot be mitigated. To ‘continue confining’ is meant to apply natural correction to fulfill inherent safety function. Fission products must be detoxified to realize the new basic concept on radioactive waste, aiming at the final processing and disposal of radioactive wastes as same as that in the other wastes such as PCB, together with much efforts not to produce radioactive wastes and to reduce their volume nevertheless if they are emitted. Technology development on the detoxification is one of the most important subjects. A new High Temperature Gas-cooled Reactor, namely the New HTGR

  8. Proposals of new basic concepts on safety and radioactive waste and of new High Temperature Gas-cooled Reactor based on these basic concepts

    International Nuclear Information System (INIS)

    Ogawa, Masuro

    2016-01-01

    Highlights: • The author proposed new basic concepts on safety and radioactive waste. • A principle of ‘continue confining’ to realize the basic concept on safety is also proposed. • It is indicated that only a HTGR can attain the conditions required from the principle. • Technologies to realize the basic concept on radioactive waste are also discussed. • A New HTGR system based on the new basic concepts is proposed. - Abstract: A new basic concept on safety of ‘Not causing any serious catastrophe by any means’ and a new basic concept on radioactive waste of ‘Not returning any waste that possibly affects the environment’ are proposed in the present study, aiming at nuclear power plants which everybody can accept, in consideration of the serious catastrophe that happened at Fukushima Japan in 2011. These new basic concepts can be found to be valid in comparison with basic concepts on safety and waste in other industries. The principle to realize the new basic concept on safety is, as known well as the inherent safety, to use physical phenomena such as Doppler Effect and so on which never fail to work even if all equipment and facilities for safety lose their functions. In the present study, physical phenomena are used to ‘continue confining’, rather than ‘confine’, because the consequence of emission of radioactive substances to the environment cannot be mitigated. To ‘continue confining’ is meant to apply natural correction to fulfill inherent safety function. Fission products must be detoxified to realize the new basic concept on radioactive waste, aiming at the final processing and disposal of radioactive wastes as same as that in the other wastes such as PCB, together with much efforts not to produce radioactive wastes and to reduce their volume nevertheless if they are emitted. Technology development on the detoxification is one of the most important subjects. A new High Temperature Gas-cooled Reactor, namely the New HTGR

  9. The Effect of LEGO Training on Pupils' School Performance in Mathematics, Problem Solving Ability and Attitude: Swedish Data

    Science.gov (United States)

    Hussain, Shakir; Lindh, Jorgen; Shukur, Ghazi

    2006-01-01

    The purpose of this study is to investigate the effect of one year of regular "LEGO" training on pupils' performances in schools. The underlying pedagogical perspective is the constructivist theory, where the main idea is that knowledge is constructed in the mind of the pupil by active learning. The investigation has been made in two…

  10. Fictions industrielles et apprentissage du temps : les jeux LEGO Bionicles

    Directory of Open Access Journals (Sweden)

    Irène Langlet

    2011-06-01

    Full Text Available Il y a un paradoxe LEGO : venue tard aux nouveaux jouets médiatiques et numériques, la firme danoise a pourtant lancé l’un des phénomènes les plus exemplaires des années 2000 : la gamme Bionicle, qui mêle figurines, jeux de construction, fictions populaires multi-supports (imprimé, télévision, jeux vidéo, CD-Rom, cinéma, communautés de joueurs sur internet, univers partagé, et tous les produits non ludiques dérivés. Une description fine de la gamme Bionicle fait apparaître d’emblée, non seulement son adéquation étroite aux problématiques de porosité intermédiatique et d’exploitation de la fiction, mais son innovation majeure, étroitement liée à la nature des produits de la firme LEGO. Dans un processus de « médiatisation », la gamme accomplit, après la généralisation de séries thématiques favorisant l’imaginaire, le passage de LEGO à la narrativisation. On montrera en quoi l’introduction du narratif dans cette gamme a répondu à cet objectif-maître de l’industrie des biens de consommation en régime médiatique : consommer du média, c’est encore jouer au jeu-noyau. Mais on verra aussi en quoi ce cadre narratif peut suggérer des analyses qui vont au-delà de la théorie du marketing ou de la didactique du jouet, et qui ont trait aux usages contemporains de la fiction et à la psychologie du développement en matière de maîtrise de la temporalité.

  11. Administrative Aspects of the Criticality Controls Used in Programmes for Basic Criticality Research, Reactor Development and Materials Processing

    Energy Technology Data Exchange (ETDEWEB)

    Wood, D. P.; Giessing, D. F. [Operational Safety Division, USAEC Albuquerque Operations Office, NM (United States)

    1966-05-15

    This paper describes the administrative and procedural aspects of criticality controls used by a field office of the United States Atomic Energy Commission in programmes that include reactor criticals, research and materials testing reactors, and power reactor development. Situations encountered include handling, storing, and processing large quantities of uranium-235 and plutonium-239 of various configurations and compositions in laboratories and operations which gather basic criticality data, processing of fissile material, and varied reactor research and development, programmes including fuel materials. Similar situations exist for uranium-233 and plutonium-238 on a smaller laboratory scale. The administrative controls and interactions of the USAEC field office and the operating contractors, who operate these installations for the USAEC, are outlined. Also, the purpose and scope of the direct examination by USAEC personnel of these contractor facilities are analysed. The programme has been in effect for three years and is believed to be successful in maintaining efficient operations and an acceptable low level of risk of inadvertent criticality. Success of this programme is in good measure due to the close working relationship between the staffs of the USAEC field office and the operating contractors. (author)

  12. Proceeding of the Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology. Part I : Physics, Reactor Physics and Nuclear Instrumentation

    International Nuclear Information System (INIS)

    Sudjatmoko; Karmanto, Eko Edy; Supartini, Endang

    1996-04-01

    Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity was held by PPNY BATAN for monitoring the research Activity which achieved in BATAN. The Proceeding contains a proposal about basic which has physics; reactor physics and nuclear instrumentation. This proceedings is the first part from two part which published in series. There are 33 articles which have separated index

  13. A LEGO Mindstorms NXT Approach for Teaching at Data Acquisition, Control Systems Engineering and Real-Time Systems Undergraduate Courses

    Science.gov (United States)

    Cruz-Martin, A.; Fernandez-Madrigal, J. A.; Galindo, C.; Gonzalez-Jimenez, J.; Stockmans-Daou, C.; Blanco-Claraco, J. L.

    2012-01-01

    LEGO Mindstorms NXT robots are being increasingly used in undergraduate courses, mostly in robotics-related subjects. But other engineering topics, like the ones found in data acquisition, control and real-time subjects, also have difficult concepts that can be well understood only with good lab exercises. Such exercises require physical…

  14. Analysis of dynamic stability and safety of reactor system by reactor simulator

    International Nuclear Information System (INIS)

    Raisic, N.

    1963-11-01

    In order to enable qualitative analysis of dynamic properties of reactors RA and RB, mathematical models of these reactors were formulated and adapted for solution on analog computer. This report contains basic assessments for creating the model and complete equations for each reactor. Model was used to analyse three possible accidents at the RA reactor and possible hypothetical accidents at the RB reactor

  15. The future role of research reactors

    International Nuclear Information System (INIS)

    Glaeser, W.

    2001-01-01

    The decline of neutron source capacity in the next decades urges for the planning and construction of new neutron sources for basic and applied research with neutrons. Modern safety precautions of research reactors make them competitive with other ways of neutron production using non-chain reactions for many applications. Research reactors consequently optimized offer a very broad range of possible applications in basic and applied research. Research reactors at universities also in the future have to play an important role in education and training in basic and applied nuclear science. (orig.)

  16. Some basic concepts of fast breeder reactor safeguards

    International Nuclear Information System (INIS)

    Tkharev, E.; Walford, F.J.

    1987-04-01

    The range of discussion topics of this report is restricted to a few key areas of safeguards importance at Fast Breeder Reactors (FBR) only. The differences between thermal and fast reactors that may have safeguards significance in the case of FBRs are listed. The FBR principles of design are mentioned. The relevant safeguards objectives and criteria are given. The fundamental issues for safeguarding FBR are treated. An outline safeguards approach is presented. Model inspection activities are mentioned. 4 figs

  17. Atomic reactor thermal engineering

    International Nuclear Information System (INIS)

    Kim, Gwang Ryong

    1983-02-01

    This book starts the introduction of atomic reactor thermal engineering including atomic reaction, chemical reaction, nuclear reaction neutron energy and soon. It explains heat transfer, heat production in the atomic reactor, heat transfer of fuel element in atomic reactor, heat transfer and flow of cooler, thermal design of atomic reactor, design of thermodynamics of atomic reactor and various. This deals with the basic knowledge of thermal engineering for atomic reactor.

  18. Reactor physics aspects of CANDU reactors

    International Nuclear Information System (INIS)

    Critoph, E.

    1980-01-01

    These four lectures are being given at the Winter Course on Nuclear Physics at Trieste during 1978 February. They constitute part of the third week's lectures in Part II: Reactor Theory and Power Reactors. A physical description of CANDU reactors is given, followed by an overview of CANDU characteristics and some of the design options. Basic lattice physics is discussed in terms of zero energy lattice experiments, irradiation effects and analytical methods. Start-up and commissioning experiments in CANDU reactors are reviewed, and some of the more interesting aspects of operation discussed - fuel management, flux mapping and control of the power distribution. Finally, some of the characteristics of advanced fuel cycles that have been proposed for CANDU reactors are summarized. (author)

  19. Examining Students' Proportional Reasoning Strategy Levels as Evidence of the Impact of an Integrated LEGO Robotics and Mathematics Learning Experience

    Science.gov (United States)

    Martínez Ortiz, Araceli

    2015-01-01

    The presented study used a problem-solving experience in engineering design with LEGO robotics materials as the real-world mathematics-learning context. The goals of the study were (a) to determine if a short but intensive extracurricular learning experience would lead to significant student learning of a particular academic topic and (b) to…

  20. Motivating programming students by Problem Based Learning and LEGO robots

    DEFF Research Database (Denmark)

    Lykke, Marianne; Coto Chotto, Mayela; Mora, Sonia

    2014-01-01

    . For this reason the school is focusing on different teaching methods to help their students master these skills. This paper introduces an experimental, controlled comparison study of three learning designs, involving a problem based learning (PBL) approach in connection with the use of LEGO Mindstorms to improve...... students programming skills and motivation for learning in an introductory programming course. The paper reports the results related with one of the components of the study - the experiential qualities of the three learning designs. The data were collected through a questionnaire survey with 229 students...... from three groups exposed to different learning designs and through six qualitative walk-alongs collecting data from these groups by informal interviews and observations. Findings from the three studies were discussed in three focus group interviews with 10 students from the three experimental groups....

  1. The CAREM reactor and present currents in reactor design

    International Nuclear Information System (INIS)

    Ordonez, J.P.

    1990-01-01

    INVAP has been working on the CAREM project since 1983. It concerns a very low power reactor for electrical energy generation. The design of the reactor and the basic criteria used were described in 1984. Since then, a series of designs have been presented for reactors which are similar to CAREM regarding the solutions presented to reduce the chance of major nuclear accidents. These designs have been grouped under different names: Advanced Reactors, Second Generation Reactors, Inherently Safe Reactors, or even, Revolutionary Reactors. Every reactor fabrication firm has, at least, one project which can be placed in this category. Presently, there are two main currents of Reactor Design; Evolutionary and Revolutionary. The present work discusses characteristics of these two types of reactors, some revolutionary designs and common criteria to both types. After, these criteria are compared with CAREM reactor design. (Author) [es

  2. LEGO Mindstorms NXT: Juego como Herramienta de Aprendizaje de Programación

    Directory of Open Access Journals (Sweden)

    Leidy Diana Jiménez-Pinzón

    2014-06-01

    Full Text Available LEGO Mindstorms es un juego que se usa como herramienta para el aprendizaje de distintas áreas de conocimiento. Una persona puede aprender acerca de programación mediante distintos lenguajes y aplicaciones para compilar el código de la solución planteada y resolver una situación particular. Sin embargo, la enseñanza de programación es sólo un fundamento teórico y poco práctico. Por estas razones, se pretende enseñar a programar mediante un lenguaje sencillo y una plataforma que permita visualizar el código gráficamente y validarlo específicamente con las instrucciones programadas sobre un robot.

  3. Basic principles

    International Nuclear Information System (INIS)

    Wilson, P.D.

    1996-01-01

    Some basic explanations are given of the principles underlying the nuclear fuel cycle, starting with the physics of atomic and nuclear structure and continuing with nuclear energy and reactors, fuel and waste management and finally a discussion of economics and the future. An important aspect of the fuel cycle concerns the possibility of ''closing the back end'' i.e. reprocessing the waste or unused fuel in order to re-use it in reactors of various kinds. The alternative, the ''oncethrough'' cycle, discards the discharged fuel completely. An interim measure involves the prolonged storage of highly radioactive waste fuel. (UK)

  4. Basic experiments during loss of vacuum event (LOVE) in fusion experimental reactor

    International Nuclear Information System (INIS)

    Ogawa, Masuro; Kunugi, Tomoaki; Seki, Yasushi

    1993-01-01

    If a loss of vacuum event (LOVE) occurs due to damage of the vacuum vessel of a nuclear fusion experimental reactor, some chemical reactions such as a graphic oxidation and a buoyancy-driven exchange flow take place after equalization of the gas pressure between the inside and outside of the vacuum vessel. The graphite oxidation would generate inflammable carbon monoxide and release tritium retained in the graphite. The exchange flow through the breaches may transport the carbon monoxide and tritium out of the vacuum vessel. To add confidence to the safety evaluations and analyses, it is important to grasp the basic phenomena such as the exchange flow and the graphite oxidation. Experiments of the exchange flow and the graphite oxidation were carried out to obtain the exchange flow rate and the rate constant for the carbon monoxide combustion, respectively. These experimental results were compared with existing correlations. The authors plan a scaled-model test and a full-scale model test for the LOVE

  5. Physics and kinetics of TRIGA reactor

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    This training module is written as an introduction to reactor physics for reactor operators. It assumes the reader has a basic, fundamental knowledge of physics, materials and mathematics. The objective is to provide enough reactor theory knowledge to safely operate a typical research reactor. At this level, it does not necessarily provide enough information to evaluate the safety aspects of experiment or non-standard operation reviews. The material provides a survey of basic reactor physics and kinetics of TRIGA type reactors. Subjects such as the multiplication factor, reactivity, temperature coefficients, poisoning, delayed neutrons and criticality are discussed in such a manner that even someone not familiar with reactor physics and kinetics can easily follow. A minimum of equations are used and several tables and graphs illustrate the text. (author)

  6. To the analysis of reactor noise in boiling water reactors

    International Nuclear Information System (INIS)

    Seifritz, W.

    1972-01-01

    The paper contains some basic thoughts on the problem of neutron flux oscillations in power reactors. The advantages of self-powered detectors and their function are explained. In addition, noise measurements of the boiling water reactors at Lingen and Holden are described, and the possibilities of an employment of vanadium detectors for the analysis of reactor noise are discussed. The final pages of the paper contain a complete list of the author's publications in the field of reactor noise analysis. (RW/AK) [de

  7. Modelamiento y programación de un juego de legos en un entorno de realidad virtual

    OpenAIRE

    Arboleda, Freddy; Laica, Ricardo; Loor, Magdalena; García, Sixto

    2011-01-01

    This project seeks by the use of the techn Lego blocks, in order to check the applicability of the concepts learned throughout the topic specifies the general ideas on the model blocks. First, we focus in the creation of the 3D objects and scenes, which are going to constitute the virtual environment. Later, we are going to detail the different positioning and control algorithms created to help us in the precision and the logic en the movements of the virtu and disadvantages...

  8. Future plant of basic research for nuclear energy by university researchers

    International Nuclear Information System (INIS)

    Shibata, Toshikazu

    1984-01-01

    National Committee for Nuclear Energy Research, Japan Science Council has completed a future plan for basic nuclear energy research by university researchers. The JSC has recommended the promotion of basic research for nuclear energy based on the plan in 1983. The future plan consists of four main research fields, namely, (1) improvements of reactor safety, (2) down stream, (3) thorium fuel reactors, and (4) applications of research reactor and radioisotopes. (author)

  9. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

    Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

  10. 1989 basic plan for atomic energy development and utilization

    International Nuclear Information System (INIS)

    1989-01-01

    A Basic Plan for Atomic Energy Development and Utilization has been established each year based on the guidelines set up by the Atomic Energy Commission of Japan, with the aim of promoting the development and utilization of atomic energy schematically and efficiently. The Basic Plan shows specific projects to achieve the objectives specified in the Long-Range Plan for Atomic Energy Development and Utilization. The Basic Plan specifies efforts to be made for overall strengthening of safety measures (safety policies, safety research, disaster prevention, etc.), promotion of nuclear power generation, establishment of the nuclear fuel cycle (securing of uranium, technology for uranium enrichment, reprocessing, etc.), development of new types of power reactors (fast breeder reactor, new types of converter reactors, plutonium fuel processing technology), promotion of leading projects (nuclear fusion, utilization of radiations, atomic powered ships, high-temperature engineering tests), promotion of basic technology development (basic research, training of scientists and engineers), voluntary and active international activities (international cooperation), and acquisition of understanding and cooperation of the general public. (N,K.)

  11. Basic natural circulation characteristics of SBWR

    International Nuclear Information System (INIS)

    Kuran, S.; Soekmen, C. N.

    2001-01-01

    Natural circulation is an important passive heat removal mechanism for both existing and next generation light water reactors. Simplified Boiling Water Reactor (SBWR) is one of the advanced light water reactors that rely on natural circulation for normal as well as emergency core cooling. In this study, basic natural circulation characteristics of this reactor are examined on a flow loop that simulates the operation of SBWR. On this model, effect of system operating parameters on the steady state natural circulation characteristics inside the loop is studied via solving the transcendental equation for loop flow rate

  12. Basic considerations for the safety analysis report of the Greek Research Reactor-1 (GRR-1)

    International Nuclear Information System (INIS)

    Anoussis, J.N.; Chrysochoides, N.G.; Papastergiou, C.N.

    1980-09-01

    The basic considerations upon which the new revised Safety Analysis Report (SAR) for the GRR-1 will be based are presented. The format and the content the SAR will follow are given. A number of credible and less credible accidents is briefly analysed on the basis of present knowledge and experience for similar reactors, as well as the experience gained in the last 10 years of the GRR-1 operation at 5 MW. The accident caused by partial blockage of the cooling flow is considered to be the Maximum Credible Accident (MCA) for the GRR-1. The MCA is analysed and its radiological impact to the environment is estimated using conservative assumptions. (T.A.)

  13. Competition-motivated teamwork and narratives to motivate girls for engineering

    DEFF Research Database (Denmark)

    Friesel, Anna; Timcenko, Olga

    2011-01-01

    cooperation between Ballerup Community, Copenhagen University College of Engineering and Aalborg University in Copenhagen. We focus on girls' engagement in FIRST LEGO League competitions, in order to motivate them in the future to study engineering. LEGO Mindstorm robots and RoboLab graphical programming......This paper describes competition-motivated teamwork and narratives to motivate teenager girls, 11-17 years old, to learn programming and basics of control. FIRST LEGO League competitions have been held at the Copenhagen University College of Engineering for several years because of successful...

  14. Fast reactors: potential for power

    International Nuclear Information System (INIS)

    1983-02-01

    The subject is discussed as follows: basic facts about conventional and fast reactors; uranium economy; plutonium and fast reactors; cooling systems; sodium coolant; safety engineering; handling and recycling plutonium; safeguards; development of fast reactors in Britain and abroad; future progress. (U.K.)

  15. Nuclear reactors. Introduction

    International Nuclear Information System (INIS)

    Boiron, P.

    1997-01-01

    This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

  16. Basic approach to the disposal of low level radioactive waste generated from nuclear reactors containing comparatively high radioactivity

    International Nuclear Information System (INIS)

    Moriyama, Yoshinori

    1998-01-01

    Low level radioactive wastes (LLW) generated from nuclear reactors are classified into three categories: LLW containing comparatively high radioactivity; low level radioactive waste; very low level radioactive waste. Spent control rods, part of ion exchange resin and parts of core internals are examples of LLW containing comparatively high radioactivity. The Advisory Committee of Atomic Energy Commission published the report 'Basic Approach to the Disposal of LLW from Nuclear Reactors Containing Comparatively High Radioactivity' in October 1998. The main points of the proposed concept of disposal are as follows: dispose of underground deep enough not be disturb common land use (e.g. 50 to 100 m deep); dispose of underground where radionuclides migrate very slowly; dispose of with artificial engineered barrier which has the same function as the concrete pit; control human activities such as land use of disposal site for a few hundreds years. (author)

  17. The fusion reactor

    International Nuclear Information System (INIS)

    Brennan, M.H.

    1974-01-01

    Basic principles of the fusion reactor are outlined. Plasma heating and confinement schemes are described. These confinement systems include the linear Z pinch, magnetic mirrors and Tokamaks. A fusion reactor is described and a discussion is given of its environmental impact and its fuel situation. (R.L.)

  18. Using FIRST LEGO League Robotics Competitions to Engage Middle School Students in Physics

    Science.gov (United States)

    Rosen, Jeffrey

    2009-11-01

    As the nation and world grapple with looming crises in sectors such as energy, health care and the environment, it is critical that we keep today's youth interested in careers in science, technology, engineering and math (STEM). Studies indicate that many students lose interest in the sciences by ages 10-13, when they are in grades 4-8 in the U.S. educational system. Many of the interventions to counteract this trend focus on boosting interest in STEM in secondary schools and universities. However the case can be made that the greater need is actually earlier in the education of the child. How can we work with this age group in an exciting way that will promote the study of science? Student robotics competitions might be one effective answer. Programs are currently being run around the country and the world that engage young people in the study of science through robotic competition. Many of these programs rely on mentors to guide the students through the process, which in the most effective programs includes the study of physic concepts through engineering design. During this presentation we will discuss the options for participating in programs that help the students and teachers better understand the science, specifically the physics, which underlies robotics. In particular, we will focus on the international program called FIRST LEGO League (FLL), in which students ages 9-14 are challenged every year to construct a LEGO robot that can navigate and complete a course of theme-related missions. The FLL program is currently operating in almost every state in the U.S. and relies on recruiting qualified mentors and judges who want to impact young people's interest in STEM. Physics professionals can make a tremendous difference in the lives of these eager middle school students.

  19. Effect of Catalyst Pellet-Diameter and Basicity on Transesterification of Soybean Oil into Biodiesel using K2O/CaO-ZnO Catalyst over Hybrid Catalytic-Plasma Reactor

    Directory of Open Access Journals (Sweden)

    Istadi I.

    2018-01-01

    Full Text Available This research is aimed to study the effect of catalyst pellet-diameter and catalyst basicity on the transesterification process of soybean oil into biodiesel over a hybrid catalytic-plasma reactor. Various catalyst diameters (3, 5, and 7 mm were tested in this reaction system. Catalyst basicity was also examined by comparing fresh and used catalyst as well as with and without K2O promoter. All catalysts testing were performed in a hybrid plasma-catalytic reactor (dielectric barrier discharge – DBD type. From the results, the synergistic effects roles of the catalyst and the plasma in the transesterification process are important, in which the energetic electrons within plasma assist the reaction on the catalyst surface by an exciting bonded electron. The catalyst basicity was influenced by the composition of CaO on the catalyst as well as roles of the alkaline K2O promoter. Catalyst basicity is important in producing biodiesel with high performance. Yield of fatty acid alkyl ester (FAAE or biodiesel is slightly influenced by the catalyst diameter within the range of diameter studied.

  20. Proceeding on the scientific meeting and presentation on basic research of nuclear science and technology (book I): physics, reactors

    International Nuclear Information System (INIS)

    Syarip; Prayitno; Samin; Agus Taftazani; Sudjatmoko; Pramudita Anggraita; Gede Sutresna W; Tjipto Sujitno; Slamet Santosa; Herry Poernomo; R Sukarsono; Prajitno

    2014-06-01

    Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is an annual activity held by Centre for Accelerator Science and Technology, National Nuclear Energy Agency, in Yogyakarta, for monitoring research activities achieved by the Agency. The papers presented in the meeting were collected into proceedings which were divided into two groups that are physics and nuclear reactors. The proceedings consists of three articles from keynote speakers and 25 articles from BATAN and others participants.(PPIKSN)

  1. Molecular ecology of anaerobic reactor systems

    DEFF Research Database (Denmark)

    Hofman-Bang, H. Jacob Peider; Zheng, D.; Westermann, Peter

    2003-01-01

    Anaerobic reactor systems are essential for the treatment of solid and liquid wastes and constitute a core facility in many waste treatment plants. Although much is known about the basic metabolism in different types of anaerobic reactors, little is known about the microbes responsible for these ......Anaerobic reactor systems are essential for the treatment of solid and liquid wastes and constitute a core facility in many waste treatment plants. Although much is known about the basic metabolism in different types of anaerobic reactors, little is known about the microbes responsible...... to the abundance of each microbe in anaerobic reactor systems by rRNA probing. This chapter focuses on various molecular techniques employed and problems encountered when elucidating the microbial ecology of anaerobic reactor systems. Methods such as quantitative dot blot/fluorescence in-situ probing using various...

  2. Nuclear reactor types

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    The characteristics of different reactor types designed to exploit controlled fission reactions are explained. Reactors vary from low power research devices to high power devices especially designed to produce heat, either for direct use or to produce steam to drive turbines to generate electricity or propel ships. A general outline of basic reactors (thermal and fast) is given and then the different designs considered. The first are gas cooled, including the Magnox reactors (a list of UK Magnox stations and reactor performance is given), advanced gas cooled reactors (a list of UK AGRs is given) and the high temperature reactor. Light water cooled reactors (pressurized water [PWR] and boiling water [BWR] reactors) are considered next. Heavy water reactors are explained and listed. The pressurized heavy water reactors (including CANDU type reactors), boiling light water, steam generating heavy water reactors and gas cooled heavy water reactors all come into this category. Fast reactors (liquid metal fast breeder reactors and gas cooled fast reactors) and then water-cooled graphite-moderated reactors (RBMK) (the type at Chernobyl-4) are discussed. (U.K.)

  3. Thermohydraulics of reactors

    International Nuclear Information System (INIS)

    Delhaye, J.M.

    2008-01-01

    This scientific and technical handbook about PWR reactors thermohydraulics is the result of many years of teaching in the framework of the CEA-INSTN's atomic engineering training courses, in engineering schools and during continuing training activities. Its main goal is to present in a rigorous and pedagogical way the basic knowledge necessary for the understanding and modeling of single phase and two-phase thermohydraulic phenomena encountered during the design and operation of nuclear reactors. In particular, heat transfers in two-phase flows are presented in a detailed way. Most chapters include some nuclear engineering examples of application of the studied concepts, and some exercises aiming at mastering these concepts. Each example or exercise is accompanied by its detailed solution. Content: - thermohydraulic characteristics of reactors; - design and thermal dimensioning of reactors; - thermal engineering of the fuel element; - two-phase flow configurations in ducts; - recalls about single-phase flow equations; - basic equations for two-phase flows; - modeling of two-phase flows inside ducts; - pressure drops in ducts; - boiling and vapor condensation heat transfers; - two-phase flow instabilities in ducts; - two-phase flow blocking; thermohydraulics of naval propulsion reactors

  4. Improving collaborative play between children with autism spectrum disorders and their siblings : the effectiveness of a robot-mediated intervention based on lego (R) therapy

    NARCIS (Netherlands)

    Huskens, Bibi; Palmen, Annemiek; Van der Werff, Marije; Lourens, Tino; Barakova, Emilia

    2015-01-01

    The aim of the study was to investigate the effectiveness of a brief robot-mediated intervention based on Lego(A (R)) therapy on improving collaborative behaviors (i.e., interaction initiations, responses, and play together) between children with ASD and their siblings during play sessions, in a

  5. High-temperature and breeder reactors - economic nuclear reactors of the future

    International Nuclear Information System (INIS)

    Djalilzadeh, A.M.

    1977-01-01

    The thesis begins with a review of the theory of nuclear fission and sections on the basic technology of nuclear reactors and the development of the first generation of gas-cooled reactors applied to electricity generation. It then deals in some detail with currently available and suggested types of high temperature reactor and with some related subsidiary issues such as the coupling of different reactor systems and various schemes for combining nuclear reactors with chemical processes (hydrogenation, hydrogen production, etc.), going on to discuss breeder reactors and their application. Further sections deal with questions of cost, comparison of nuclear with coal- and oil-fired stations, system analysis of reactor systems and the effect of nuclear generation on electricity supply. (C.J.O.G.)

  6. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

    This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light wate

  7. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    This module describes the general design, characteristics and parameters of TRIGA reactors and fuels. It is recommended that most of this information should be incorporated into any reactor operator training program and, in many cases, the facility Safety Analysis Report. It is oriented to teach the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and the differences between TRIGA fuels and others more traditional reactor fuels. (nevyjel)

  8. REACTOR: an expert system for diagnosis and treatment of nuclear reactor accidents

    International Nuclear Information System (INIS)

    Nelson, W.R.

    1982-01-01

    REACTOR is an expert system under development at EG and G Idaho, Inc., that will assist operators in the diagnosis and treatment of nuclear reactor accidents. This paper covers the background of the nuclear industry and why expert system technology may prove valuable in the reactor control room. Some of the basic features of the REACTOR system are discussed, and future plans for validation and evaluation of REACTOR are presented. The concept of using both event-oriented and function-oriented strategies for accident diagnosis is discussed. The response tree concept for representing expert knowledge is also introduced

  9. Development of small and medium integral reactor. ctor Development of fluid system design for small and medium integral reactor

    International Nuclear Information System (INIS)

    Lee, D. J.; Chang, M. H.; Kim, K. K.; Kim, J. P.; Yoon, J. H.; Lee, Y. J.; Park, C. T.; Bae, Y. Y.; Kang, D. J.; Lee, K. H.; Lee, J.; Kim, H. Y.; Cho, B. H.; Seo, J. K.; Kang, K. S.; Kang, H. O.

    1997-07-01

    The purpose of this study is to develop system design technology of integral reactor, as a new design concept of small and medium reactor having enhanced safety and economy, and to have a design assessment / verification technology through basic thermal hydraulic experiments. This report describes of the following: 1) basic requirement for the integral reactor system design 2) Conceptual design of primary and secondary circuits of NSSS, emergency core cooling system, passive residual heat removal system, severe accident mitigation cooling system, passive residual heat removal system, severe accident mitigation system and other auxiliary system 3) Requirements and test program for the basic thermal hydraulic experiments including, CHF test for hexagonal fuel assembly, flow instability for once-through steam generator, core flow distribution test and verification test for non-condensable gas model in RELAP-5 code. The results of this study can be utilized for using as the foundation technology of in the next basic design phase and design technology for future advanced reactors. (author). 30 refs.,24 tabs., 56 figs

  10. Development of small and medium integral reactor. ctor Development of fluid system design for small and medium integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, D. J.; Chang, M. H.; Kim, K. K.; Kim, J. P.; Yoon, J. H.; Lee, Y. J.; Park, C. T.; Bae, Y. Y.; Kang, D. J.; Lee, K. H.; Lee, J.; Kim, H. Y.; Cho, B. H.; Seo, J. K.; Kang, K. S.; Kang, H. O.

    1997-07-01

    The purpose of this study is to develop system design technology of integral reactor, as a new design concept of small and medium reactor having enhanced safety and economy, and to have a design assessment / verification technology through basic thermal hydraulic experiments. This report describes of the following: (1) basic requirement for the integral reactor system design (2) Conceptual design of primary and secondary circuits of NSSS, emergency core cooling system, passive residual heat removal system, severe accident mitigation cooling system, passive residual heat removal system, severe accident mitigation system and other auxiliary system (3) Requirements and test program for the basic thermal hydraulic experiments including, CHF test for hexagonal fuel assembly, flow instability for once-through steam generator, core flow distribution test and verification test for non-condensable gas model in RELAP-5 code. The results of this study can be utilized for using as the foundation technology of in the next basic design phase and design technology for future advanced reactors. (author). 30 refs.,24 tabs., 56 figs.

  11. Present status and future prospect of research reactors

    International Nuclear Information System (INIS)

    Takemi, Hirokatsu

    1996-01-01

    The present status of research reactors more than MW class reactor in JAERI and the Kyoto University and the small reactors in the Musashi Institute of Technology, the Rikkyo University, the Tokyo University, the Kinki University and other countries are explained in the paper. The present status of researches are reported by the topics in each field. The future researches of the beam reactor and the irradiation reactor are reviewed. On various kinds of use of research reactor and demands of neutron field of a high order, new type research reactors under investigation are explained. Recently, the reactors are used in many fields such as the basic science: the basic physics, the material science, the nuclear physics, and the nuclear chemistry and the applied science; the earth and environmental science, the biology and the medical science. (S.Y.)

  12. ESTUDIO Y MODELADO DE UN BRAZO ROBÓTICO LEGO DE TRES GRADOS DE LIBERTAD

    Directory of Open Access Journals (Sweden)

    JAIME ALBERTO GUZMÁN

    2011-12-01

    Full Text Available En este artículo se presenta el estudio y modelado de un brazo robótico lego de tres grados de libertad en asocio con sus respectivos modelos de su cinemática directa e inversa junto con una aproximación al análisis dinámico para la generación de trayectorias de este robot. Las ecuaciones que rigen el movimiento son deducidas de los modelos matemáticos propios a las cadenas cinemáticas y son implementadas en el lenguaje de programación Java y ejecutadas por el robot a través de la extensión Java -LeJOS.

  13. Determining suitable lego-structures to estimate stability of larger peptide nanostructures using computational methods.

    Science.gov (United States)

    Beke, Tamás; Czajlik, András; Csizmadia, Imre G; Perczel, András

    2006-02-02

    Nanofibers, nanofilms and nanotubes constructed of one to four strands of oligo-alpha- and oligo-beta-peptides were obtained by using carefully selected building units. Lego-type approaches based on thermoneutral isodesmic reactions can be used to reconstruct the total energies of both linear and tubular periodic nanostructures with acceptable accuracy. Total energies of several different nanostructures were accurately determined with errors typically falling in the subchemical range. Thus, attention will be focused on the description of suitable isodesmic reactions that have enabled the determination of the total energy of polypeptides and therefore offer a very fast, efficient and accurate method to obtain energetic information on large and even very large nanosystems.

  14. Lego Robots & Autism Spectrum Disorder: a potential partnership?

    Directory of Open Access Journals (Sweden)

    Sandra Costa

    2016-06-01

    Full Text Available Individuals with autism spectrum disorder (ASD present difficulties in developing social behaviours, in communicating gestural or verbally, and they may present some repetitive motor activities. The objective of this study was to improve social competences and to enable the transfer of acquired skills of five children with ASD and intellectual disabilities using a low-cost Lego robot as a mediator. The proposed methodology was divided in five phases: Familiarization, Pre-test, Practice, Post-Test and Transfer of Skills. The study ran in two sequential periods at different places. Each of these periods tackled different individual research questions and goals (taking into account the target group. During each period, the proposed methodology had to be adjusted according to the current context. Therefore, different experimental scenarios and corresponding specific goals had to be delineated. Results show that joint attention of the children increased over the sessions; and interaction with the researcher was verified. Furthermore, results show that there was an effective transfer of skills in the addressed case studies. This reinforces conclusions that robots seem, in fact, powerful tools that should be explored concerning this target population. But a more detailed study is required. The proposed methodology can be used by professionals and parents as a complement to common interventions.

  15. Reactor plant for Belene NPP completion

    International Nuclear Information System (INIS)

    Dragunov, Yu. G.; Ryzhov, S. B.; Ermakov, D. N.; Repin, A. I.

    2004-01-01

    Construction of 'Belene' NPP was started at the end of 80-ties using project U-87 with V-320 reactor plant, general designer of this plant is OKB 'Gidropress'. At the beginning of 90-ties, on completing the considerable number of deliveries and performance of civil engineering work at the site the NPP construction was suspended. Nowadays, considering the state of affairs at the site and the work performed by Bulgarian Party on preservation of the equipment delivered, the most perspective is supposed to be implementation of the following versions in completing 'Belene' NPP: for completion of Unit 1 - reactor plant VVER-1000 on the basis of V-320 reactor with the maximum use of the delivered equipment (V-320M) having the extended service life and safety improvement; for Unit 2 - advanced reactor plant VVER-1000. For the upgraded reactor plant V-230M the basic solutions and characteristics are presented, as well as the calculated justification of strength and safety analyses, design of the reactor core and fuel cycle, instrumentation and control systems, application of the 'leak-before break' in the project and implementation of safety measures. For the modernised reactor plant V-392M the main characteristics and basic changes are presented, concerning reactor pressure vessel, steam generator, reactor coolant pump set. Design of NPP with the modernized reactor plant V-320M meets the up-to-date requirements and can be licensed for completion and operation. In the design of NPP with the advanced reactor plant the basic solutions and the equipment are used that are similar to those used in standard reactor plant V-320 and new one with VVER-1000 under construction and completion in Russia, and abroad. Compliance of reactor design with the up-to-date international requirements, considering the extended service life of the main equipment, shows its rather high potential for implementation during completion of 'Belene' NPP

  16. The market for research reactors

    International Nuclear Information System (INIS)

    Roegler, H.J.

    1986-01-01

    The assay deals with some basic questions if there is an international market for research reactors at all, which influencing factors affect this market, and if research reactors have any effects on the future market for nuclear engineering. (UA) [de

  17. Safety research basic plan of JNC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Japan Nuclear Cycle Development Institute (JNC) formally succeeded to Power Reactor and Nuclear Fuel Development Corporation (PNC) on October, 1 1998. This report describes the basic plan for major program of JNC which consists of two parts: management philosophy of the new institute and the latest revised medium term program. In the first part, the primary mission of JNC is to perform its R and D concentrating on fast breeder reactor and its fuel cycle, and treatment and disposal of high-level radioactive wastes, while at the same time giving special consideration to safety. In the second, individual programs in the new basic plan are discussed in detail. The outline and schedule of each program are also attached in the table form. (H. Itami)

  18. Fast reactors in nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Kazachkovskii, O

    1981-02-01

    The possible applications are discussed of fast reactor nuclear power plants. Basic differences are explained in fast and thermal reactors, mainly with a view to nuclear fuel utilization. Discussed in more detail are the problems of nuclear fuel reproduction and the nost important technical problems of fast reactors. Flow charts are shown of heat transfer for fast reactors BN-350 (loop design) and BN-600 (integral coolant circuit design). Main specifications are given for demonstration and power fast reactors in operation, under construction and in project-stage.

  19. Improving Collaborative Play between Children with Autism Spectrum Disorders and Their Siblings: The Effectiveness of a Robot-Mediated Intervention Based on Lego® Therapy

    Science.gov (United States)

    Huskens, Bibi; Palmen, Annemiek; Van der Werff, Marije; Lourens, Tino; Barakova, Emilia

    2015-01-01

    The aim of the study was to investigate the effectiveness of a brief robot-mediated intervention based on Lego® therapy on improving collaborative behaviors (i.e., interaction initiations, responses, and play together) between children with ASD and their siblings during play sessions, in a therapeutic setting. A concurrent multiple baseline design…

  20. LEGO-NMR spectroscopy: a method to visualize individual subunits in large heteromeric complexes.

    Science.gov (United States)

    Mund, Markus; Overbeck, Jan H; Ullmann, Janina; Sprangers, Remco

    2013-10-18

    Seeing the big picture: Asymmetric macromolecular complexes that are NMR active in only a subset of their subunits can be prepared, thus decreasing NMR spectral complexity. For the hetero heptameric LSm1-7 and LSm2-8 rings NMR spectra of the individual subunits of the complete complex are obtained, showing a conserved RNA binding site. This LEGO-NMR technique makes large asymmetric complexes accessible to detailed NMR spectroscopic studies. © 2013 The Authors. Published by Wiley-VCH Verlag GmbH & Co. KGaA. This is an open access article under the terms of Creative Commons the Attribution Non-Commercial NoDerivs License, which permits use and distribution in any medium, provided the original work is properly cited, the use is non-commercial and no modifications or adaptations are made.

  1. Reactor coolant cleanup device

    International Nuclear Information System (INIS)

    Igarashi, Noboru.

    1986-01-01

    Purpose: To enable to introduce reactor water at high temperature and high pressure as it is, as well as effectively adsorb to eliminate cobalt in reactor water. Constitution: The coolant cleanup device comprises a vessel main body inserted to coolant pipeway circuits in a water cooled reactor power plant and filters contained within the vessel main body. The filters are prepared by coating and baking powder of metal oxides such as manganese ferrite having a function capable of adsorbing cobalt in the coolants onto the surface of supports made of metals or ceramics resistant to strong acids and alkalies in the form of three-dimensional network structure, for example, zircaloy-2, SUS 303 and the zirconia (baking) to form a basic filter elements. The basic filter elements are charged in plurality to the vessel main body. (Kawaiami, Y.)

  2. Possible fusion reactor

    International Nuclear Information System (INIS)

    Yoshikawa, S.

    1976-05-01

    A scheme to improve performance characteristics of a tokamak-type fusion reactor is proposed. Basically, the tokamak-type plasma could be moved around so that the plasma could be heated by compression, brought to the region where the blanket surrounds the plasma, and moved so as to keep wall loading below the acceptable limit. This idea should be able to help to economize a fusion reactor

  3. Structural insight into RNA recognition motifs: versatile molecular Lego building blocks for biological systems.

    Science.gov (United States)

    Muto, Yutaka; Yokoyama, Shigeyuki

    2012-01-01

    'RNA recognition motifs (RRMs)' are common domain-folds composed of 80-90 amino-acid residues in eukaryotes, and have been identified in many cellular proteins. At first they were known as RNA binding domains. Through discoveries over the past 20 years, however, the RRMs have been shown to exhibit versatile molecular recognition activities and to behave as molecular Lego building blocks to construct biological systems. Novel RNA/protein recognition modes by RRMs are being identified, and more information about the molecular recognition by RRMs is becoming available. These RNA/protein recognition modes are strongly correlated with their biological significance. In this review, we would like to survey the recent progress on these versatile molecular recognition modules. Copyright © 2012 John Wiley & Sons, Ltd.

  4. Advanced modularity design for the MIT pebble bed reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kadak, Andrew C. [Department of Nuclear Engineering, Massachusetts Institute of Technology, 77 Massachusetts Avenue, 24-202 Cambridge, MA 02139-4307 (United States)]. E-mail: kadak@mit.edu; Berte, Marc V. [Department of Nuclear Engineering, Massachusetts Institute of Technology, 77 Massachusetts Avenue, 24-202 Cambridge, MA 02139-4307 (United States)]. E-mail: mvberte@yahoo.com

    2006-03-15

    The future of all reactors will depend on whether they can be economically built and operated. One of the major impediments to new nuclear construction is the capital cost due in large part to the length of construction time and complexity of the plant. Pebble bed reactors offer the opportunity to reduce the complexity of the plant because the number of safety systems required is significantly reduced due to the inherent safety of the technology. However, because of its small size, the capital cost per kilowatt is likely to be large if traditional construction approaches are followed. This strongly suggests the need for innovative construction concepts to reduce the construction time and cost. MIT has proposed a modularity approach in which the plant is pre-built in space-frame type modules which are built in factories. These space frames would contain all the equipment contained in a given volume. Once equipment in the space frame is installed, the space frame would then be shipped to the site and assembled 'lego-style.' Studies presently underway have demonstrated the feasibility of the concept. Thermal stress analysis has been performed and an integrated design with the space frames has been developed. It is expected that this modularity approach will significantly shorten construction time and expense. This paper proposes a concept for further development, not a final design for the entire plant.

  5. Advanced modularity design for the MIT pebble bed reactor

    International Nuclear Information System (INIS)

    Kadak, Andrew C.; Berte, Marc V.

    2006-01-01

    The future of all reactors will depend on whether they can be economically built and operated. One of the major impediments to new nuclear construction is the capital cost due in large part to the length of construction time and complexity of the plant. Pebble bed reactors offer the opportunity to reduce the complexity of the plant because the number of safety systems required is significantly reduced due to the inherent safety of the technology. However, because of its small size, the capital cost per kilowatt is likely to be large if traditional construction approaches are followed. This strongly suggests the need for innovative construction concepts to reduce the construction time and cost. MIT has proposed a modularity approach in which the plant is pre-built in space-frame type modules which are built in factories. These space frames would contain all the equipment contained in a given volume. Once equipment in the space frame is installed, the space frame would then be shipped to the site and assembled 'lego-style.' Studies presently underway have demonstrated the feasibility of the concept. Thermal stress analysis has been performed and an integrated design with the space frames has been developed. It is expected that this modularity approach will significantly shorten construction time and expense. This paper proposes a concept for further development, not a final design for the entire plant

  6. Neutron transport. Physics and calculation of nuclear reactors with applications to pressurized water reactors and fast neutron reactors. 2 ed.

    International Nuclear Information System (INIS)

    Bussac, J.; Reuss, P.

    1985-01-01

    This book presents the main physical bases of neutron theory and nuclear reactor calculation. 1) Interactions of neutrons with matter and basic principles of neutron transport; 2) Neutron transport in homogeneous medium and the neutron field: kinetic behaviour, slowing-down, resonance absorption, diffusion equation, processing methods; 3) Theory of a reactor constituted with homogeneous zones: critical condition, kinetics, separation of variables, calculation and neutron balance of the fundamental mode, one-group and multigroup theories; 4) Study of heterogeneous cell lattices: fast fission factor, resonance absorption, thermal output factor, diffusion coefficient, computer codes; 5) Operation and control of reactors: perturbation theory, reactivity, fuel properties evolution, poisoning by fission products, calculation of a reactor and fuel management; 6) Study of some types of reactors: PWR and fast breeder reactors, the main reactor types of the present French program [fr

  7. Proceeding of the Scientific Meeting and Presentation on Basic Research of Nuclear Science and Technology: Book I. Physics, Reactor Physics and Nuclear Instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    The proceeding contains papers presented on Scientific Meeting and Presentation on on Basic Research of Nuclear Science and Technology, held in Yogyakarta, 25-27 April 1995. This proceeding is part one from two books published for the meeting contains papers on Physics, Reactor Physics and Nuclear Instrumentation as results of research activities in National Atomic Energy Agency. There are 39 papers indexed individually. (ID)

  8. Dorello's Canal for Laymen: A Lego-Like Presentation.

    Science.gov (United States)

    Ezer, Haim; Banerjee, Anirban Deep; Thakur, Jai Deep; Nanda, Anil

    2012-06-01

    Objective Dorello's canal was first described by Gruber in 1859, and later by Dorello. Vail also described the anatomy of Dorello's canal. In the preceding century, Dorello's canal was clinically important, in understanding sixth nerve palsy and nowadays it is mostly important for skull base surgery. The understanding of the three dimensional anatomy, of this canal is very difficult to understand, and there is no simple explanation for its anatomy and its relationship with adjacent structures. We present a simple, Lego-like, presentation of Dorello's canal, in a stepwise manner. Materials and Methods Dorello's canal was dissected in five formalin-fixed cadaver specimens (10 sides). The craniotomy was performed, while preserving the neural and vascular structures associated with the canal. A 3D model was created, to explain the canal's anatomy. Results Using the petrous pyramid, the sixth nerve, the cavernous sinus, the trigeminal ganglion, the petorclival ligament and the posterior clinoid, the three-dimensional structure of Dorello's canal was defined. This simple representation aids in understanding the three dimensional relationship of Dorello's canal to its neighboring structures. Conclusion Dorello's canal with its three dimensional structure and relationship to its neighboring anatomical structures could be reconstructed using a few anatomical building blocks. This method simplifies the understanding of this complex anatomical structure, and could be used for teaching purposes for aspiring neurosurgeons, and anatomy students.

  9. Upgradation of Apsara reactor

    International Nuclear Information System (INIS)

    Mammen, S.; Mukherjee, P.; Bhatnagar, A.; Sasidharan, K.; Raina, V.K.

    2009-01-01

    Apsara is a 1 MW swimming pool type research reactor using high enriched uranium as fuel with light water as coolant and moderator. The reactor is in operation for more than five decades and has been extensively used for basic research, radioisotope production, neutron radiography, detector testing, shielding experiments etc. In view of its long service period, it is planned to carry out refurbishment of the reactor to extend its useful life. During refurbishment, it is also planned to upgrade the reactor to a 2 MW reactor to improve its utilization and to upgrade the structure, system and components in line with the current safety standards. This paper gives a brief account of the design features and safety aspects of the upgraded Apsara reactor. (author)

  10. Basic visualization experiments on eutectic reaction of boron carbide and stainless steel under sodium-cooled fast reactor conditions

    International Nuclear Information System (INIS)

    Yamano, Hidemasa; Suzuki, Tohru; Kamiyama, Kenji; Kudo, Isamu

    2016-01-01

    This paper describes basic visualization experiments on eutectic reaction and relocation of boron carbide (B 4 C) and stainless steel (SS) under a high temperature condition exceeding 1500degC as well as the importance of such behaviors in molten core during a core disruptive accident in a Generation-IV sodium-cooled fast reactor (750 MWe class) designed in Japan. At first, a reactivity history was calculated using an exact perturbation calculation tool taking into account expected behaviors. This calculation indicated the importance of a relocation behavior of the B 4 C-SS eutectic because its behavior has a large uncertainty in the reactivity history. To clarify this behavior, basic experiments were carried out by visualizing the reaction of a B 4 C pellet contacted with molten SS in a high temperature-heating furnace. The experiments have shown the eutectic reaction visualization as well as freezing and relocation of the B 4 C-SS eutectic in upper part of the solidified test piece due to the density separation. (author)

  11. Exploitation questions regarding channel type reactors: water graphite channel reactors (operation, reconstruction, advantages and disadvantages)

    International Nuclear Information System (INIS)

    Chichindaev, D.A.

    2001-01-01

    An overview of up-grade of the RBMK-type reactors is given. I this paper the core design and core monitoring, pressure boundary integrity, RBMK basic design and safety improvements emergency core cooling system (ECCS) as well as reactor cavity overpressure protection system (RCOPS) are discussed

  12. Basic policy of maintenance for the power conversion system of the gas turbine high temperature reactor 300 (GTHTR300)

    International Nuclear Information System (INIS)

    Kosugiyama, Shinichi; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, Xing; Katanishi, Shoji; Takada, Shoji

    2003-01-01

    Basic policy of maintenance was determined for major equipment in the power conversion system of the Gas Turbine High Temperature Reactor 300 (GTHTR300). It was developed based on the current maintenance practice in Light Water Reactors (LWRs), High Temperature Engineering Test Reactor (HTTR) and conventional combined cycle power plants while taking into account of unique design features of GTHTR300. First, potential degradation phenomena in operations were identified and corresponding maintenance approaches were proposed for the equipment. Such degradations encountered typically in LWRs as corrosion, erosion and stress corrosion cracking are unlikely to occur since the working fluid of GTHTR300 is inert helium. Main causes of the degradations are high operating temperature and pressure. The gas turbine, compressor, generator, control valves undergo opening and dismantling maintenance in a suitable time interval. The power conversion vessel, heat exchanger vessel, primary system piping and heat exchanging tubes of precooler are subjected to in-service inspections similar to those done in LWRs. As turbine blades represent the severest material degradation because of their high-temperature and high-stress operating conditions, a lifetime management scheme was suggested for them. The longest interval of open-casing maintenance of the gas turbine is estimated to be six to seven years from technical point of view. Present study is entrusted from the Ministry of Education, Culture, Sports, Science and Technology of Japan. (author)

  13. A PC-based high temperature gas reactor simulator for Indonesian conceptual HTR reactor basic training

    Science.gov (United States)

    Syarip; Po, L. C. C.

    2018-05-01

    In planning for nuclear power plant construction in Indonesia, helium cooled high temperature reactor (HTR) is favorable for not relying upon water supply that might be interrupted by earthquake. In order to train its personnel, BATAN has cooperated with Micro-Simulation Technology of USA to develop a 200 MWt PC-based simulation model PCTRAN/HTR. It operates in Win10 environment with graphic user interface (GUI). Normal operation of startup, power maneuvering, shutdown and accidents including pipe breaks and complete loss of AC power have been conducted. A sample case of safety analysis simulation to demonstrate the inherent safety features of HTR was done for helium pipe break malfunction scenario. The analysis was done for the variation of primary coolant pipe break i.e. from 0,1% - 0,5 % and 1% - 10 % helium gas leakages, while the reactor was operated at the maximum constant power of 10 MWt. The result shows that the highest temperature of HTR fuel centerline and coolant were 1150 °C and 1296 °C respectively. With 10 kg/s of helium flow in the reactor core, the thermal power will back to the startup position after 1287 s of helium pipe break malfunction.

  14. The Effect of Scratch- and Lego Mindstorms Ev3-Based Programming Activities on Academic Achievement, Problem-Solving Skills and Logical-Mathematical Thinking Skills of Students

    Science.gov (United States)

    Korkmaz, Özgen

    2016-01-01

    The aim of this study was to investigate the effect of the Scratch and Lego Mindstorms Ev3 programming activities on academic achievement with respect to computer programming, and on the problem-solving and logical-mathematical thinking skills of students. This study was a semi-experimental, pretest-posttest study with two experimental groups and…

  15. Tests for validation of fast neutron reactors safety

    International Nuclear Information System (INIS)

    Nagata, T.; Yamashita, H.

    2001-01-01

    Japanese scientific research and design enterprises in cooperation with industrial and power generating corporations implement a project on creating a fast neutron reactor of the ultimate safety. One of the basic expected results from such a development is creation of a reactor core structure that is able to eliminate recriticality occurrence in the course of reactor accident involving fuel melting. One of the possible ways to solve this problem is to include pipes (meant for specifying directed (controlled) molten fuel relocation) into fuel assembly structure. In the course of conduction and subsequent implementation of such a design the basic issue is to experimentally confirm the operating capacity of FA having such a structure and that is called FAIDUS. Within EAGLE Project on experimental basis of IAE NNC RK an activity has been started on preparation and conduction of out-of-pile and in-pile tests. During tests a sodium coolant will be used. Studies are conducted by NNC RK in cooperation with the Japanese corporations JAPC and JNC. Basic objective of out-of-pile tests was to obtain preliminary information on fuel relocation behavior under conditions simulating accident involving melting of core consisting of FAIDUS FA, which will help to clarify simulation criteria and to develop the most optimum structure of the experimental channel for reactor experiments conduction. The basic objective of in-pile tests was the experimental confirmation of operating capacity of FAIDUS FA model under reactor conditions. According to the program two tests are planned to be performed at IGR reactor: tests for validation of fast neutron reactor safety, and out-of-pile tests at EAGLE experimental facility without sodium coolant

  16. Calculation Sheet for the Basic Design of the ATLAS Fluid System

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun Sik; Moon, S. K.; Yun, B. J.; Kwon, T. S.; Choi, K. Y.; Cho, S.; Park, C. K.; Lee, S. J.; Kim, Y. S.; Song, C. H.; Baek, W. P.; Hong, S. D

    2007-03-15

    The basic design of an integral effect test loop for pressurized water reactors (PWRs), the ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been carried out by Thermal-Hydraulics Safety Research Team in Korea Atomic Energy Research Institute (KAERI). The ATLAS facility has been designed to have the length scale of 1/2 and area scale of 1/144 compared with the reference plant, APR1400, and is scaled for full pressure and temperature conditions. This report includes calculation sheets for the basic design of ATLAS fluid systems, which are consisted of a reactor pressure vessel with core simulator, the primary loop piping, a pressurizer, reactor coolant pumps, steam generators, the secondary system, the safety system, the auxiliary system, and the heat loss compensation system. The present calculation sheets will be used to help understanding the basic design of the ATLAS fluid system and its based scaling methodology.

  17. Calculation Sheet for the Basic Design of the ATLAS Fluid System

    International Nuclear Information System (INIS)

    Park, Hyun Sik; Moon, S. K.; Yun, B. J.; Kwon, T. S.; Choi, K. Y.; Cho, S.; Park, C. K.; Lee, S. J.; Kim, Y. S.; Song, C. H.; Baek, W. P.; Hong, S. D.

    2007-03-01

    The basic design of an integral effect test loop for pressurized water reactors (PWRs), the ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been carried out by Thermal-Hydraulics Safety Research Team in Korea Atomic Energy Research Institute (KAERI). The ATLAS facility has been designed to have the length scale of 1/2 and area scale of 1/144 compared with the reference plant, APR1400, and is scaled for full pressure and temperature conditions. This report includes calculation sheets for the basic design of ATLAS fluid systems, which are consisted of a reactor pressure vessel with core simulator, the primary loop piping, a pressurizer, reactor coolant pumps, steam generators, the secondary system, the safety system, the auxiliary system, and the heat loss compensation system. The present calculation sheets will be used to help understanding the basic design of the ATLAS fluid system and its based scaling methodology

  18. Progress report of the French program, and basic design of the Jules Horowitz reactor

    International Nuclear Information System (INIS)

    Ballagny, A.

    1998-01-01

    Since the SILOE reactor was shutdown on December 23, 1997, France has been entirely depending on the OSIRIS reactor to conduct the material and fuel irradiation programmes necessary to the evolution of its nuclear power plants and to prepare the future by analysing further reactor designs which might originate in other strategies, namely in the fuel cycle field. The Jules Horowitz reactor, which operation scheduled to start in 2006, will last 50 years, must cover all irradiation needs including, as far as possible, those related to fast breeder reactor studies, more particularly since the SUPERPHENIX reactor shutdown was announced. RJH reactor studies therefore focus on the increase of flux levels and the search for the limit performance of U 3 Si 2 based MTR fuels. (author)

  19. Modelling aerosol behavior in reactor cooling systems

    International Nuclear Information System (INIS)

    McDonald, B.H.

    1990-01-01

    This paper presents an overview of some of the areas of concern in using computer codes to model fission-product aerosol behavior in the reactor cooling system (RCS) of a water-cooled nuclear reactor during a loss-of-coolant accident. The basic physical processes that require modelling include: fission product release and aerosol formation in the reactor core, aerosol transport and deposition in the reactor core and throughout the rest of the RCS, and the interaction between aerosol transport processes and the thermalhydraulics. In addition to these basic physical processes, chemical reactions can have a large influence on the nature of the aerosol and its behavior in the RCS. The focus is on the physics and the implications of numerical methods used in the computer codes to model aerosol behavior in the RCS

  20. Investigation of molten salt fast reactor

    International Nuclear Information System (INIS)

    Kubota, Kenichi; Konomura, Mamoru

    2002-01-01

    On survey research for practicability strategy of fast reactor (FR) (phase 1), to extract future practicability image candidates of FR from wide options, in addition to their survey and investigation objects of not only solid fuel reactors of conventional research object but also molten salt reactor as a flowing fuel reactor, investigation on concept of molten salt FR plant was carried out. As a part of the first step of the survey research for practicability strategy, a basic concept on plant centered at nuclear reactor facility using chloride molten salt reactor capable of carrying out U-Pu cycle was examined, to perform a base construction to evaluate economical potential for a practical FBR. As a result, a result could be obtained that because of inferior fuel inventory and heat transmission to those in Na cooling reactor in present knowledge, mass of reactor vessel and intermediate heat exchanger were to widely increased to expect reduction of power generation unit price even on considering cheapness of its fuel cycle cost. Therefore, at present step further investigation on concept design of the chloride molten salt reactor plant system is too early in time, and it is at a condition where basic and elementary researches aiming at upgrading of economical efficiency such as wide reduction of fuel inventory, a measure expectable for remarkable rationalization effect of reprocessing system integrating a reactor to a processing facility, and so on. (G.K.)

  1. 04 - Sodium cooled fast breeder fourth-generation reactors - The experimental reactor ALLEGRO, the other ways for fast breeder fourth-generation reactors

    International Nuclear Information System (INIS)

    2012-12-01

    The authors first present the technology of gas-cooled fast breeder reactors (basic principles, specific innovations, feasibility studies, fuel element, safety) and notably the ALLEGRO project (design options and expected performances, preliminary safety demonstration). Then, they present the lead-cooled fast-breeder reactor technology: interests and obstacles, return on experience, the issue of lead density, neutron assessment, transmutation potential, dosimetry, safety chemical properties and compatibility with the fuel, water, air and steels. The next part addresses the technology of molten-salt fast-breeder reactors: choice of the liquid fuel and geometry, reactor concept (difficulties, lack of past R and D), demonstration and demonstrators, international context

  2. Fast reactor physics - an overview

    International Nuclear Information System (INIS)

    Lee, S.M.

    2004-01-01

    An introduction to the basic features of fast neutron reactors is made, highlighting the differences from the more conventional thermal neutron reactors. A discussion of important feedback reactivity mechanisms is given. Then an overview is presented of the methods of fast reactor physics, which play an important role in the successful design and operation of fast reactors. The methods are based on three main elements, namely (i) nuclear data bases, (ii) numerical methods and computer codes, and (iii) critical experiments. These elements are reviewed and the present status and future trends are summarized. (author)

  3. Manipulating waves with LEGO{sup ®} bricks: A versatile experimental platform for metamaterial architectures

    Energy Technology Data Exchange (ETDEWEB)

    Celli, Paolo, E-mail: pcelli@umn.edu; Gonella, Stefano, E-mail: sgonella@umn.edu [Department of Civil, Environmental, and Geo- Engineering, University of Minnesota, Minneapolis, Minnesota 55455 (United States)

    2015-08-24

    In this letter, we discuss a versatile, fully reconfigurable experimental platform for the investigation of phononic phenomena in metamaterial architectures. The approach revolves around the use of 3D laser vibrometry to reconstruct global and local wavefield features in specimens obtained through simple arrangements of LEGO{sup ®} bricks on a thin baseplate. The agility by which it is possible to reconfigure the brick patterns into a nearly endless spectrum of topologies makes this an effective approach for rapid experimental proof of concept, as well as a powerful didactic tool, in the arena of phononic crystals and metamaterials engineering. We use our platform to provide a compelling visual illustration of important spatial wave manipulation effects (waveguiding and seismic isolation), and to elucidate fundamental dichotomies between Bragg-based and locally resonant bandgap mechanisms.

  4. Nuclear reactors: physics and materials

    Energy Technology Data Exchange (ETDEWEB)

    Yadigaroglu, G

    2005-07-01

    In the form of a tutorial addressed to non-specialists, the article provides an introduction to nuclear reactor technology and more specifically to Light Water Reactors (LWR); it also shows where materials and chemistry problems are encountered in reactor technology. The basics of reactor physics are reviewed, as well as the various strategies in reactor design and the corresponding choices of materials (fuel, coolant, structural materials, etc.). A brief description of the various types of commercial power reactors follows. The design of LWRs is discussed in greater detail; the properties of light water as coolant and moderator are put in perspective. The physicochemical and metallurgical properties of the materials impose thermal limits that determine the performance and the maximum power a reactor can deliver. (author)

  5. Analysis of dynamic stability and safety of reactor system by reactor simulator; Analiza dinamicke stabilnosti i sigurnosti reaktorskog sistema pomocu reaktorskog simulatora

    Energy Technology Data Exchange (ETDEWEB)

    Raisic, N [Boris Kidric Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)

    1963-11-15

    In order to enable qualitative analysis of dynamic properties of reactors RA and RB, mathematical models of these reactors were formulated and adapted for solution on analog computer. This report contains basic assessments for creating the model and complete equations for each reactor. Model was used to analyse three possible accidents at the RA reactor and possible hypothetical accidents at the RB reactor.

  6. A basic plan of a micro reactor for the promotion of nuclear literacy necessity of the reactor

    International Nuclear Information System (INIS)

    Murata, Takashi; Yoshiki, Nobuya; Kinehara, Yoshiki

    2000-01-01

    It is important for ordinary Japanese to achieve scientific literacy, which enables to understand information appropriately and make their decision reasonably, on science and technology, including nuclear activities. To achieve nuclear literacy, a reactor for interpretation should be established at a science and technology museum, where students, educators and the public would understand functions of an actual reactor and get interests in nuclear activities, so they would understand what nuclear energy is. In this facility, scientists and engineers including pioneers of nuclear activities in Japan should be engaged and provide interpretative contents for various guests, for example, practical operation of the reactor. This facility would be preferred to be established in metropolitan area, where many visitors would be expected to come. Then this facility would be very useful for the achievement of nuclear literacy. (author)

  7. RA Reactor; Reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-02-15

    In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation. [Serbo-Croat] Pored osnovnih karakeristika reaktora RA, organizacije rada i finansijskih pokazatelja, razmatra se stanje opreme reaktora nakon 18 godina rada, pitanja dozvole za rad sa 80% obogacenim gorivom, problem skladistenja isluzenog goriva u bazenu zgrade reaktora i potreba za obnavljanjem komponenti opreme, pre svega elektronske.

  8. Not Your Typical Simulation Workshop: Using LEGOs to Train Medical Students on the Practice of Effective Communication.

    Science.gov (United States)

    Papanagnou, Dimitrios; Lee, Hyunjoo; Rodriguez, Carlos; Zhang, Xiao Chi C; Rudner, Joshua

    2018-01-21

    As students in the health professions transition from the classroom into the clinical environment, they will be expected to effectively communicate with their team members and their patients. Effective communication skills are essential to their ability to effectively contribute to their clinical team and the patient care they deliver. The authors propose an interactive workshop that can support students' deliberate practice of communication skills. The authors designed a simulation workshop that affords students the opportunity to practice their communication and peer-to-peer coaching skills. Using LEGOs, a one-hour workshop was conducted with medical students. Students were divided into groups of two. Each student took on a different role: teacher or builder. Teachers were tasked with instructing builders on how to construct a pre-made LEGO structure, not allowing builders to look at the structure. A group debriefing followed to evaluate the activity and explore the themes that emerged. Twenty first-year medical students and 25 fourth-year medical students participated in this activity. Most groups were successful in reproducing the pre-made structure. Groups that pre-briefed before building were most successful. Unsuccessful groups did not define orientation or direction in mutually understood terms, resulting in the creation of an incorrect mirror image of the structure - a common phenomenon seen during the teaching of procedures in the clinical learning environment. The workshop was well received. Students made requests to have similar sessions throughout their training to better support the development of effective communication skills. The workshop can easily be applied to other specialties to assist with procedural skills instruction or in workshops focusing on effective communication.

  9. Not Your Typical Simulation Workshop: Using LEGOs to Train Medical Students on the Practice of Effective Communication

    Science.gov (United States)

    Lee, Hyunjoo; Rodriguez, Carlos; Zhang, Xiao Chi C; Rudner, Joshua

    2018-01-01

    As students in the health professions transition from the classroom into the clinical environment, they will be expected to effectively communicate with their team members and their patients. Effective communication skills are essential to their ability to effectively contribute to their clinical team and the patient care they deliver. The authors propose an interactive workshop that can support students’ deliberate practice of communication skills. The authors designed a simulation workshop that affords students the opportunity to practice their communication and peer-to-peer coaching skills. Using LEGOs, a one-hour workshop was conducted with medical students. Students were divided into groups of two. Each student took on a different role: teacher or builder. Teachers were tasked with instructing builders on how to construct a pre-made LEGO structure, not allowing builders to look at the structure. A group debriefing followed to evaluate the activity and explore the themes that emerged. Twenty first-year medical students and 25 fourth-year medical students participated in this activity. Most groups were successful in reproducing the pre-made structure. Groups that pre-briefed before building were most successful. Unsuccessful groups did not define orientation or direction in mutually understood terms, resulting in the creation of an incorrect mirror image of the structure – a common phenomenon seen during the teaching of procedures in the clinical learning environment. The workshop was well received. Students made requests to have similar sessions throughout their training to better support the development of effective communication skills. The workshop can easily be applied to other specialties to assist with procedural skills instruction or in workshops focusing on effective communication. PMID:29568715

  10. A PSA study for the SMART basic design

    International Nuclear Information System (INIS)

    Han, Sang Hoon; Kim, H. C.; Yang, S. H.; Lee, D. J.

    2002-03-01

    SMART (System-Integrated Modular Advanced Reactor) is under development that is an advanced integral type small and medium category nuclear power reactor with the rated thermal power of 330 MW. A Probabilistic Safety Analysis (PSA) for the SMART basic design has been performed to evaluate the safety and optimize the design. Currently, the basic design is done and the detailed design is not available for the SMART, we made several assumptions about the system design before performing the PSA. The scope of the PSA was limited to the Level-1 internal full power PSA. The level-2 and 3 PSA, the external PSA, and the low power/shutdown PSA will be performed in the final design stage

  11. Advanced light-water reactors

    International Nuclear Information System (INIS)

    Golay, M.W.; Todreas, N.E.

    1990-01-01

    Environmental concerns, economics and the earth's finite store of fossil fuels argue for a resuscitation of nuclear power. The authors think improved light-water reactors incorporating passive safety features can be both safe and profitable, but only if attention is paid to economics, effective management and rigorous training methods. The experience of nearly four decades has winnowed out designs for four basic types of reactor: the heavy-water reactor (HWR), the gas-cooled rector (GCR), the liquid-metal-cooled reactor (LMR) and the light-water reactor (LWR). Each design is briefly described before the paper discusses the passive safety features of the AP-600 rector, so-called because it employs an advanced pressurized water design and generates 600 MW of power

  12. Basic plans of atomic energy development and utilization for fiscal 1978

    International Nuclear Information System (INIS)

    1978-01-01

    The Government has promoted the development and utilization of atomic energy as one of the most important measures for energy supplies. In Japan, due to the unrest concerning safety of nuclear power, siting of nuclear power plants is difficult, thereby the nuclear power generation program is delayed. Then, in major research and development projects such as those of uranium enrichment, fast breeder reactors, an advanced thermal reactor and nuclear fusion, while the remarkable results are being accumulated, the practical aspects are in need of positive governmental measures. Under this situation, the long range program of atomic energy development and utilization is being revised. For the fiscal year 1978 (from April, 1978 to March, 1979), based on the revision, the basic plans are presented, first, the basic policy, and second, the practical measures: strengthening of the safety measures; establishment of the nuclear fuel cycle; development of the new types of power reactors; promotion of the basic researches; securing of the people's understanding and cooperation. (Mori, K

  13. Proceedings of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Science and Technology part I : Physics and Nuclear Reactor

    International Nuclear Information System (INIS)

    Kusminarto; Sri Juari Santoso; Agus Taftazani; Sudjatmoko; Darsono; Samin; Syarip; Prajitno; Muhadi Ayub Wasitho; Sukarsono; Tjipto Sujitno; Elisabeth Supriyatni

    2009-07-01

    The Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Accelerator Technology and Material Process, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. The proceedings contains papers presented on scientific meeting about Physics and Nuclear Reactor. The proceedings is the first part of the three parts which published in series. There are 28 papers. (PPIN)

  14. Reactors of the world

    International Nuclear Information System (INIS)

    1971-01-01

    Basic data relating to 127 power reactors in 15 countries which are expected to be in operation at the end of this year, with a total installed electrical generating capacity of 35 340.15 MW(e), and a listing of 361 research reactors in 46 countries are given in the 1971 edition of the IAEA handbook, Power and Research Reactors in Member States, which has just been published. This edition, the fourth, was prepared especially for the Fourth International Conference on the Peaceful Uses of Atomic Energy. (author)

  15. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1993-09-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The major Department's programs promoted in the year are the assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  16. Reactor engineering department annual report

    International Nuclear Information System (INIS)

    1990-09-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1989 (April 1, 1989 - March 31, 1990). One of major Department's programs is the assessment of the high conversion light water reactor and the design activities of advanced reactor system. Development of a high energy proton linear accelerator for the nuclear engineering including is also TRU incineration promoted. Other major tasks of the Department are various basic researches on nuclear data and group constants, theoretical methods and code development, on reactor physics experiments and analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  17. RA reactor operation and maintenance in 1992, Part 1

    International Nuclear Information System (INIS)

    Sotic, O.; Cupac, S.; Sulem, B.; Zivotic, Z.; Majstorovic, D.; Tanaskovic, M.

    1992-01-01

    During 1992 Ra reactor was not in operation. All the activities were fulfilled according to the previously adopted plan. Basic activities were concerned with revitalisation of the RA reactor and maintenance of reactor components. All the reactor personnel was busy with reconstruction and renewal of the existing reactor systems and building of the new systems, maintenance of the reactor devices. Part of the staff was trained for relevant tasks and maintenance of reactor systems [sr

  18. La reivindicación del saber lego en la defensa de la salud pública: Erin Brockovich

    Directory of Open Access Journals (Sweden)

    Alfredo MENÉNDEZ-NAVARRO

    2016-09-01

    Full Text Available Basada en hechos reales, Erin Brockovich narra la singular labor de esta mujer sin formación legal y un complicado contexto familiar en la preparación y desenlace de una exitosa demanda contra la Pacific Gas and Electric Company por contaminación de aguas de consumo humano con cromo hexavalente en Hinkley (California, EE.UU.. La película permite acercarnos a las estrategias de ocultación de riesgos ambientales de las grandes corporaciones industriales así como reivindicar el valor del conocimiento lego y del empoderamiento de los ciudadanos en la defensa del derecho a la salud.

  19. The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 1: Basic Models

    Science.gov (United States)

    Mosunova, N. A.

    2018-05-01

    The article describes the basic models included in the EUCLID/V1 integrated code intended for safety analysis of liquid metal (sodium, lead, and lead-bismuth) cooled fast reactors using fuel rods with a gas gap and pellet dioxide, mixed oxide or nitride uranium-plutonium fuel under normal operation, under anticipated operational occurrences and accident conditions by carrying out interconnected thermal-hydraulic, neutronics, and thermal-mechanical calculations. Information about the Russian and foreign analogs of the EUCLID/V1 integrated code is given. Modeled objects, equation systems in differential form solved in each module of the EUCLID/V1 integrated code (the thermal-hydraulic, neutronics, fuel rod analysis module, and the burnup and decay heat calculation modules), the main calculated quantities, and also the limitations on application of the code are presented. The article also gives data on the scope of functions performed by the integrated code's thermal-hydraulic module, using which it is possible to describe both one- and twophase processes occurring in the coolant. It is shown that, owing to the availability of the fuel rod analysis module in the integrated code, it becomes possible to estimate the performance of fuel rods in different regimes of the reactor operation. It is also shown that the models implemented in the code for calculating neutron-physical processes make it possible to take into account the neutron field distribution over the fuel assembly cross section as well as other features important for the safety assessment of fast reactors.

  20. Learning Basic Mechatronics through Helicopter Workshop

    OpenAIRE

    Adzly Anuar; Maryam Huda Ahmad Phesal; Azrul Abidin Zakaria; Goh Chin Hock; Sivadass Thiruchelvam; Dickson Neoh Tze How; Muhammad Fahmi Abdul Ghani; Khairul Salleh Mohamed Sahari

    2014-01-01

    In recent years, technologies related to mechatronics and robotics is available even to elementary level students. It is now common to see schools in Malaysia using Lego Mindstorm as a tool for active learning on mechatronics and robotics. A new yet interesting way of learning mechatronics and robotics is introduced by Dr. Dan Barry, a former astronaut and his son Andrew Barry during their visit to Malaysia. The kits used are based on a 4-channel RC helicopter, Arduino Uno microcontroller, IR...

  1. A basic plan of micro reactor for the promotion of nuclear literacy problems in realization of the reactor

    Energy Technology Data Exchange (ETDEWEB)

    Murata, Takashi [Graduate School of Energy Science, Kyoto University, Kyoto (Japan); Yoshiki, Nobuya [Central Research Inst. of Electric Power Industry, Tokyo (Japan); Nakagawa, Haruo [Hitachi Ltd., Tokyo (Japan)

    2001-04-01

    It is difficult for new sciences and big technologies such as life sciences, nuclear energy, biotechnology, etc. to achieve the appropriate public understanding. One of the issues is the lack of scientific literacy in the public. We propose a new type of nuclear reactor to prepare the opportunity for the public to be acquainted with the information and technology of the nuclear science and engineering. This reactor for interpretation is a symbolic facility adjacent to the scientific and technological museum. Features of the interpretative reactor must be safety and openness. The safety is satisfied by the excess reactivity less than 0.5% {delta}k/k and little burn up based on the thermal output less than 1 W. (author)

  2. A basic plan of micro reactor for the promotion of nuclear literacy problems in realization of the reactor

    International Nuclear Information System (INIS)

    Murata, Takashi; Yoshiki, Nobuya; Nakagawa, Haruo

    2001-01-01

    It is difficult for new sciences and big technologies such as life sciences, nuclear energy, biotechnology, etc. to achieve the appropriate public understanding. One of the issues is the lack of scientific literacy in the public. We propose a new type of nuclear reactor to prepare the opportunity for the public to be acquainted with the information and technology of the nuclear science and engineering. This reactor for interpretation is a symbolic facility adjacent to the scientific and technological museum. Features of the interpretative reactor must be safety and openness. The safety is satisfied by the excess reactivity less than 0.5% Δk/k and little burn up based on the thermal output less than 1 W. (author)

  3. Nuclear Capacity Building through Research Reactors

    International Nuclear Information System (INIS)

    2017-01-01

    Four Instruments: •The IAEA has recently developed a specific scheme of services for Nuclear Capacity Building in support of the Member States cooperating research reactors (RR) willing to use RRs as a primary facility to develop nuclear competences as a supporting step to embark into a national nuclear programme. •The scheme is composed of four complementary instruments, each of them being targeted to specific objective and audience: Distance Training: Internet Reactor Laboratory (IRL); Basic Training: Regional Research Reactor Schools; Intermediate Training: East European Research Reactor Initiative (EERRI); Group Fellowship Course Advanced Training: International Centres based on Research Reactors (ICERR)

  4. Physics of high-temperature reactors

    International Nuclear Information System (INIS)

    Massimo, L.

    1976-01-01

    The subject is covered in chapters entitled: general description of the HTR core; general considerations about reactor physics; neutron cross-sections; basic aspects of transport and diffusion theory; methods for the solution of the diffusion equation; slowing-down and thermalization in graphite; resonance absorption; spectrum calculations and cross-section averaging; burn-up; core design; fuel management and cost calculations; temperature coefficient; core dynamics and accident analysis; reactor control; peculiarities of HTR physics; analysis of calculational accuracy; sequence of reactor design calculations. (U.K.)

  5. The advanced MAPLE reactor concept

    International Nuclear Information System (INIS)

    Lidstone, R.F.; Lee, A.G.; Gillespie, G.E.; Smith, H.J.

    1989-01-01

    In Canada the need for advanced neutron sources has long been recognized. During the past several years Atomic Energy of Canada Limited (AECL) has been developing the new MAPLE multipurpose reactor concept. To date, the MAPLE program has focused on the development of a modest-cost multipurpose medium-flux neutron source to meet contemporary requirements for applied and basic research using neutron beams, for small-scale materials testing and analysis and for radioisotope production. The basic MAPLE concept incorporates a compact light-water cooled and moderated core within a heavy water primary reflector to generate strong neutron flux levels in a variety of irradiation facilities. In view of renewed Canadian interest in a high-flux neutron source, the MAPLE group has begun to explore advanced concepts based on AECL's experience with heavy water reactors. The overall objective is to define a high-flux facility that will support materials testing for advanced power reactors, new developments in extracted neutron-beam applications, and/or production of radioisotopes. The design target is to attain performance levels of HFR-Grenoble, HFBR, HFIR in a new heavy water-cooled, -moderated,-reflected reactor based on rodded LEU fuel. Physics, shielding, and thermohydraulic studies have been performed for the MAPLE heavy water reactor. 14 refs., 4 figs., 1 tab

  6. Gas reactor international cooperative program interim report. Pebble bed reactor fuel cycle evaluation

    International Nuclear Information System (INIS)

    1978-09-01

    Nuclear fuel cycles were evaluated for the Pebble Bed Gas Cooled Reactor under development in the Federal Republic of Germany. The basic fuel cycle specified for the HTR-K and PNP is well qualified and will meet the requirements of these reactors. Twenty alternate fuel cycles are described, including high-conversion cycles, net-breeding cycles, and proliferation-resistant cycles. High-conversion cycles, which have a high probability of being successfully developed, promise a significant improvement in resource utilization. Proliferation-resistant cycles, also with a high probability of successful development, compare very favorably with those for other types of reactors. Most of the advanced cycles could be adapted to first-generation pebble bed reactors with no significant modifications

  7. Power reactors in Member States. 1979 edition

    International Nuclear Information System (INIS)

    1979-01-01

    This is the fifth issue of a periodic computer-based listing of nuclear power reactors, presenting the situation as of 1 May 1979. The basic design data for all reactors in operation, under construction, planned and shut down have been included. The following two tables are included to give a general picture of the overall situation: Table I: Reactor types and net electrical power. Table II: Reactor units and net electrical powered by country cummulated by year

  8. General scheme of research reactor mainly for production of fission 99Mo

    International Nuclear Information System (INIS)

    Shen Feng; Liu Xingmin; Wu Xiaochun; Sun Zheng; Guo Chunqiu; Yi Dayong

    2012-01-01

    On the basis of the analysis for current circumstance and development tendency of research reactor mainly for 99 Mo production in the world, the design idea of this sort of research reactor was proposed. By the optimization and basic design, the general design parameters of the reactor were analyzed and testified. The evaluation of output activities of 99 Mo and the analysis of economics were conducted on the basically assumption. It is argued that the economics of this reactor is improved dramatically while the safety is ensured by the analysis. (authors)

  9. QUARTERLY PROGRESS REPORT JANUARY, FEBRUARY, MARCH, 1968 REACTOR FUELS AND MATERIALS DEVELOPMENT PROGRAMS FOR FUELS AND MATERIALS BRANCH OF USAEC DIVISION OF REACTOR DEVELOPMENT AND TECHNOLOGY

    Energy Technology Data Exchange (ETDEWEB)

    Cadwell, J. J.; de Halas, D. R.; Nightingale, R. E.; Worlton, D. C.

    1968-06-01

    Progress is reported in these areas: nuclear graphite; fuel development for gas-cooled reactors; HTGR graphite studies; nuclear ceramics; fast-reactor nitrides research; non-destructive testing; metallic fuels; basic swelling studies; ATR gas and water loop operation and maintenance; reactor fuels and materials; fast reactor dosimetry and damage analysis; and irradiation damage to reactor metals.

  10. Reactor physics computations

    International Nuclear Information System (INIS)

    Shapiro, A.

    1977-01-01

    Those reactor-core calculations which provide the effective multiplication factor (or eigenvalue) and the stationary (or fundamental mode) neutron-flux distribution at selected times during the lifetime of the core are considered. The multiplication factor is required to establish the nuclear composition and configuration which satisfy criticality and control requirements. The steady-state flux distribution must be known to calculate reaction rates and power distributions which are needed for the thermal, mechanical and shielding design of the reactor, as well as for evaluating refueling requirements. The calculational methods and techniques used for evaluating the nuclear design information vary with the type of reactor and with the preferences and prejudices of the reactor-physics group responsible for the calculation. Additionally, new methods and techniques are continually being developed and made operational. This results in a rather large conglomeration of methods and computer codes which are available for reactor analysis. The author provides the basic calculational framework and discusses the more prominent techniques which have evolved. (Auth.)

  11. A fast spectrum dual path flow cermet reactor

    International Nuclear Information System (INIS)

    Anghaie, S.; Feller, G.J.; Peery, S.D.; Parsley, R.C.

    1993-01-01

    A cermet fueled, dual path fast reactor for space nuclear propulsion applications is conceptually designed. The reactor utilizes an outer annulus core and an inner cylindrical core with radial and axial reflector. The dual path flow minimizes the impact of power peaking near the radial reflector. Basic neutronics and core design aspects of the reactor are discussed. The dual path reactor is integrated into a 25000 lbf thrust nuclear rocket

  12. Design characteristics of zero power fast reactor Lasta

    International Nuclear Information System (INIS)

    Milosevic, M.; Stefanovic, D.; Pesic, M.; Popovic, D.; Nikolic, D.; Antic, D.; Zavaljevski, N.

    1987-01-01

    The concept, purpose and preliminary design of a zero power fast reactor LASTA are described. The methods of computing the reactor core parameters and reactor kinetics are presented with the basic calculated results and analysis for one selected LASTA configuration. The nominal parameters are determined according to the selected reactor safety criteria and results of calculations. Important aspects related to the overall safety are examined in detail. (author)

  13. Design and construction of small power reactors

    International Nuclear Information System (INIS)

    Tachi, Yasuo

    1992-01-01

    Small size reactors are considered to have many advantages over large-sized reactors. But at the same time, small size reactors show eventual disadvantages in economy. In this paper one of the possibilities to improve its basic disadvantage will be discussed from a manufacturer's point of view. The stress will be placed on the possibility and possible effects of adoption of Computer Aided Engineering. (author). 2 figs

  14. Collective Value Creation and Empowerment in an Online Brand Community: A Netnographic Study on LEGO Builders

    Directory of Open Access Journals (Sweden)

    Pekka Tuominen

    2012-06-01

    Full Text Available Online communities are becoming “places” of belonging, information, and emotional support that people cannot do without. These social groups have a real existence for their participants, and thus have consequential effects on many aspects of behaviour. This article examines collective value creation and empowerment in an online brand community. It presents the main features of an online brand community, the process of value co-creation, and motivators for participating in online brand communities. These key factors jointly characterize collective value creation and empowerment. This netnographic study focuses on an online brand community called BrickBuilders, which is a meeting place for LEGO builders in Finland. BrickBuilders’ members feel a sense of belonging, they share similar motivations, and they create value together.

  15. The PP1 binding code: a molecular-lego strategy that governs specificity.

    Science.gov (United States)

    Heroes, Ewald; Lesage, Bart; Görnemann, Janina; Beullens, Monique; Van Meervelt, Luc; Bollen, Mathieu

    2013-01-01

    Ser/Thr protein phosphatase 1 (PP1) is a single-domain hub protein with nearly 200 validated interactors in vertebrates. PP1-interacting proteins (PIPs) are ubiquitously expressed but show an exceptional diversity in brain, testis and white blood cells. The binding of PIPs is mainly mediated by short motifs that dock to surface grooves of PP1. Although PIPs often contain variants of the same PP1 binding motifs, they differ in the number and combination of docking sites. This molecular-lego strategy for binding to PP1 creates holoenzymes with unique properties. The PP1 binding code can be described as specific, universal, degenerate, nonexclusive and dynamic. PIPs control associated PP1 by interference with substrate recruitment or access to the active site. In addition, some PIPs have a subcellular targeting domain that promotes dephosphorylation by increasing the local concentration of PP1. The diversity of the PP1 interactome and the properties of the PP1 binding code account for the exquisite specificity of PP1 in vivo. © 2012 The Authors Journal compilation © 2012 FEBS.

  16. Random processes in nuclear reactors

    CERN Document Server

    Williams, M M R

    1974-01-01

    Random Processes in Nuclear Reactors describes the problems that a nuclear engineer may meet which involve random fluctuations and sets out in detail how they may be interpreted in terms of various models of the reactor system. Chapters set out to discuss topics on the origins of random processes and sources; the general technique to zero-power problems and bring out the basic effect of fission, and fluctuations in the lifetime of neutrons, on the measured response; the interpretation of power reactor noise; and associated problems connected with mechanical, hydraulic and thermal noise sources

  17. Cover Feature: LEGO-Inspired Drug Design: Unveiling a Class of Benzo[d]thiazoles Containing a 3,4-Dihydroxyphenyl Moiety as Plasma Membrane H+-ATPase Inhibitors (ChemMedChem 1/2018)

    DEFF Research Database (Denmark)

    Thanh Tung, Truong; Dao, Trong Tuan; Grifell Junyent, Marta

    2018-01-01

    The Cover Feature shows a rational procedure for assembling privileged molecular fragments (like playing with LEGO bricks) to obtain hit structures. We have invented a novel procedure for targeting biological macromolecules possessing a binding site with a poorly known topography. We have coined ......, 2018 (DOI: 10.1002/cmdc.201700635)....

  18. Prospect of realizing nuclear fusion reactors

    International Nuclear Information System (INIS)

    1989-01-01

    This Report describes the results of the research work on nuclear fusion, which CRIEPI has carried out for about ten years from the standpoint of electric power utilities, potential user of its energy. The principal points are; (a) economic analysis (calculation of costs) based on Japanese analysis procedures and database of commercial fusion reactors, including fusion-fission hybrid reactors, and (b) conceptual design of two types of hybrid reactors, that is, fission-fuel producing DMHR (Demonstration Molten-Salt Hybrid Reactor) and electric-power producing THPR (Tokamak Hybrid Power Reactor). The Report consists of the following chapters: 1. Introduction. 2. Conceptual Design of Hybrid Reactors. 3. Economic Analysis of Commercial Fusion Reactors. 4. Basic Studies Applicable Also to Nuclear Fusion Technology. 5. List of Published Reports and Papers; 6. Conclusion. Appendices. (author)

  19. Basic research on high-uranium density fuels for research and test reactors

    International Nuclear Information System (INIS)

    Ugajin, M.; Itoh, A.; Akabori, M.

    1992-01-01

    High-uranium density fuels, uranium silicides (U 3 Si 2 , U 3 Si) and U 6 Me-type uranium alloys (Me = Fe, Mn, Ni), were prepared and examined metallurgically as low-enriched uranium (LEU) fuels for research and test reactors. Miniature aluminum-dispersion plate-type fuel (miniplate) and aluminum-clad disk-type fuel specimens were fabricated and subjected to the neutron irradiation in JMTR (Japan Materials Testing Reactor). Fuel-aluminum compatibility tests were conducted to elucidate the extent of reaction and to identify reaction products. The relative stability of the fuels in an aluminum matrix was established at 350degC or above. Experiments were also performed to predict the chemical form of the solid fission-products in the uranium silicide (U 3 Si 2 ) simulating a high burnup anticipated for reactor service. (author)

  20. Basic nuclear data and reactor shielding design formulaire PROPANE Do

    International Nuclear Information System (INIS)

    Estiot, J.C.; Salvatores, M.; Trapp, J.P.

    1979-01-01

    This paper presents a calculational scheme - formulaire PROPANE - to calculate the deep neutron penetration in the fast reactor shield. The emphasis is put on the multigroup data and method approximations. The performances of this formulaire are presented

  1. Nuclear reactor control column

    International Nuclear Information System (INIS)

    Bachovchin, D.M.

    1982-01-01

    The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest crosssectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor

  2. The integral fast reactor

    International Nuclear Information System (INIS)

    Till, C.E.

    1987-01-01

    On April 3rd, 1986, two dramatic demonstrations of the inherent capability of sodium-cooled fast reactors to survive unprotected loss of cooling accidents were carried out on the experimental sodium-cooled power reactor, EBR-II, on the Idaho site of Argonne National Laboratory. Transients potentially of the most serious kind, one an unprotected loss of flow, the other an unprotected loss of heat sink, both initiated from full power. In both cases the reactor quietly shut itself down, without damage of any kind. These tests were a part of the on-going development program at Argonne to develop an advanced reactor with significant new inherent safety characteristics. Called the Integral Fast Reactor, or IFR, the basic thrust is to develop everything that is needed for a complete nuclear power system - reactor, closed fuel cycle, and waste processing - as a single optimized entity, and, for simplicity in concept, as an integral part of a single plant. The particular selection of reactor materials emphasizes inherent safety characteristics and also makes possible a simplified closed fuel cycle and waste process improvements

  3. Proceedings of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Science and Technology part I : Physics and Nuclear Reactor

    International Nuclear Information System (INIS)

    Kamsul Abraha; Yateman Arryanto; Sri Jauhari S; Agus Taftazani; Kris Tri Basuki; Djoko Sardjono, Ign.; Sukarsono, R.; Samin; Syarip; Suryadi, MS; Sardjono, Y.; Tri Mardji Atmono; Dwiretnani Sudjoko; Tjipto Sujitno, BA.

    2007-08-01

    The Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology is a routine activity held by Centre for Accelerator Technology and Material Process, National Nuclear Energy Agency, for monitoring the research activity which achieved in National Nuclear Energy Agency. The Meeting was held in Yogyakarta on July 10, 2007. The proceedings contains papers presented on the meeting about Physics and Nuclear Reactor and there are 52 papers. The proceedings is the first part of the three parts which published in series. (PPIN)

  4. Conceptual Study for development of a low power research reactor

    International Nuclear Information System (INIS)

    Park, C.; Kim, H. S.; Park, J. H.; Chae, H. T.; Lee, B. C.

    2013-01-01

    Even though the nuclear society is again facing with difficult situations after Fukusima accident, some countries still continues to consider nuclear power as one option of national energy sources and to introduce nuclear energy. As a research reactor has been regarded as a step-stone to establish infrastructures for the nuclear power development program, some countries that have plan to introduce the nuclear power energy are considering to construct a research reactor. Particularly, a low power research reactor whose main purpose is basic researches on the nuclear technology and education/training would be of interest to developing countries when taking the economy and level of science and technology into consideration. And many low power research reactors at operation are obsolescent and their numbers are decreasing. Hence, some concepts on a low power research reactor are being studied for the future needs. This paper presents the conceptual study on the basic requirements and the preliminary design features of a low power research reactor

  5. Safeguards challenges of Fast Breeder Reactor

    International Nuclear Information System (INIS)

    Ko, H. S.

    2010-01-01

    Although the safeguards system of Sodium Fast Reactor (SFR) seems similar to that of Light Water Reactor (LWR), it was raised safeguards challenges of SFR that resulted from the visual opacity of liquid sodium, chemical reactivity of sodium and other characteristics of fast reactor. As it is the basic concept stage of the safeguards of SFR in Korea, this study tried to analyze the latest similar study of safeguards issues of the Fast Breeder Reactor (FBR) at Joyo and Monju in Japan. For this reason, this study is to introduce some potential safeguards challenges of Fast Breeder Reactor. With this analysis, future study could be to address the safeguards challenges of SFR in Korea

  6. AECL programs in basic physics research

    International Nuclear Information System (INIS)

    Bartholomew, G.A.; Dolling, G.; Harvey, M.; Milton, J.C.D.

    1982-02-01

    This report describes the CRNL program of research into the basic properties of atomic nuclei and condensed matter (liquids and solids). Brief descriptions are given of some of the current experimental programs done principally at the NRU reactor and MP tandem accelerator, the associated theoretical studies, and some highlights of past achievements

  7. NEPTUNE: a modular system for light-water reactor calculation

    International Nuclear Information System (INIS)

    Bouchard, J.; Kanevoky, A.; Reuss, P.

    1975-01-01

    A complete modular system of light water reactor calculations has been designed. It includes basic nuclear data processing, the APOLLO phase: transport calculations for cells, multicells, fuel assemblies or reactors, the NEPTUNE phase: reactor calculations. A fuel management module, devoted to the automatic determination of the best shuffling strategy is included in NEPTUNE [fr

  8. 50 years of the RB reactor utilization

    International Nuclear Information System (INIS)

    Milosevic, M.; Pesic, M.; Ljubenov, V.

    2008-01-01

    This paper is dedicated to the 50 th anniversary of the RB reactor operation, which was the first nuclear reactor built in former Yugoslavia. Information about the construction period, basic technical characteristics and experimental possibilities of the facility, description of first experiments performed 50 years ago, utilisation and modifications done during the implementation of different state nuclear programs and the most important research results are presented in the paper. Role of the RB reactor in the forthcoming decommissioning of the RA research reactor and some plans for future utilisation are underlined also. (author)

  9. Characterization of radioactive waste from nuclear power reactors

    International Nuclear Information System (INIS)

    Piumetti, Elsa H.; Medici, Marcela A.

    2007-01-01

    Different kinds of radioactive waste are generated as result of the operation of nuclear power reactors and in all cases the activity concentration of several radionuclides had to be determined in order to optimize resources, particularly when dealing with final disposal or long-term storage. This paper describes the three basic approaches usually employed for characterizing nuclear power reactor wastes, namely the direct methods, the semi-empirical methods and the analytical methods. For some radionuclides or kind of waste, the more suitable method or combination of methods applicable is indicated, stressing that these methods shall be developed and applied during the waste generation step, i.e. during the operation of the reactor. In addition, after remarking the long time span expected from waste generation to their final disposal, the importance of an appropriate record system is pointed out and some basic requirements that should be fulfilled for such system are presented. It is concluded that the tools for a proper characterization of nuclear reactor radioactive waste are available though such tools should be tailored to each specific reactor and their history. (author) [es

  10. Power reactors in member states

    International Nuclear Information System (INIS)

    1975-01-01

    This is the first issue of a periodical computer-based listing of civilian nuclear power reactors in the Member States of the IAEA, presenting the situation as of 1 April 1975. It is intended as a replacement for the Agency's previous annual publication of ''Power and Research Reactors in Member States''. In the new format, the listing contains more information about power reactors in operation, under construction, planned and shut down. As far as possible all the basic design data relating to reactors in operation have been included. In future these data will be included also for other power reactors, so that the publication will serve to give a clear picture of the technical progress achieved. Test and research reactors and critical facilities are no longer listed. Of interest to nuclear power planners, nuclear system designers, nuclear plant operators and interested professional engineers and scientists

  11. DESIGN SAFETY PROBLEMS OF NUCLEAR REACTORS IN SPACE FOR ELECTRICAL POWER

    Energy Technology Data Exchange (ETDEWEB)

    Pickler, D A

    1963-06-15

    A general treatment is presented of some of the problems in the design safety of reactors which are to be operated in space. The basic requirements of these reachigh temperatures. The usual concept of a space reactor is described briefly, and the hazards of an assumed unmanned vehicle with an enriched-U-fueled reactor are examined during its launching, orbit, and reentry. Graphs are given for the dose vs distance downwind for an excursion of 100 Mw-sec, for the activity vs time after shutdown of a reactor which has been operated for 5 yr at 100 kw(t), and for the altitude vs orbital lifetime. Apparent conflicts between the basic requirements are discussed. (D.L.C.)

  12. Small mirror fusion reactors

    International Nuclear Information System (INIS)

    Carlson, G.A.; Schultz, K.R.; Smith, A.C. Jr.

    1978-01-01

    Basic requirements for the pilot plants are that they produce a net product and that they have a potential for commercial upgrade. We have investigated a small standard mirror fusion-fission hybrid, a two-component tandem mirror hybrid, and two versions of a field-reversed mirror fusion reactor--one a steady state, single cell reactor with a neutral beam-sustained plasma, the other a moving ring field-reversed mirror where the plasma passes through a reaction chamber with no energy addition

  13. A new fluidized bed nuclear reactor

    International Nuclear Information System (INIS)

    Sefidvash, F.

    1986-01-01

    A new nuclear reactor design based on the fluidized bed concept is proposed. A current design utilizes spherical fuel of slightly enriched Zircaloy-clad uranium dioxide fluidized by light water under pressure. The reactor is modular in system; therefore, any size reactor can be constructed from the basic standard modul. The reactor physics calculations show that reactivity increases with porosity to a maximum value and thereafter decreases. This produces inherent safety and eliminates the need for control rods and burnable poisons. The heat transfer calculations show that the maximum power extracted from the reactor core is not limited to the material temperature limits but to the maximum mass flow of coolant, which corresponds to the desired operating porosity. Design simplicity and inherent safety make it an attractive small reactor design. (Author) [pt

  14. German research reactor back-end provisions

    International Nuclear Information System (INIS)

    Koester, Siegfried; Gruber, Gerhard

    2002-01-01

    Germany has several types of Research Reactors in operation. These reactors use fuel containing uranium of U.S. origin. Basically all the fuel which will be spent until May 2006 will be returned to the U.S. under existing contracts with the U.S. Department of Energy. The contracts are based on the U.S. FRR SNF (Foreign Research Reactor Spent Nuclear Fuel) Program which started in May 1996 and which will last for 10 years. In 1990, the German Federal Government started a program to long-term store (approx. 40 years) and finally dispose of spent fuel in Germany after the so-called U.S. fuel return window will be closed. In order to long-term store the fuel, a special container was designed which covers all different types of spent fuel from the Research Reactors. The container called 'CASTOR MTR 2' is basically licensed and is already in use for the spent fuel of Russian origin from the 'Research Reactor Rossendorf' in the eastern part of Germany. All that fuel is expected to be stored in the existing intermediate storage facility, the so-called BZA (Brennelemente Zwischenlager Ahaus). BZA already accomodates spent fuel from the former THTR-300 high temperature reactor. A final repository does not yet exist in Germany. Alternative provisions to close the back-end of the Research Reactor fuel cycle are reprocessing at COGEMA (France) or in Russian facilities, perspectively. Waste return in a form to be agreed will be mandatory, at least in France. (author)

  15. Basic Principles of Wastewater Treatment

    OpenAIRE

    Von Sperling, Marcos

    2007-01-01

    "Basic Principles of Wastewater Treatment is the second volume in the series Biological Wastewater Treatment, and focusses on the unit operations and processes associated with biological wastewater treatment. The major topics covered are: microbiology and ecology of wastewater treatment reaction kinetics and reactor hydraulics conversion of organic and inorganic matter sedimentation aeration The theory presented in this volume forms the basis upon which the other books...

  16. Computational geometry for reactor applications

    International Nuclear Information System (INIS)

    Brown, F.B.; Bischoff, F.G.

    1988-01-01

    Monte Carlo codes for simulating particle transport involve three basic computational sections: a geometry package for locating particles and computing distances to regional boundaries, a physics package for analyzing interactions between particles and problem materials, and an editing package for determining event statistics and overall results. This paper describes the computational geometry methods in RACER, a vectorized Monte Carlo code used for reactor physics analysis, so that comparisons may be made with techniques used in other codes. The principal applications for RACER are eigenvalue calculations and power distributions associated with reactor core physics analysis. Successive batches of neutrons are run until convergence and acceptable confidence intervals are obtained, with typical problems involving >10 6 histories. As such, the development of computational geometry methods has emphasized two basic needs: a flexible but compact geometric representation that permits accurate modeling of reactor core details and efficient geometric computation to permit very large numbers of histories to be run. The current geometric capabilities meet these needs effectively, supporting a variety of very large and demanding applications

  17. Application of phased arrays in basic and in-service inspection

    International Nuclear Information System (INIS)

    Gebhardt, W.; Schwarz, H.P.; Bonitz, F.; Woll, H.

    1985-01-01

    In the scope of the reactor safety research program of the Federal Ministry of Research and Technology a flexible microcomputer controlled phased array system was developed. Meanwhile, several industrial prototypes for simple and complicated applications are built up. The applicability of phased array systems in NDE for basic and inservice inspections of reactor pressure vessels is investigated. Methods for defect detection, reconstruction and classification are described

  18. Reactor engineering and engineered reactor safety in France

    International Nuclear Information System (INIS)

    1987-01-01

    The proceedings give the full text of the lectures held by acknowledged French experts at the KTG Seminar in Mainz on March 10, 1987, all dealing with the leading topic of the current status of reactor engineering and development in France. Although the basic engineering principles and construction lines as well as the safety philosophy are the same in France as in West Germany, there have been distinctive developments over many years in the two countries that by now are not well known even among experts in this field, and hence cannot be properly assessed. Non-availability of relevant surveys or other type of literature in the German language reviewing the French developments is another factor that hitherto was a handicap to mutual exchange of information. The seminar was intended to close this gap. The proceedings should be read by all those in West Germany who wish to be informed about the developments in reactor engineering and reactor safety in France. (orig./DG) [de

  19. Basic considerations for the mechanical design of heating reactors

    International Nuclear Information System (INIS)

    Rau, P.

    1997-01-01

    The paper discusses the principal aspects of the mechanical design of the reactor unit for a nuclear district heating plant. It is reasoned that the design must be specifically tailored to the characteristics of the applications, and that the experience gained with the design practice of big nuclear power stations must also be incorporated. Some examples of the design solutions for the SIEMENS NRH-200 are presented for illustration. (author). 7 refs, 10 figs

  20. Basic considerations for the mechanical design of heating reactors

    Energy Technology Data Exchange (ETDEWEB)

    Rau, P [Siemens AG, Unternehmensbereich KWU, Erlangen (Germany)

    1997-09-01

    The paper discusses the principal aspects of the mechanical design of the reactor unit for a nuclear district heating plant. It is reasoned that the design must be specifically tailored to the characteristics of the applications, and that the experience gained with the design practice of big nuclear power stations must also be incorporated. Some examples of the design solutions for the SIEMENS NRH-200 are presented for illustration. (author). 7 refs, 10 figs.

  1. Simulator for materials testing reactors

    International Nuclear Information System (INIS)

    Takemoto, Noriyuki; Sugaya, Naoto; Ohtsuka, Kaoru; Hanakawa, Hiroki; Onuma, Yuichi; Hosokawa, Jinsaku; Hori, Naohiko; Kaminaga, Masanori; Tamura, Kazuo; Hotta, Kohji; Ishitsuka, Tatsuo

    2013-06-01

    A real-time simulator for both reactor and irradiation facilities of a materials testing reactor, “Simulator of Materials Testing Reactors”, was developed for understanding reactor behavior and operational training in order to utilize it for nuclear human resource development and to promote partnership with developing countries which have a plan to introduce nuclear power plant. The simulator is designed based on the JMTR (Japan Materials Testing Reactor), and it simulates operation, irradiation tests and various kinds of anticipated operational transients and accident conditions caused by the reactor and irradiation facilities. The development of the simulator was sponsored by the Japanese government as one of the specialized projects of advanced research infrastructure in order to promote basic as well as applied researches. This report summarizes the simulation components, hardware specification and operation procedure of the simulator. (author)

  2. The integral fast reactor

    International Nuclear Information System (INIS)

    Till, C.E.

    1987-01-01

    On April 3rd, 1986, two demonstrations of the inherent capability of sodium-cooled fast reactors to survive unprotected loss of cooling accidents were carried out on the experimental sodium-cooled power reactor, EBR-II, on the Idaho site of Argonne National Laboratory. Transients potentially of the most serious kind, one an unprotected loss of flow, the other an unprotected loss of heat sink, both initiated from full power. In both cases the reactor quietly shut itself down, without damage of any kind. These tests were a part of the on-going development program at Argonne to develop an advanced reactor with significant new inherent safety characteristics. Called the integral fast reactor, or IFR, the basic thrust is to develop everything that is needed for a complete nuclear power system - reactor, closed fuel cycle, and waste processing - as a single optimized entity, and, for simplicity in concept, as an integral part of a single plant. The particular selection of reactor materials emphasizes inherent safety characteristics also makes possible a simplified close fuel cycle and waste process improvements. The paper describes the IFR concept, the inherent safety, tests, and status of IFR development today

  3. Heat extraction from HTGR reactor

    International Nuclear Information System (INIS)

    Balajka, J.; Princova, H.

    1986-01-01

    The analysis of an HTGR reactor energy balance showed that steam reforming of natural gas or methane is the most suitable process of utilizing the high-temperature heat. Basic mathematical relations are derived allowing to perform a general energy balance of the link between steam reforming and reactor heat output. The results of the calculation show that the efficiency of the entire reactor system increases with increasing proportion of heat output for steam reforming as against heat output for the steam generator. This proportion, however, is limited with the output helium temperature from steam reforming. It is thus always necessary to use part of the reactor heat output for the steam cycle involving electric power generation or low-potential heat generation. (Z.M.)

  4. Neutrons in basic and applied nuclear research - a review

    International Nuclear Information System (INIS)

    Bhattacharya, Sailajananda

    2013-01-01

    Energetic neutron sources, both white and mono-energetic, are widely used In basic nuclear physics as well as various multidisciplinary research. Precise measurement of various neutron induced reaction cross-sections are crucial for the design and development of new generation of reactors, like accelerator driven subcritical systems, nuclear incinerators, etc. A review of some recent trends in neutron induced basic and applied nuclear research will be presented in this talk. (author)

  5. Chapter 12. Nullification of nuclear reactors

    International Nuclear Information System (INIS)

    Toelgyessy, J.; Harangozo, M.

    2000-01-01

    This is a chapter of textbook of radioecology for university students. In this chapter authors deal with problems connected with nullification of nuclear reactors. There are tree basic methods of nullification of nuclear reactors: (1) conservation, (2) safe close (wall up, embed in concrete), (3) direct dismantlement and remotion and two combined ways: (1) combination of mothball with subsequent dismantlement and remotion and (2) combination of safe close with subsequent dismantlement and remotion. Activity levels as well as volumes of radioactive wastes connected with decommissioning of nuclear reactors are reviewed

  6. DOE fundamentals handbook: Nuclear physics and reactor theory

    International Nuclear Information System (INIS)

    1993-01-01

    The Nuclear Physics and Reactor Theory Handbook was developed to assist nuclear facility operating contractors in providing operators, maintenance personnel, and the technical staff with the necessary fundamentals training to ensure a basic understanding of nuclear physics and reactor theory. The handbook includes information on atomic and nuclear physics; neutron characteristics; reactor theory and nuclear parameters; and the theory of reactor operation. This information will provide personnel with a foundation for understanding the scientific principles that are associated with various DOE nuclear facility operations and maintenance

  7. User-friendly freehand ultrasound calibration using Lego bricks and automatic registration.

    Science.gov (United States)

    Xiao, Yiming; Yan, Charles Xiao Bo; Drouin, Simon; De Nigris, Dante; Kochanowska, Anna; Collins, D Louis

    2016-09-01

    As an inexpensive, noninvasive, and portable clinical imaging modality, ultrasound (US) has been widely employed in many interventional procedures for monitoring potential tissue deformation, surgical tool placement, and locating surgical targets. The application requires the spatial mapping between 2D US images and 3D coordinates of the patient. Although positions of the devices (i.e., ultrasound transducer) and the patient can be easily recorded by a motion tracking system, the spatial relationship between the US image and the tracker attached to the US transducer needs to be estimated through an US calibration procedure. Previously, various calibration techniques have been proposed, where a spatial transformation is computed to match the coordinates of corresponding features in a physical phantom and those seen in the US scans. However, most of these methods are difficult to use for novel users. We proposed an ultrasound calibration method by constructing a phantom from simple Lego bricks and applying an automated multi-slice 2D-3D registration scheme without volumetric reconstruction. The method was validated for its calibration accuracy and reproducibility. Our method yields a calibration accuracy of [Formula: see text] mm and a calibration reproducibility of 1.29 mm. We have proposed a robust, inexpensive, and easy-to-use ultrasound calibration method.

  8. Basic principles of accounting and control of nuclear materials in the BOR-60 experimental fast reactor

    International Nuclear Information System (INIS)

    Gryazev, V.M.; Gadzhiev, G.I.; Alekseev, I.N.

    1979-01-01

    Under a contract with the International Atomic Energy Agency, the V.I. Lenin Atomic Reactor Research Institute is currently carrying out a study of ways of organizing a nuclear materials accounting and control system for the BOR-60 fast reactor. Some results of this study are presented in the paper. The special physical and technological features of fast reactors create additional difficulties in safeguards systems and give rise to a number of new possibilities for the illicit removal of nuclear materials. These questions are discussed with reference to the BOR-60 reactor but the conclusions are probably applicable to all fast reactors. The proposed accounting and control system is based on non-destructive measurements of the amount of fissile materials in the operating fuel assemblies and screened bundles of the reactor, on the independent control of the principal facility parameters (a list of which is given) and on an automated information collection and evaluation system. Visual means of inspection can be very effective in fast reactor safeguards systems, especially for controlling storage, but they are not used with the BOR-60 reactor. (author)

  9. The law for the Power Reactor and Nuclear Fule Development Corporation

    International Nuclear Information System (INIS)

    1977-01-01

    The Corporation is designated to engage in the independent development of fast breeder and advanced thermal reactors, the production, reprocessing and holding of nuclear fuel materials, and the exploration, mining and ore dressing of nuclear source materials to promoting the development and utilization of atomic energy. These activities are based on the Atomic Energy Basic Law, and limited to the peaceful uses. The basic concepts of a fast breeder reactor and an advanced thermal reactor are defined. A chapter is dedicated to the number, constitution, duties, competence, appointment and dismissal of the officers. The score of business is specified, beginning from the development and research of the reactors and ending with the import, export, purchase and selling of nuclear fuel materials and nuclear source materials. (Okada, K.)

  10. Basic philosophy of the safety design of the Toshiba boiling water reactor

    International Nuclear Information System (INIS)

    Sato, T.

    1992-01-01

    This paper discusses the safety design of the Toshiba Boiling Water Reactor (TOSBWR) which was created ∼8 years ago. The design concept is intermediate between conventional boiling water reactors (BWRs) and the advanced BWR (ABWR). It utilizes internal pumps and fine motion control rod drive, but the emergency core cooling system (ECCS) configuration is different from both conventional BWRs and the ABWR. The plant output is 1350 MW (electric). The design is based on two important philosophies: the positive cost reduction philosophy and the constant risk philosophy

  11. Research Project 'RB research nuclear reactor' (operation and maintenance), Final report

    International Nuclear Information System (INIS)

    1985-01-01

    This final report covers operation and maintenance activities at the RB reactor during period from 1981-1985. First part covers the RB reactor operation, detailed description of reactor components, fuel, heavy water, reactor vessel, cooling system, equipment and instrumentation, auxiliary systems. It contains data concerned with dosimetry and radiation protection, reactor staff, and financial data. Second part deals maintenance, regular control and testing of reactor equipment and instrumentation. Third part is devoted to basic experimental options and utilization of the RB reactor including training

  12. Memory and accurate processing brain rehabilitation for the elderly: LEGO robot and iPad case study.

    Science.gov (United States)

    Lopez-Samaniego, Leire; Garcia-Zapirain, Begonya; Mendez-Zorrilla, Amaia

    2014-01-01

    This paper presents the results of research that applies cognitive therapies associated with memory and mathematical problem-solving in elderly people. The exercises are programmed in an iPad and can be performed both from the Tablet and in an interactive format with a LEGO robot. The system has been tested with 2 men and 7 women over the age of 65 who have slight physical and cognitive impairment. Evaluation with the SUS resulted in a mean of 48.45 with a standard deviation of 5.82. The score of overall satisfaction was 84.37 with a standard deviation of 18.6. Interaction with the touch screen caused some usability problems due to the elderly people's visual difficulties and clicking accuracy. Future versions will include visualization with more color contrast and less use of the keyboard.

  13. Calorimetric dosimetry of reactor radiation

    International Nuclear Information System (INIS)

    Radak, B.; Markovic, V.; Draganic, I.

    1961-01-01

    Calorimetric dosimetry of reactor radiation is relatively new reactor dosimetry method and the number of relevant papers is rather small. Some difficulties in applying standard methods (chemical dosemeters, ionization chambers) exist because of the complexity of radiation. In general application of calorimetric dosemeters for measuring absorbed doses is most precise. In addition to adequate choice of calorimetric bodies there is a possibility of determining the yields of each component of the radiation mixture in the total absorbed dose. This paper contains a short review of the basic calorimetry methods and some results of measurements at the RA reactor in Vinca performed by isothermal calorimeter [sr

  14. Basic study on high temperature gas cooled reactor technology for hydrogen production

    International Nuclear Information System (INIS)

    Chang, Jong Hwa; Lee, W. J.; Lee, H. M.

    2003-01-01

    The annual production of hydrogen in the world is about 500 billion m 3 . Currently hydrogen is consumed mainly in chemical industries. However hydrogen has huge potential to be consumed in transportation sector in coming decades. Assuming that 10% of fossil energy in transportation sector is substituted by hydrogen in 2020, the hydrogen in the sector will exceed current hydrogen consumption by more than 2.5 times. Currently hydrogen is mainly produced by steam reforming of natural gas. Steam reforming process is chiefest way to produce hydrogen for mass production. In the future, hydrogen has to be produced in a way to minimize CO2 emission during its production process as well as to satisfy economic competition. One of the alternatives to produce hydrogen under such criteria is using heat source of high-temperature gas-cooled reactor. The high-temperature gas-cooled reactor represents one type of the next generation of nuclear reactors for safe and reliable operation as well as for efficient and economic generation of energy

  15. Contributions of research Reactors in science and technology

    International Nuclear Information System (INIS)

    Butt, N.M.; Bashir, J.

    1992-12-01

    In the present paper, after defining a research reactor, its basic constituents, types of reactors, their distribution in the world, some typical examples of their uses are given. Particular emphasis in placed on the contribution of PARR-I (Pakistan Research Reactor-I), the 5 MW Swimming Pool Research reactor which first became critical at the Pakistan Institute of Nuclear Science and Technology (PINSTECH) in Dec. 1965 and attained its full power in June 1966. This is still the major research facility at PINSTECH for research and development. (author)

  16. Nuclear data and multigroup methods in fast reactor calculations

    International Nuclear Information System (INIS)

    Gur, Y.

    1975-03-01

    The work deals with fast reactor multigroup calculations, and the efficient treatment of basic nuclear data, which serves as raw material for the calculations. Its purpose is twofold: to build a computer code system that handles a large, detailed library of basic neutron cross section data, (such as ENDF/B-III) and yields a compact set of multigroup cross sections for reactor calculations; to use the code system for comparative analysis of different libraries, in order to discover basic uncertainties that still exist in the measurement of neutron cross sections, and to determine their influence upon uncertainties in nuclear calculations. A program named NANICK which was written in two versions is presented. The first handles the American basic data library, ENDF/B-III, while the second handles the German basic data library, KEDAK. The mathematical algorithm is identical in both versions, and only the file management is different. This program calculates infinitely diluted multigroup cross sections and scattering matrices. It is complemented by the program NASIF that calculates shielding factors from resonance parameters. Different versions of NASIF were written to handle ENDF/B-III or KEDAK. New methods for evaluating in reactor calculations the long term behavior of the neutron flux as well as its fine structure are described and an efficient calculation of the shielding factors from resonance parameters is offered. (B.G.)

  17. The timing of reactor dismantling

    International Nuclear Information System (INIS)

    Roberts, P.

    2000-01-01

    Work has been progressing across the world for the decommissioning of nuclear reactors. The initial work focused on the early, complete dismantling but this was associated with small size reactors and was done for experimental or demonstration purposes. The situation now is that an increasing number of full size power reactors are being shutdown and decision are being made as to the decommissioning strategy to be applied, e.g. with respect to the appropriate timing of reactor dismantling. There are two basic approaches to the timing of reactor dismantling, which are to either proceed with dismantling on an early time scale or to delay it for a period of years. There are a number of examples worldwide of both approaches being taken but one common feature of the approach taken by most countries is that decisions are made on a case by case basis, taking account of relevant factors, and as a result the strategy can vary from reactor to reactor and from country to country. Decisions on timing take account of the following main factors: safety, radioactive decay, financial factors, radioactive waste, reactor type, technology, repository availability, site re-use, regulatory standards, plant knowledge/records, other issues

  18. Criticality safety basics, a study guide

    Energy Technology Data Exchange (ETDEWEB)

    V. L. Putman

    1999-09-01

    This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates.

  19. Criticality safety basics, a study guide

    International Nuclear Information System (INIS)

    Putman, V.L.

    1999-01-01

    This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates

  20. Reactor lattice codes

    International Nuclear Information System (INIS)

    Kulikowska, T.

    1999-01-01

    The present lecture has a main goal to show how the transport lattice calculations are realised in a standard computer code. This is illustrated on the example of the WIMSD code, belonging to the most popular tools for reactor calculations. Most of the approaches discussed here can be easily modified to any other lattice code. The description of the code assumes the basic knowledge of reactor lattice, on the level given in the lecture on 'Reactor lattice transport calculations'. For more advanced explanation of the WIMSD code the reader is directed to the detailed descriptions of the code cited in References. The discussion of the methods and models included in the code is followed by the generally used homogenisation procedure and several numerical examples of discrepancies in calculated multiplication factors based on different sources of library data. (author)

  1. The IAEA programme on research reactor safety

    International Nuclear Information System (INIS)

    Abou Yehia, H.

    2007-01-01

    According to the research reactor database of IAEA (RRDB), 250 reactors are operating worldwide, 248 have been shut down and 170 have been decommissioned. Among the 248 reactors that do not run, some will resume their activities, others will be dismantled and the rest do not face a clear future. The analysis of reported incidents shows that the ageing process is a major cause of failures, more than two thirds of operating reactors are over 30 years old. It also appears that the lack of adequate regulations or safety standards for research reactors is an important issue concerning reactor safety particularly when reactors are facing re-starting or upgrading or modifications. The IAEA has launched a 4-axis program: 1) to set basic safety regulations and standards for research reactors, 2) to provide IAEA members with an efficient help for the application of these safety regulations to their reactors, 3) to foster international exchange of information on research reactor safety, and 4) to provide IAEA members with a help concerning safety issues linked to malicious acts or sabotage on research reactors

  2. The Atomic energy basic law

    International Nuclear Information System (INIS)

    1979-01-01

    The law aims to secure future energy resources, push forward progress of science and advancement of industry for welfare of the mankind and higher standard of national life by helping research, development and utilization of atomic power. Research, development and utilization of atomic power shall be limited to the peaceful purpose with emphasis laid on safety and carried on independently under democratic administration. Basic concepts and terms are defined, such as: atomic power; nuclear fuel material; nuclear raw material; reactor and radiation. The Atomic Energy Commission and the Atomic Energy Safety Commission shall be set up at the Prime Minister's Office deliberately to realize national policy of research, development and utilization of atomic power and manage democratic administration for atomic energy. The Atomic Energy Commission shall plan, consider and decide matters concerning research, development and utilization of atomic energy. The Atomic Energy Safety Commission shall plan, consider and decide issues particularly concerning safety securing among such matters. The Atomic Energy Research Institute shall be founded under the governmental supervision to perform research, experiment and other necessary affairs for development of atomic energy. The Power Reactor and Nuclear Fuel Development Corporation shall be established likewise to develop fast breeding reactor, advanced thermal reactor and nuclear fuel materials. Development of radioactive minerals, control of nuclear fuel materials and reactors and measures for patent and invention concerning atomic energy, etc. are stipulated respectively. (Okada, K.)

  3. Some recent contributions of basic nuclear science to nuclear waste transmutation

    International Nuclear Information System (INIS)

    Schapira, J.P.

    2001-01-01

    Nuclear waste transmutation aims at alleviating some long-term risks associated with actinides and with some long-lived fission products. Proposals of using accelerator driven system (ADS) to efficiently burn actinides in uranium free fuels have revitalized some basic researches in the field of nuclear and reactor physics. This is the case for high intensity accelerator in the ADS context and for the neutron source which relies to a large extent on basic nuclear physics related to spallation. There is also an experimental program called MUSE at Cadarache to study the sub-critical reactor physics with regard to its neutronics. A second area where basic research is involved is the measurement of new or more reliable neutron cross sections specific to transmutation and also to the thorium fuel cycle considered as a long-term option for ''clean'' energy production with reduced actinide production. This second area will possibly be covered by a new facility called n-TOF developed at CERN. (author)

  4. US Department of Energy 1992--1993 Reactor Sharing Program

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1994-04-01

    The University of Florida Training Reactor serves as a host institution to support various educational institutions which are located primarily within the state of Florida. All users and uses were carefully screened to assure the usage was for educational institutions eligible for participation in the Reactor Sharing Program. Three tables are included that provide basic information about the 1992--1993 program and utilization of the reactor facilities by user institutions

  5. The evaluation of research reactor TRIGA MARK II safety

    International Nuclear Information System (INIS)

    Jordan, R.; Kozuh, M.; Mavko, B.

    1994-01-01

    In the paper the Probabilistic Safety Analysis (PSA) of a research reactor is described. Five different initiating events were selected and analyzed with the use of event trees. Seven reactor systems were modeled with fault trees. Three groups of radiation releases were introduced - Success, Reactor-Hall, Environment - and their frequencies were estimated. The importance factors of initiating events, human errors and basic events were calculated regarding the consequence groups. (author)

  6. Fast reactor programme

    International Nuclear Information System (INIS)

    Plakman, J.C.

    1982-01-01

    This progress report summarizes the fast reactor research carried out by ECN during the period covering the year 1980. This research is mainly concerned with the cores of sodium-cooled breeders, in particular the SNR-300, and its related safety aspects. It comprises six items: A programme to determine relevant nuclear data of fission- and corrosion-products; A fuel performance programme comprising in-pile cladding failure experiments and a study of the consequences of loss-of-cooling and overpower; Basic research on fuel; Investigation of the changes in the mechanical properties of austenitic stainless steel DIN 1.4948 due to fast neutron doses, this material has been used in the manufacture of the reactor vessel and its internal components; Study of aerosols which could be formed at the time of a fast reactor accident and their progressive behaviour on leaking through cracks in the concrete containment; Studies on heat transfer in a sodium-cooled fast reactor core. As fast breeders operate at high power densities, an accurate knowledge of the heat transfer phenomena under single-phase and two-phase conditions is sought. (Auth.)

  7. Conceptual design of multipurpose compact research reactor

    International Nuclear Information System (INIS)

    Nagata, Hiroshi; Kusunoki, Tsuyoshi; Hori, Naohiko; Kaminaga, Masanori

    2012-01-01

    Conceptual design of the high-performance and low-cost multipurpose compact research reactor which will be expected to construct in the nuclear power plant introduction countries, started from 2010 in JAEA and nuclear-related companies in Japan. The aims of this conceptual design are to achieve highly safe reactor, economical design, high availability factor and advanced irradiation utilization. One of the basic reactor concept was determined as swimming pool type, thermal power of 10MW and water cooled and moderated reactor with plate type fuel element same as the JMTR. It is expected that the research reactors are used for human resource development, progress of the science and technology, expansion of industry use, lifetime extension of LWRs and so on. (author)

  8. Training of research reactor personnel

    International Nuclear Information System (INIS)

    Cherruau, F.

    1980-01-01

    Research reactor personnel operate the reactor and carry out the experiments. These two types of work entail different activities, and therefore different skills and competence, the number of relevant staff being basically a function of the size, complexity and versatility of the reactor. Training problems are often reactor-specific, but the present paper considers them from three different viewpoints: the training or retraining of new staff or of personnel already employed at an existing facility, and training of personnel responsible for the start-up and operation of a new reactor, according to whether local infrastructure and experience already exist or whether they have to be built up from scratch. On-the-spot experience seems to be an essential basis for sound training, but requires teaching abilities and aids often difficult to bring together, and the availability of instructors that does not always fit in smoothly with current operational and experimental tasks. (author)

  9. Modeling the PUSPATI TRIGA Reactor using MCNP code

    International Nuclear Information System (INIS)

    Mohamad Hairie Rabir; Mark Dennis Usang; Naim Syauqi Hamzah; Julia Abdul Karim; Mohd Amin Sharifuldin Salleh

    2012-01-01

    The 1 MW TRIGA MARK II research reactor at Malaysian Nuclear Agency achieved initial criticality on June 28, 1982. The reactor is designed to effectively implement the various fields of basic nuclear research, manpower training, and production of radioisotopes. This paper describes the reactor parameters calculation for the PUSPATI TRIGA REACTOR (RTP); focusing on the application of the developed reactor 3D model for criticality calculation, analysis of power and neutron flux distribution and depletion study of TRIGA fuel. The 3D continuous energy Monte Carlo code MCNP was used to develop a versatile and accurate full model of the TRIGA reactor. The model represents in detailed all important components of the core and shielding with literally no physical approximation. (author)

  10. Qualitative methods in nuclear reactor dynamics. Issue 23

    International Nuclear Information System (INIS)

    Goryachenko, V.D.

    1983-01-01

    Applicability of qualitative methods of the theory of nonlinear oscillations including the bifurcation theory to the problems of nuclear reactor nonlinear dynamics is investigated. Basic statements of the dynamic system qualitative theory on a phase plane and the bifurcation theory of multidimensional dynamic systems are briefly outlined. The model of reactor dynamics with two reactivity temperature coefficients neglecting delayed neutrons, the model of slow process dynamics in a reactor with two reactivity temperature coefficients, the simplified model of reactor dynamics as an object with delay and the model of a reactor with linear feedback are considered. A conclusion is drawn that the usage of the above models allows one to reveal qualitative peculiarities of reactor dynamics creating conditions for more purposeful utilization of more complicated models

  11. Materials science research for sodium cooled fast reactors

    Indian Academy of Sciences (India)

    The paper gives an insight into basic as well as applied research being carried out at the Indira Gandhi Centre for Atomic Research for the development of advanced materials for sodium cooled fast reactors towards extending the life of reactors to nearly 100 years and the burnup of fuel to 2,00,000 MWd/t with an objective ...

  12. Use of Covariances in a Consistent Data Assimilation for Improvement of Basic Nuclear Parameters in Nuclear Reactor Applications: From Meters to Femtometers

    International Nuclear Information System (INIS)

    Herman, Mike; Hoblit, Sam; Gustavo, Nobre; Palumbo, Annalia; Pigni, M.T.; Palmiotti, G.; Hiruta, H.; Salvatores

    2013-01-01

    neutron energy spectrum that are adopted in the assimilation (adjustment). In fact, after such an adjustment is performed, neutronic designers are then tied to this energy group structure and neutron energy spectrum when carrying out further calculations. In reality, this can be quite a limiting factor in view of the complex spectral issues that are involved in most reactor physics. This work combines novel, but proven, methodologies for overcoming these limitations. In fact, this is the first attempt to build up a link between the wealth of precise integral experiments and a basic theory of nuclear reactions. Essential ingredients of such a procedure, denominated here as assimilation, are covariances for model parameters and sensitivity matrices. The latter provide direct link between reaction theory and integral experiments. The result is a consistent data assimilation performed directly on the basic nuclear physics parameters that are being used in a variety of nuclear reaction mechanisms. The resulting improvement in their performance will consequently reduce related uncertainties when employed in reactor calculations. By using integral reactor physics experiments (meter scale), information is propagated back to the nuclear physics level (femtometers) covering a range of more than 13 orders of magnitude. The assimilation procedure should result in more accurate and more reliable evaluated data files of universal validity rather than tailored to a particular application. In fact, after data assimilation is carried out, the basic nuclear data file can be processed by a dedicated code into any energy group structure that the reactor physicist deems to be useful. On the other hand, integral experiments used in the assimilation should provide additional, possibly quite strict, constraints on the parameters entering nuclear reaction modeling, as well as the reaction models themselves. This report describes three years of combined research by Brookhaven National Lab (BNL

  13. Evaluation of reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-04-15

    Although the operation of nuclear reactors has a remarkably good record of safety, the prevention of possible reactor accidents is one of the major factors that atomic planners have to contend with. At the same time, excessive caution may breed an attitude that hampers progress, either by resisting new development or by demanding unnecessarily elaborate and expensive precautions out of proportion to the actual hazards involved. The best course obviously is to determine the possible dangers and adopt adequate measures for their prevention, providing of course, for a reasonable margin of error in judging the hazards and the effectiveness of the measures. The greater the expert understanding and thoroughness with which this is done, the narrower need the margin be. This is the basic idea behind the evaluation of reactor safety

  14. Physicochemical, morphological, and rheological characterization of Xanthosoma robustum Lego-like starch.

    Science.gov (United States)

    Londoño-Restrepo, Sandra M; Rincón-Londoño, Natalia; Contreras-Padilla, Margarita; Acosta-Osorio, Andrés A; Bello-Pérez, Luis A; Lucas-Aguirre, Juan C; Quintero, Víctor D; Pineda-Gómez, Posidia; del Real-López, Alicia; Rodríguez-García, Mario E

    2014-04-01

    This work presents the physicochemical and pasting characterization of isolated mafafa starch and mafafa flour (Xanthosoma robustum). According to SEM images of mafafa starches in the tuber, these starches form Lego-like shaped structures with diameters between 8 and 35 μm conformed by several starch granules of wedge shape that range from 2 to 7 μm. The isolated mafafa starch is characterized by its low contents of protein, fat, and ash. The starch content in isolated starch was found to be 88.58% while the amylose content obtained was 35.43%. X-ray diffraction studies confirm that isolated starch is composed mainly by amylopectin. These results were confirmed by differential scanning calorimetry and thermo gravimetric analysis. This is the first report of the molecular parameters for mafafa starch: molar mass that ranged between 2×10(8) and 4×10(8) g/mol, size (Rg) value between 279 and 295 nm, and molecular density value between 9.2 and 9.7 g/(mol nm(3)). This study indicates that mafafa starch shows long chains of amylopectin this fact contributes to higher viscosity development and higher gel stability. The obtained gel phase is transparent in the UV-vis region. The viscosity, gel stability and optical properties suggest that there is potential for mafafa starch applications in the food industry. Copyright © 2014 Elsevier B.V. All rights reserved.

  15. Plutonium bearing oxide fuels for recycling in thermal reactors and fast breeder reactors

    International Nuclear Information System (INIS)

    Cunningham, G.W.

    1977-01-01

    Programs carried out in the past two decades have established the technical feasibility of using plutonium as a fuel material in both water-cooled power reactors and sodium-cooled fast breeder reactors. The problem facing the technical community is basically one of demonstrating plutonium fuel recycle under strict conditions of public safety, accountability, personnel exposure, waste management, transportation and diversion or theft which are still evolving. In this paper only technical and economic aspects of high volume production and the demonstration program required are discussed. This paper discusses the role of mixed oxide fuels in light water reactors and the objectives of the LMFBR required for continual growth of nuclear power during the next century. The results of studies showing the impact of using plutonium on uranium requirements, power costs, and the market share of nuclear power are presented. The influence of doubling time and the introduction date of LMFBRs on the benefits to be derived by its commercial use are discussed. Advanced fuel development programs scoped to meet future commerical LMFBR fuel requirements are described. Programs designed to provide the basic technology required for using plutonium fuels in a manner which will satisfy all requirements for public acceptance are described. Included are the high exposure plutonium fabrication development program centered around the High Performance Fuels Laboratory being built at the Hanford Engineering Development Laboratory and the program to confirm the technology required for the production of mixed oxide fuels for light water reactors which is being coordinated by Savannah River Laboratories

  16. Economics of the modular reactor as new-generation nuclear power

    International Nuclear Information System (INIS)

    Hattori, Sadao

    1987-01-01

    This paper lists thirteen advantages which could be effectuated by modular reactors. These advantages are derived basically from the general attributes of modularization, i.e., continuity of production, smallness of size/capacity, ease of standardization, and built-in passive safety. This paper also suggests a general direction in which the development of modular reactors evolve, and a possible nuclear application where modular reactors be effectively utilized. (author)

  17. RA research reactor in 'Vinca' Institute-approach to the decommissioning

    International Nuclear Information System (INIS)

    Ljubenov, V.Lj.; Pesic, M.P.; Sotic, O.

    2002-01-01

    In this paper short overview of decommissioning process of research reactors according to IAEA standards and world practice is given. Basic technical characteristics and details of operational history of the RA research reactor in Vinca Institute of Nuclear Sciences are present. The main nuclear and radiation safety problems related to the RA reactor facility are defined and the outlines of the future decommissioning project are proposed. (author)

  18. The safety basis of the integral fast reactor program

    International Nuclear Information System (INIS)

    Pedersen, D.R.; Seidel, B.R.

    1990-01-01

    The Integral Fast Reactor (IFR) and metallic fuel have emerged as the US Department of Energy reference reactor concept and fuel system for the development of an advanced liquid-metal reactor. This article addresses the basic elements of the IFR reactor concept and focuses on the safety advances achieved by the IFR Program in the areas of (1) fuel performance, (2) superior local faults tolerance, (3) transient fuel performance, (4) fuel-failure mechanisms, (5) performance in anticipated transients without scram, (6) core-melt mitigation, and (7) actinide recycle

  19. Reactor physics innovations of the advanced CANDU reactor core: adaptable and efficient

    International Nuclear Information System (INIS)

    Chan, P.S.W.; Hopwood, J.M.; Bonechi, M.

    2003-01-01

    The Advanced CANDU Reactor (ACR) is designed to have a benign, operator-friendly core physics characteristic, including a slightly negative coolant-void reactivity and a moderately negative power coefficient. The discharge fuel burnup is about three times that of natural uranium fuel in current CANDU reactors. Key features of the reactor physics innovations in the ACR core include the use of H 2 O coolant, slightly enriched uranium (SEU) fuel, and D 2 O moderator in a reduced lattice pitch. These innovations result in substantial improvements in economics, as well as significant enhancements in reactor performance and waste reduction over the current reactor design. The ACR can be readily adapted to different power outputs by increasing or decreasing the number of fuel channels, while maintaining identical fuel and fuel-channel characteristics. The flexibility provided by on-power refuelling and simple fuel bundle design enables the ACR to easily adapt to the use of plutonium and thorium fuel cycles. No major modifications to the basic ACR design are required because the benign neutronic characteristics of the SEU fuel cycle are also inherent in these advanced fuel cycles. (author)

  20. Advanced reactor design study. Assessing nonbackfittable concepts for improving uranium utilization in light water reactors

    International Nuclear Information System (INIS)

    Fleischman, R.M.; Goldsmith, S.; Newman, D.F.; Trapp, T.J.; Spinrad, B.I.

    1981-09-01

    The objective of the Advanced Reactor Design Study (ARDS) is to identify and evaluate nonbackfittable concepts for improving uranium utilization in light water reactors (LWRs). The results of this study provide a basis for selecting and demonstrating specific nonbackfittable concepts that have good potential for implementation. Lead responsibility for managing the study was assigned to the Pacific Northwest Laboratory (PNL). Nonbackfittable concepts for improving uranium utilization in LWRs on the once-through fuel cycle were selected separately for PWRs and BWRs due to basic differences in the way specific concepts apply to those plants. Nonbackfittable concepts are those that are too costly to incorporate in existing plants, and thus, could only be economically incorporated in new reactor designs or plants in very early stages of construction. Essential results of the Advanced Reactor Design Study are summarized

  1. Amendment of Atomic Energy Basic Law and the development of Atomic Energy Administration

    International Nuclear Information System (INIS)

    Ochi, Kenji

    1978-01-01

    This article explains the key points of the major development of Atomic Energy Administration recently made by amendments of Atomic Energy Basic Law and other two relating laws. These amendments passed through the Diet and were enacted on 7th, June, 1978. The aim of them is focussed on reinforcement and rearrangement of safety controls on nuclear reactors. Previously, although the approval of the installation plan with basic designs of a nuclear reactor has been done by Prime Minister, further approvals of detailed designs and process of construction works, as well as inspections before and after operation have been conducted by each responsible minister, respectively. That is, those controls for power reactors have been within jurisdiction of minister of Trade and Industry, and for nuclear ships' reactors minister of Transportation has been responsible. Under the new system, above mentioned ministers continue to exercise almost same controls over reactors within their jurisdiction respectively, however the new laws have established so-called ''double check'' principle in that: when each responsible minister approves the installation, detailed designs and further stages of construction and operation of the reactor, he should hear and pay a great regard for opinions of Atomic Energy Commission and Atomic Energy Safety Commission. The latter is newly established organization which has similar status and authority to the former. (J.P.N.)

  2. Reactor assessments of advanced bumpy torus configurations

    International Nuclear Information System (INIS)

    Uckan, N.A.; Owen, L.W.; Spong, D.A.; Miller, R.L.; Ard, W.B.; Pipkins, J.F.; Schmitt, R.J.

    1984-02-01

    Recently, several innovative approaches were introduced for enhancing the performance of the basic ELMO Bumpy Torus (EBT) concept and for improving its reactor potential. These include planar racetrack and square geometries, Andreoletti coil systems, and bumpy torus-stellarator hybrids (which include twisted racetrack and helical axis stellarator - snakey torus). Preliminary evaluations of reactor implications of each approach have been carried out based on magnetics (vacuum) calculations, transport and scaling relationships, and stability properties deduced from provisional configurations that implement the approach but are not necessarily optimized. Further optimization is needed in all cases to evaluate the full potential of each approach. Results of these studies indicate favorable reactor projections with a significant reduction in reactor physical size as compared to conventional EBT reactor designs carried out in the past

  3. Nuclear reactor simulator

    International Nuclear Information System (INIS)

    Baptista, Vinicius Damas

    1996-01-01

    The Nuclear Reactor Simulator was projected to help the basic training in the formation of the Nuclear Power Plants operators. It gives the trainee the opportunity to see the nuclear reactor dynamics. It's specially indicated to be used as the support tool to NPPT (Nuclear Power Preparatory Training) from NUS Corporation. The software was developed to Intel platform (80 x 86, Pentium and compatible ones) working under the Windows operational system from Microsoft. The program language used in development was Object Pascal and the compiler used was Delphi from Borland. During the development, computer algorithms were used, based in numeric methods, to the resolution of the differential equations involved in the process. (author)

  4. The atomic energy basic law

    International Nuclear Information System (INIS)

    1977-01-01

    The law establishes clearly the principles that Japan makes R and D, and utilizations of atomic energy only for the peaceful purposes. All the other laws and regulations concerning atomic energy are based on the law. The first chapter lays down the above mentioned objective of the law, and gives definitions of basic concepts and terms, such as atomic energy, nuclear fuel material, nuclear source material, nuclear reactor and radiation. The second chapter provides for the establishment of Atomic Energy Commission which conducts plannings and investigations, and also makes decisions concerning R and D, and utilizations of atomic energy. The third chapter stipulates for establishment of two government organizations which perform R and D of atomic energy developments including experiments and demonstrations of new types of reactors, namely, Atomic Energy Research Institute and Power Reactor and Nuclear Fuel Development Corporation. Chapters from 4th through 8th provide for the regulations on development and acquisition of the minerals containing nuclear source materials, controls on nuclear fuel materials and nuclear reactors, administrations of the patents and inventions concerning atomic energy, and also prevention of injuries due to radiations. The last 9th chapter requires the government and its appointee to compensate the interested third party for damages in relation to the exploitation of nuclear source materials. (Matsushima, A.)

  5. On the utilization of neutron beams of research reactors in research and applications

    International Nuclear Information System (INIS)

    FAYEK, M.K.

    2000-01-01

    Nuclear research reactors are the most widely available neutron sources, and they are capable of producing very high fluxes of neutrons having a considerable range of energies, from a few MeV to 10 MeV. Therefore, these neutrons can be used in many fields of basic research and for applications in physics, chemistry, medicine, biology, etc. Experiments with research reactors over the last 50 years have laid the foundations of today's nuclear technology. In addition, research reactors continue to be utilized as facilities for testing materials and in training manpower for nuclear programs, because basic training on a research reactor provides an essential understanding of the nuclear process, and personnel become accustomed to work under the special conditions resulting from irradiation and contamination risks

  6. Materials for fusion reactors

    International Nuclear Information System (INIS)

    Ehrlich, K.; Kaletta, D.

    1978-03-01

    The following report describes five papers which were given during the IMF seminar series summer 1977. The purpose of this series was to discuss especially the irradiation behaviour of materials intended for the first wall of future fusion reactors. The first paper deals with the basic understanding of plasma physics relating to the fusion reactor and presents the current state of art of fusion technology. The next two talks discuss the metals intended for the first wall and structural components of a fusion reactor. Since 14 MeV neutrons play an important part in the process of irradiation damage their role is discussed in detail. The question which machines are presently available to simulate irradiation damage under conditions similar to the ones found in a fusion reactor are investigated in the fourth talk which also presents the limitations of the different methods of simulation. In this context also discussed is the importance future intensive neutron sources and materials test reactors will have for this problem area. The closing paper has as a theme the review of the present status of research of metallic and non-metallic materials in view of the quite different requirements for different fusion systems; a closing topic is the world supply on rare materials required for fusion reactors. (orig) [de

  7. Thermionic reactor power conditioner design for nuclear electric propulsion.

    Science.gov (United States)

    Jacobsen, A. S.; Tasca, D. M.

    1971-01-01

    Consideration of the effects of various thermionic reactor parameters and requirements upon spacecraft power conditioning design. A basic spacecraft is defined using nuclear electric propulsion, requiring approximately 120 kWe. The interrelationships of reactor operating characteristics and power conditioning requirements are discussed and evaluated, and the effects on power conditioner design and performance are presented.

  8. Reactors physics. Bases of nuclear physics

    International Nuclear Information System (INIS)

    Diop, Ch.M.

    2006-01-01

    The aim of nuclear reactor physics is to quantify the relevant macroscopic data for the characterization of the neutronic state of a reactor core and to evaluate the effects of radiations (neutrons and gamma radiations) on organic matter and on inorganic materials. This first article presents the bases of nuclear physics in the context of nuclear reactors: 1 - reactor physics and nuclear physics; 2 - atomic nucleus - basic definitions: nucleus constituents, dimensions and mass of the atomic nucleus, mass defect, binding energy and stability of the nucleus, strong interaction, nuclear momentums of nucleons and nucleus; 3 - nucleus stability and radioactivity: equation of evolution with time - radioactive decay law; alpha decay, stability limit of spontaneous fission, beta decay, electronic capture, gamma emission, internal conversion, radioactivity, two-body problem and notion of radioactive equilibrium. (J.S.)

  9. Evaluation of nuclear reactor based activation analysis techniques

    International Nuclear Information System (INIS)

    Obrusnik, I.; Kucera, J.

    1977-09-01

    A survey is presented of the basic types of activation analysis applied in environmental control. Reactor neutron activation analysis is described (including the reactor as a neutron source, sample activation in the reactor, methodology of neutron activation analysis, sample transport into the reactor and sample packaging after irradiation, instrumental activation analysis with radiochemical separation, data measurement and evaluation, sampling and sample preparation). Sources of environmental contamination with trace elements, sampling and sample analysis by neutron activation are described. The analysis is described of soils, waters and biological materials. Methods are shown of evaluating neutron activation analysis results and of their interpretation for purposes of environmental control. (J.B.)

  10. Reactor control device

    International Nuclear Information System (INIS)

    Kameda, Akiyuki.

    1979-01-01

    Purpose: To enable three types of controls, that is, level control, scram control and excess reactivity control required for a reactor by a same mechanism by feeding neutron absorber liquid and pressure control gas to several blind pipes provided in the reactor core. Constitution: A plurality of blind pipes are disposed spaced apart in a reactor core and connected by way of injection pipes to a neutron absorber liquid tank. A pressure regulator is connected to the blind pipes, to which pressure control gas is supplied. The neutron absorber liquid used herein consists of sodium, potassium or their alloy, or mercury as a basic substance incorporated with one or more selected from boron, tantalum, rhenium, europium or their compounds. The level control, scram control and excess reactivity control can be attained by moderating the pressure changes in the pressure control gas or by regulating the fluctuation in the liquid level. (Horiughi, T.)

  11. Design of high temperature Engineering Test Reactor (HTTR)

    International Nuclear Information System (INIS)

    Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio

    1994-09-01

    Construction of High Temperature Engineering Test Reactor (HTTR) is now underway to establish and upgrade basic technologies for HTGRs and to conduct innovative basic research at high temperatures. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW in thermal output and outlet coolant temperature of 850degC for rated operation and 950degC for high temperature test operation. It is planned to conduct various irradiation tests for fuels and materials, safety demonstration tests and nuclear heat application tests. JAERI received construction permit of HTTR reactor facility in February 1990 after 22 months of safety review. This report summarizes evaluation of nuclear and thermal-hydraulic characteristics, design outline of major systems and components, and also includes relating R and D result and safety evaluation. Criteria for judgment, selection of postulated events, major analytical conditions for anticipated operational occurrences and accidents, computer codes used in safety analysis and evaluation of each event are presented in the safety evaluation. (author)

  12. The progress of basic research for ADS in China

    International Nuclear Information System (INIS)

    Xia Haihong; Zhao Zhixiang; Ding Dazhao

    2002-01-01

    The conceptual study of Accelerator Driven System (ADS), which is an entirely new approach for the exploitation of next generation nuclear energy, had lasted for about five years and ended in 1999 in China. From then a five years program of basic research for ADS has been launched. According to present technical and budget status in China, a moderate style multi-purpose verification system is under consideration, which consists of a low energy accelerator (150MeV/3mA proton linac) and a swimming pool light water sub-critical reactor. CIAE (China Institute of Atomic Energy), IHEP (Institute of High Energy Physics), PKU-IHIP (Institute of Heavy Ion Physics in Peking University) and other institutions are jointly carrying on the basic research of ADS. The main results on ADS system optimization, ADS related reactor physics study, nuclear physics study, accelerator physics and technology study, material compatibility study, material radiation effects study has been reported. (author)

  13. Unification of reactor elastomeric sealing based on material

    International Nuclear Information System (INIS)

    Sinha, N.K.; Raj, Baldev

    2012-01-01

    The unification of elastomeric sealing applications of Indian nuclear reactors based on a few qualified fluoroelastomer/perfluoroelastomer compounds and standardized approaches for finite element analysis (FEA) based design, manufacturing process and antifriction coatings is discussed. It is shown that the advance polymer architecture based Viton ® formulation developed for inflatable seals of 500 MWe Prototype Fast Breeder Reactor (PFBR) and its four basic variations can encompass other sealing applications of PFBR with minimum additional efforts on development and validation. Changing the blend ratio of Viton ® GBL 200S and 600S in inflatable seal formulation could extend its use to Pressurized Heavy Water Reactors (PHWRs). The higher operating temperature of Advanced Heavy Water Reactor (AHWR) seals expands the choice to perfluoroelastomers. FEA based on plane-strain/axisymmetric modeling (with Mooney–Rivlin as the basic constitutive model), seal manufacture by cold feed extrusion and injection molding as well as plasma Teflon-like coating belonging to two variations obtained from the development of inflatable seals provide the necessary standardization for unification. The gains in simplification of design, development and operation of seals along with the enhancements of safety and reliability are expected to be substantial.

  14. Designing using Lego and Uno-Stacko: A Playful Architecture for an Integrated Kindergarten and Elementary School

    Science.gov (United States)

    Muthmainnah, K.; Aryanti, T.; Ardiansyah, A.

    2017-03-01

    The integrated kindergarten and elementary school is a public educational facility used for early age and elementary education. Designated for children at 4-12 years of age, the design should meet the standards and requirements, while considering children’s needs in their development phase. This paper discusses the design of an integrated kindergarten and elementary school using the playful theme. Design was explored using LEGO and UNO-STACKO to create spaces that accommodate material exploration for children. The design takes the play concept as a medium of child’s learning in order to improve their ability and awareness of the surrounding environment. The design translates the playful theme into imaginary dimension, constructive-deconstructive shapes, and glide circulations concept. The spatial pattern is applied by considering children’s behavior in the designated ages to trigger their creativity improvement. The design is expected to serve as a model of an integrated kindergarten and elementary school architecture.

  15. Reactor cold neutron source facility, the first in Japan

    International Nuclear Information System (INIS)

    Utsuro, Masahiko; Maeda, Yutaka; Kawai, Takeshi; Tashiro, Tameyoshi; Sakakibara, Shoji; Katada, Minoru.

    1986-01-01

    In the Research Reactor Institute, Kyoto University, the first cold neutron source facility for the reactor in Japan was installed, and various tests are carried out outside the reactor. Nippon Sanso K.K. had manufactured it. After the prescribed tests outside the reactor, this facility will be installed soon in the reactor, and its outline is described on this occasion. Cold neutrons are those having very small energy by being cooled to about-250 deg C. Since the wavelength of the material waves of cold neutrons is long, and their energy is small, they are very advantageous as an experimental means for clarifying the structure of living body molecules and polymers, the atom configuration in alloys, and atomic and molecular movements by neutron scattering and neutron diffraction. The basic principle of the cold neutron source facility is to irradiate thermal neutrons on a cold moderator kept around 20 K, and to moderate and cool the neutrons by nuclear scattering to convert to cold neutrons. The preparatory research on cold neutrons and hydrogen liquefaction, the basic design to put the cold neutron source facility in the graphite moderator facility, the safety countermeasures, the manufacture and quality control, the operation outside the reactor and the performance are reported. The cold neutron source facility comprises a cold moderator tank and other main parts, a deuterium gas tank, a helium refrigerator and instrumentation. (Kako, I.)

  16. The status of fast reactor technology development in China

    International Nuclear Information System (INIS)

    Xu Mi

    1998-01-01

    The paper describes recent status and trends on Chinese national economy, electrical power capacity and nuclear power development. The preliminary design of the CEFR has been approved by the State Science and Technology Commission. Now it is in the detail design stage. It is planned that the first pot of concrete will be in April of 1999, in the end of 2000 the reactor building construction will be finished and the first criticality of the reactor will be envisaged in July 2003. The brief of preliminary design, analysis results of some beyond design basic accidents and design basic accidents, CEFR research works, and international cooperation are presented in the paper. (author)

  17. Introducir la fracción en el ámbito escolar a través de un material manipulativo como es el Lego

    OpenAIRE

    Sánchez Díaz, Michael

    2017-01-01

    Treball Final de Grau en Mestre o Mestra d'Educació Primària. Codi: MP1040. Curs acadèmic: 2016/2017 Con este trabajo de investigación se quiere proponer una nueva metodología a la hora de enseñar las fracciones en la asignatura de matemáticas en el aula de primaria. El principal objetivo a seguir es que, a través de un material manipulativo como es el lego, los niños sean capaces de aprender las nociones básicas sobre las fracciones haciendo y no escuchando. Para ello, se ha ido recogiend...

  18. How power is generated in a nuclear reactor

    International Nuclear Information System (INIS)

    Swaminathan, V.

    1978-01-01

    Power generation by nuclear fission as a result of chain reaction caused by neutrons interacting with fissile material such as 235 U, 233 U and 239 Pu is explained. Electric power production by reactor is schematically illustrated. Materials used in thermal reactor and breeder reactor are compared. Fuel reprocessing and disposal of radioactive waste coming from reprocessing plant is briefly described. Nuclear activities in India are reviewed. Four heavy water plants and two power reactors are under construction and will be operative in the near future. Two power reactors are already in operation. Nuclear Fuel Complex at Hyderabad supplies fuel element to the reactors. Fuel reprocessing and waste management facility has been set up at Tarapur. Bhabha Atomic Research Centre at Bombay and Reactor Research Centre at Kalpakkam near Madras are engaged in applied and basic research in nuclear science and engineering. (B.G.W.)

  19. Paracantor: A two group, two region reactor code

    Energy Technology Data Exchange (ETDEWEB)

    Stone, Stuart

    1956-07-01

    Paracantor I a two energy group, two region, time independent reactor code, which obtains a closed solution for a critical reactor assembly. The code deals with cylindrical reactors of finite length and with a radial reflector of finite thickness. It is programmed for the 1.B.M: Magnetic Drum Data-Processing Machine, Type 650. The limited memory space available does not permit a flux solution to be included in the basic Paracantor code. A supplementary code, Paracantor 11, has been programmed which computes fluxes, .including adjoint fluxes, from the .output of Paracamtor I.

  20. Gaseous fuel reactors for power systems

    International Nuclear Information System (INIS)

    Helmick, H.H.; Schwenk, F.C.

    1978-01-01

    The Los Alamos Scientific Laboratory is participating in a NASA-sponsored program to demonstrate the feasibility of a gaseous uranium fueled reactor. The work is aimed at acquiring experimental and theoretical information for the design of a prototype plasma core reactor which will test heat removal by optical radiation. The basic goal of this work is for space applications, however, other NASA-sponsored work suggests several attractive applications to help meet earth-bound energy needs. Such potential benefits are small critical mass, on-site fuel processing, high fuel burnup, low fission fragment inventory in reactor core, high temperature for process heat, optical radiation for photochemistry and space power transmission, and high temperature for advanced propulsion systems. Low power reactor experiments using uranium hexafluoride gas as fuel demonstrated performance in accordance with reactor physics predictions. The final phase of experimental activity now in progress is the fabrication and testing of a buffer gas vortex confinement system

  1. Application technique of data free way on the basic reactor materials

    International Nuclear Information System (INIS)

    Fujita, Mitsutane; Noda, Tetsuji; Kitajima, Masahiro; Nagakawa, Josei; Yamamoto, Norikazu

    1998-01-01

    National Research Institute for Metals (NRIM), Japan Atomic Energy Research Institute (JAERI), Power Reactor and Nuclear Fuel Development Corporation (PNC), and Japan Science and Technology Promotion Corporation (JST) construct each own data base on each advantageous field to develop mutually and cooperatively a system called data free way and applicable mutually for four each organization by connecting them with a network to construct a huge dispersion type data base system. In 1998 fiscal year, it was conducted by these four organization cooperatively to fill up the system applicable for function showing data content and data retrieving function by using internet. In NRIM, as a result to input the data on mechanical properties of irradiated SUS 316 stainless steel, a new information could be obtained. In order to fill up the data base for reactor materials, a use interface for the data base was developed. In addition, a system capable to use a program to estimate activation due to nuclear reaction when the materials was exposed by neutron radiation through internet was begun to develop. (G.K.)

  2. History, Development and Future of TRIGA Research Reactors

    International Nuclear Information System (INIS)

    2016-01-01

    Due to its particular fuel design and resulting enhanced inherent safety features, TRIGA reactors (Training, Research, Isotopes, General Atomics) constitute a ‘class of their own’ among the large variety of research reactors built world-wide. This publication summarizes in a single document the information on the past and present of TRIGA research reactors and presents an outlook in view of potential issues to be solved by TRIGA operating organizations in the near future. It covers the historical development and basic TRIGA characteristics, followed by utilization, fuel conversion and ageing management of TRIGA research reactors. It continues with issues and challenges, introduction to the global TRIGA research reactor network and concludes with future perspectives. The publication is complemented with a CD-ROM to illustrate the historical developments of TRIGA research reactors through individual facility examples and experiences

  3. Basic studies for the solution of the criticality equation: two groups of energy and one dimension

    International Nuclear Information System (INIS)

    Britto Aghina, L.O. de.

    1994-12-01

    This work collects six basic studies for the numerical solution of the criticality equation for thermal reactors. Use is made of the diffusion theory for two groups of energy and one dimension, applicable to bare reactors, bare equivalent, infinite bare equivalent and reflected reactors. These studies were written in Mathcad 4.0/WIN programming, a practical form for use by the researchers and operators working with the Argonaut Reactor at the Instituto de Engenharia Nuclear (IEN). (author). 11 refs, 20 figs, 8 tabs

  4. The present status and the prospect of China research reactors

    International Nuclear Information System (INIS)

    Yongmao, Z.; Yizheng, C.

    1990-01-01

    A total of 100 reactor operation years' experience of research reactors has now been obtained in China. The type and principal parameters of China research reactors and their operating status are briefly introduced in this paper. Chinese research reactors have been playing an important role in nuclear power and nuclear weapon development, industrial and agricultural production, medicine, basic and applied science research and environmental protection, etc. The utilization scale, benefits and achievements will be given. There is a good safety record in the operation of these reactors. A general safety review is discussed. The important incidents and accidents happening during a hundred reactor operating years are described and analyzed. China has the capability of developing any type of research reactor. The prospective projects are briefly introduced

  5. Nonlinear dynamics of ITU TRIGA reactor

    International Nuclear Information System (INIS)

    Hizal, N.A.; Gencay, S.; Gungordu, E.; Geckinli, M.; Ciftcioglu, O.; Can, B.

    1988-01-01

    Complete dynamics of a reactor could be developed starting from the very basic principles. However such a detailed approach is often not worth the effort for a rather simple pool type reactor which may be subjected to various power excursion maneuvers without challenging its safety system. Therefore a coupled point kinetics-lumped thermal hydraulics model is taken up as the basis of the system model. Response of the reactor to ramp insertion of reactivity is observed by sampling the power channel, water, and fuel temperatures with the help of a PC. One of the important model parameters, fuel temperature feedback effect is studied during power excursions and the results are compared with those of static tests. (author)

  6. 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.

  7. Recent developments of JAEA’s Monte Carlo code MVP for reactor physics applications

    International Nuclear Information System (INIS)

    Nagaya, Yasunobu; Okumura, Keisuke; Mori, Takamasa

    2015-01-01

    Highlights: • This paper describes the recent development status of the Monte Carlo code MVP. • The basic features and capabilities of MVP are briefly described. • New capabilities useful for reactor analysis are also described. - Abstract: This paper describes the recent development status of a Monte Carlo code MVP developed at Japan Atomic Energy Agency. The basic features and capabilities of MVP are overviewed. In addition, new capabilities useful for reactor analysis are also described

  8. N Reactor Deactivation Program Plan

    International Nuclear Information System (INIS)

    Walsh, J.L.

    1993-12-01

    This N Reactor Deactivation Program Plan is structured to provide the basic methodology required to place N Reactor and supporting facilities · in a radiologically and environmentally safe condition such that they can be decommissioned at a later date. Deactivation will be in accordance with facility transfer criteria specified in Department of Energy (DOE) and Westinghouse Hanford Company (WHC) guidance. Transition activities primarily involve shutdown and isolation of operational systems and buildings, radiological/hazardous waste cleanup, N Fuel Basin stabilization and environmental stabilization of the facilities. The N Reactor Deactivation Program covers the period FY 1992 through FY 1997. The directive to cease N Reactor preservation and prepare for decommissioning was issued by DOE to WHC on September 20, 1991. The work year and budget data supporting the Work Breakdown Structure in this document are found in the Activity Data Sheets (ADS) and the Environmental Restoration Program Baseline, that are prepared annually

  9. Nuclear reactor container

    International Nuclear Information System (INIS)

    Moriyama, Takeo; Ochiai, Kanehiro; Niino, Tsuyoshi; Kodama, Toyokazu; Hirako, Shizuka.

    1988-01-01

    Purpose: To obtain structures suitable to a container structures for nuclear power plants used in those districts where earthquakes occur frequently, in which no local stresses are caused to the fundamental base portions and the workability for the fundamental structures is improved. Constitution: Basic stabilizers are attached to a nuclear reactor container (PCV) and a basic concrete recess for receiving a basic stabilizer is disposed in basic concretes. A top stabilizer is joined and fixed to a top stabilizer receiving plate at the inside of an outer shielding wall. On the other hand, a PCV top recess for conducting the load of PCV to the top stabilizer is attached to the top of the PCV. By disposing stabilizer structures allowing miner displacements at the two points, that is, the top and the lowermost portion of the PCV, no local stress concentrations can be generated to the extension on the axial direction of components due to the inner pressure of the PCV and to the horizontal load applied to the upper portion of the PCV upon earthquakes. (Yoshino, Y.)

  10. Basic design of radiation-resistant LVDTs: Linear Variable Differential Transformer

    Energy Technology Data Exchange (ETDEWEB)

    Sohn, J. M.; Park, S. J.; Kang, Y. H. (and others)

    2008-02-15

    A LVDT(Linear Variable Differential Transformer) for measuring the pressure level was used to measure the pressure of a nuclear fuel rod during the neutron irradiation test in a research reactor. A LVDT for measuring the elongation was also used to measure the elongation of nuclear fuels, and the creep and fatigue of materials during a neutron irradiation test in a research reactor. In this report, the basic design of two radiation-resistant LVDTs for measuring the pressure level and elongation are described. These LVDTs are used a under radiation environment such as a research reactor. In the basic design step, we analyzed the domestic and foreign technical status for radiation-resistant LVDTs, made part and assembly drawings and established simple procedures for their assembling. Only a few companies in the world can produce radiation-resistant LVDTs. Not only these are extremely expensive, but the prices are continuously rising. Also, it takes a long time to procure a LVDT, as it can only be bought about by an order-production. The localization of radiation-resistant LVDTs is necessary in order to provide them quickly and at a low cost. These radiation-resistant LVDTs will be used at neutron irradiation devices such as instrumented fuel capsules, special purpose capsules and a fuel test loop in research reactors. We expect that the use of neutron irradiation tests will be revitalized by the localization of radiation-resistant LVDTs.

  11. Reactor-specific spent fuel discharge projections, 1987-2020

    International Nuclear Information System (INIS)

    Walling, R.C.; Heeb, C.M.; Purcell, W.L.

    1988-03-01

    The creation of five reactor-specific spent fuel data bases that contain information on the projected amounts of spent fuel to be discharged from U.S. commercial nuclear reactors through the year 2020 is described. The data bases contain detailed spent fuel information from existing, planned, and projected pressurized water reactors (PWR) and boiling water eactors (BWR), and one existing high temperature gas reactor (HTGR). The projections are based on individual reactor information supplied by the U.S. reactor owners. The basic information is adjusted to conform to Energy Information Administration (EIA) forecasts for nuclear installed capacity, generation, and spent fuel discharged. The EIA cases considered are: No New Orders (assumes increasing burnup), No New Orders with No Increased Burnup, Upper Reference (assumes increasing burnup), Upper Reference with No Increased Burnup, and Lower Reference (assumes increasing burnup). Detailed, by-reactor tables are provided for annual discharged amounts of spent fuel, for storage requirements assuming maximum at-reactor storage, and for storage requirements assuming maximum at-reactor storage plus intra-utility transshipment of spent fuel. 8 refs., 8 figs., 10 tabs

  12. Lego Serious Play: hacia la permeabilidad del pensamiento crítico

    Directory of Open Access Journals (Sweden)

    Miriam Peña-Zabala

    2018-01-01

    Full Text Available INTRODUCCIÓN. La presente investigación indaga sobre la importancia de relacionar la enseñanza-aprendizaje con el acto de reflexionar. La hipótesis parte de la creencia de que reflexionar favorece el desarrollo del pensamiento crítico en el alumnado, y así, la comprensión y asimilación de las prácticas educativas vinculadas al arte contemporáneo en la formación inicial de profesorado. MÉTODO. Una vez definidas las preguntas de investigación, se ha optado por el método Lego Serious Play (LSP para llevar a cabo una sesión en la que se dialoga en torno a prácticas artísticas desarrolladas en el aula. Este método analiza la idea del juego simbólico como constructor de conocimiento y, por tanto, como una posible herramienta canalizadora hacia el pensamiento reflexivo. RESULTADOS. Los relatos extraídos han permitido ver resultados significativos que posibilitan mediar entre las prácticas artísticas desarrolladas y experiencias de vida, demostrando el uso de LSP para dicho cometido. DISCUSIÓN. Se pone en valor la diversidad y versatilidad que ofrece el acto de reflexionar, lo cual supone una vía significativa hacia el pensamiento crítico. También se subraya la idea de rescatar el juego como una herramienta eficaz en la educación adulta.

  13. Operational report, basics of the preliminary project for reconstruction of the RA reactor ventilation system

    International Nuclear Information System (INIS)

    Martinc, R.

    1982-01-01

    This report presents the summary of results needed for designing the reconstruction of the RA reactor ventilation system. The final complete report will published later, including results of possible additional analyses according to the needs of main detailed project. Due to the size of the facility the need of filters for particulates is expected in systems V-1 and V-2, as well as revision of the system V-4. Adsorption filters are not needed in case of operation under regular working conditions. It would be favorable, but not indispensable to construct an adsorption filter that could be used occasionally at the input of V-2 system under the upper water shielding. This filter would be switched on when dehermetization of the reactor is planned and increased radioactivity is indicated in the gas system or experimental space of the RA reactor as well as in case of fuel elements failure. The aim of applying filters is shortening the time these elements would spend in the hermetized reactor i.e. their fast removal from the reactor. It is indispensable to build-in 'emergency' highly efficient adsorption filters in the V-2 system which would be switched on in case of accidents that would cause fuel elements meltdown (with simultaneous accident dehermetization of the heavy water system) [sr

  14. Regulation for installation and operation of marine reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The regulation is defined under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and the provisions of the order for execution of the law. The regulation is applied to marine reactors and reactors installed in foreign nuclear ships. Basic concepts and terms are explained, such as: radioactive waste; fuel assembly; exposure dose; accumulative dose; controlled area; safeguarded area; inspected surrounding area and employee. The application for permission of installation of reactors shall list maximum continuous thermal power, location and general structure of reactor facilities, structure and equipment of reactors and treatment and storage facilities of nuclear fuel materials, etc. The application for permission of reactors installed in foreign ships shall describe specified matters according to the provisions for domestic reactors. The operation program of reactors for three years shall be filed to the Minister of Transportation for each reactor every fiscal year from that year when the operation is expected to start. Records shall be made for each reactor and kept for particular periods on inspection of reactor facilities, operation, fuel assembly, control of radiation, maintenance and others. Exposure doses, inspection and check up of reactor facilities, operation of reactors, transport and storage of nuclear fuel materials, etc. are designated in detail. (Okada, K.)

  15. Heterogeneous gas core reactor

    International Nuclear Information System (INIS)

    Han, K.I.

    1977-01-01

    Preliminary investigations of a heterogeneous gas core reactor (HGCR) concept suggest that this potential power reactor offers distinct advantages over other existing or conceptual reactor power plants. One of the most favorable features of the HGCR is the flexibility of the power producing system which allows it to be efficiently designed to conform to a desired optimum condition without major conceptual changes. The arrangement of bundles of moderator/coolant channels in a fissionable gas or mixture of gases makes a truly heterogeneous nuclear reactor core. It is this full heterogeneity for a gas-fueled reactor core which accounts for the novelty of the heterogeneous gas core reactor concept and leads to noted significant advantages over previous gas core systems with respect to neutron and fuel economy, power density, and heat transfer characteristics. The purpose of this work is to provide an insight into the design, operating characteristics, and safety of a heterogeneous gas core reactor system. The studies consist mainly of neutronic, energetic and kinetic analyses of the power producing and conversion systems as a preliminary assessment of the heterogeneous gas core reactor concept and basic design. The results of the conducted research indicate a high potential for the heterogeneous gas core reactor system as an electrical power generating unit (either large or small), with an overall efficiency as high as 40 to 45%. The HGCR system is found to be stable and safe, under the conditions imposed upon the analyses conducted in this work, due to the inherent safety of ann expanding gaseous fuel and the intrinsic feedback effects of the gas and water coolant

  16. Light-water nuclear reactors

    International Nuclear Information System (INIS)

    Drevon, G.

    1983-01-01

    This work gives basic information on light-water reactors which is advanced enough for the reader to become familiar with the essential objectives and aspects of their design, their operation and their insertion in the industrial, economic and human environment. In view of the capital role of electric energy in the modern economy a significant place is given to electron-nuclear power stations, particularly those of the type adopted for the French programme. The work includes sixteen chapters. The first chapter relates the history and presents the various applications of light water reactors. The second refers to the general elementary knowledge of reactor physics. The third chapter deals with the high power light-water nuclear power station and thereby introduces the ensuing chapters which, up to and including chapter 13, are devoted to the components and the various aspects of the operation of power stations, in particular safety and the relationship with the environment. Chapter 14 provides information on the reactors adapted to applications other than the generation of electricity on an industrial scale. Chapter 15 shows the extent of the industrial effort devoted to light-water reactors and chapter 16 indicates the paths along which the present work is preparing the future of these reactors. The various chapters have been written to allow for separate consultation. An index of the main technical terms and a bibliography complete the work [fr

  17. STARFIRE: a commercial tokamak reactor

    International Nuclear Information System (INIS)

    1979-12-01

    The purpose of this document is to provide an interim status report on the STARFIRE project for the period of May to September 1979. The basic objective of the STARFIRE project is to develop a design concept for a commercial tokamak fusion electric power plant based on the deuterium/tritium/lithium fuel cycle. The key technical objective is to develop the best embodiment of the tokamak as a power reactor consistent with credible engineering solutions to design problems. Another key goal of the project is to give careful attention to the safety and environmental features of a commercial fusion reactor

  18. Safety design study of fast breeder reactors in Japan

    International Nuclear Information System (INIS)

    Miura, M.; Inagaki, T.

    1992-01-01

    This paper reports on two fast breeder reactor (FBR) concepts, the tank type and the loop type, that have been studied as possible reactor designs to be used for a demonstration FBR (DFBR). The basic principle fo the DFBR design is to ensure plant safety through a defense-in-depth methodology. Improvements in the seismic and thermal stress designs have been attempted for both reactor concepts. The system design study strives to maximize the reliability of the safety-related systems and to rationalize commercialization of the plant

  19. Advanced core monitoring technology for WWER reactors

    International Nuclear Information System (INIS)

    Nguyen, T.Q.; Casadei, A.L.; Doshi, P.K.

    1993-01-01

    The Westinghouse BEACON online monitoring system has been developed to provide continuous core monitoring and operational support for pressurized water reactor using movable detectors (fission chamber) and core thermocouples. The basic BEACON core monitoring methodology is described. Traditional WWER reactors use rhodium fixed in-core detectors as the means to provide detailed core power distribution for surveillance purposes. An adapted version of the BEACON advanced core monitoring and support system is described which seems to be, due to the different demand/response requirements, the optimal solution (for routine surveillance and anomaly detection) for WWER reactors with existing fixed in-core detectors. (Z.S.) 4 refs

  20. Present status of high-temperature engineering test reactor (HTTR) program

    International Nuclear Information System (INIS)

    Tanaka, Toshiyuki; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru; Tobioka, Toshiaki

    1994-01-01

    The 30MWt HTTR is a high-temperature gas-cooled reactor (HTGR), with a maximum helium coolant temperature of 950degC at the reactor outlet. The construction of the HTTR started in March 1991, with first criticality to be followed in 1998 after commissioning testing. At present the HTTR reactor building (underground part) and its containment vessel have been almost completed and its main components, such as a reactor pressure vessel (RPV), an intermediate heat exchanger, hot gas pipings and graphite core structures, are now manufacturing at their factories at the target of their installation starting in 1994. The project is intended to establish and upgrade the technology basis necessary for HTGR developments. Japan Atomic Energy Research Institute (JAERI) also plans to conduct material and fuel irradiation tests as an innovative basic research after attaining rated power and coolant temperature. Innovative basic researches are now in great request. The paper describes major features of HTTR, present status of its construction and research and test using HTTR. (author)

  1. Present status of High-Temperature engineering Test Reactor (HTTR) program

    International Nuclear Information System (INIS)

    Tanaka, Toshiyuki; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru; Tobioka, Toshiaki

    1993-01-01

    The 30MWt HTTR is a high-temperature gas-cooled reactor (HTGR), with a maximum helium coolant temperature of 950 deg C at the reactor outlet. The construction of the HTTR started in March 1991, with first criticality to be followed in 1998 after commissioning testing. At present the HTTR reactor building (underground part) and its containment vessel have been almost completed and its main components, such as a reactor pressure vessel (RPV), an intermediate heat exchanger, hot gas pipings and graphite core structures, are now manufacturing at their factories at the target of their installation starting in 1994. The project is intended to establish and upgrade the technology basis necessary for HTGR developments. Japan Atomic Energy Research Institute (JAERI) also plans to conduct material and fuel irradiation tests as an innovative basic research after attaining rated power and coolant temperature. Innovative basic researches are now in great request. The paper describes major features of HTTR, present status of its construction and research and test plan using HTTR. (author)

  2. Seismic Margin Assessment for Research Reactor using Fragility based Fault Tree Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kwag, Shinyoung; Oh, Jinho; Lee, Jong-Min; Ryu, Jeong-Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The research reactor has been often subjected to external hazards during the design lifetime. Especially, a seismic event can be one of significant threats to the failure of structure system of the research reactor. This failure is possibly extended to the direct core damage of the reactor. For this purpose, the fault tree for structural system failure leading to the core damage under an earthquake accident is developed. The failure probabilities of basic events are evaluated as fragility curves of log-normal distributions. Finally, the plant-level seismic margin is investigated by the fault tree analysis combining with fragility data and the critical path is identified. The plant-level probabilistic seismic margin assessment using the fragility based fault tree analysis was performed for quantifying the safety of research reactor to a seismic hazard. For this, the fault tree for structural system failure leading to the core damage of the reactor under a seismic accident was developed. The failure probabilities of basic events were evaluated as fragility curves of log-normal distributions.

  3. Plasma nitriding monitoring reactor: A model reactor for studying plasma nitriding processes using an active screen

    Science.gov (United States)

    Hamann, S.; Börner, K.; Burlacov, I.; Spies, H.-J.; Strämke, M.; Strämke, S.; Röpcke, J.

    2015-12-01

    A laboratory scale plasma nitriding monitoring reactor (PLANIMOR) has been designed to study the basics of active screen plasma nitriding (ASPN) processes. PLANIMOR consists of a tube reactor vessel, made of borosilicate glass, enabling optical emission spectroscopy (OES) and infrared absorption spectroscopy. The linear setup of the electrode system of the reactor has the advantages to apply the diagnostic approaches on each part of the plasma process, separately. Furthermore, possible changes of the electrical field and of the heat generation, as they could appear in down-scaled cylindrical ASPN reactors, are avoided. PLANIMOR has been used for the nitriding of steel samples, achieving similar results as in an industrial scale ASPN reactor. A compact spectrometer using an external cavity quantum cascade laser combined with an optical multi-pass cell has been applied for the detection of molecular reaction products. This allowed the determination of the concentrations of four stable molecular species (CH4, C2H2, HCN, and NH3). With the help of OES, the rotational temperature of the screen plasma could be determined.

  4. Plasma nitriding monitoring reactor: A model reactor for studying plasma nitriding processes using an active screen

    International Nuclear Information System (INIS)

    Hamann, S.; Röpcke, J.; Börner, K.; Burlacov, I.; Spies, H.-J.; Strämke, M.; Strämke, S.

    2015-01-01

    A laboratory scale plasma nitriding monitoring reactor (PLANIMOR) has been designed to study the basics of active screen plasma nitriding (ASPN) processes. PLANIMOR consists of a tube reactor vessel, made of borosilicate glass, enabling optical emission spectroscopy (OES) and infrared absorption spectroscopy. The linear setup of the electrode system of the reactor has the advantages to apply the diagnostic approaches on each part of the plasma process, separately. Furthermore, possible changes of the electrical field and of the heat generation, as they could appear in down-scaled cylindrical ASPN reactors, are avoided. PLANIMOR has been used for the nitriding of steel samples, achieving similar results as in an industrial scale ASPN reactor. A compact spectrometer using an external cavity quantum cascade laser combined with an optical multi-pass cell has been applied for the detection of molecular reaction products. This allowed the determination of the concentrations of four stable molecular species (CH 4 , C 2 H 2 , HCN, and NH 3 ). With the help of OES, the rotational temperature of the screen plasma could be determined

  5. Plasma nitriding monitoring reactor: A model reactor for studying plasma nitriding processes using an active screen

    Energy Technology Data Exchange (ETDEWEB)

    Hamann, S., E-mail: hamann@inp-greifswald.de; Röpcke, J. [INP-Greifswald, Felix-Hausdorff-Str. 2, 17489 Greifswald (Germany); Börner, K.; Burlacov, I.; Spies, H.-J. [TU Bergakademie Freiberg, Institute of Materials Engineering, Gustav-Zeuner-Str. 5, 09599 Freiberg (Germany); Strämke, M.; Strämke, S. [ELTRO GmbH, Arnold-Sommerfeld-Ring 3, 52499 Baesweiler (Germany)

    2015-12-15

    A laboratory scale plasma nitriding monitoring reactor (PLANIMOR) has been designed to study the basics of active screen plasma nitriding (ASPN) processes. PLANIMOR consists of a tube reactor vessel, made of borosilicate glass, enabling optical emission spectroscopy (OES) and infrared absorption spectroscopy. The linear setup of the electrode system of the reactor has the advantages to apply the diagnostic approaches on each part of the plasma process, separately. Furthermore, possible changes of the electrical field and of the heat generation, as they could appear in down-scaled cylindrical ASPN reactors, are avoided. PLANIMOR has been used for the nitriding of steel samples, achieving similar results as in an industrial scale ASPN reactor. A compact spectrometer using an external cavity quantum cascade laser combined with an optical multi-pass cell has been applied for the detection of molecular reaction products. This allowed the determination of the concentrations of four stable molecular species (CH{sub 4}, C{sub 2}H{sub 2}, HCN, and NH{sub 3}). With the help of OES, the rotational temperature of the screen plasma could be determined.

  6. Research reactor RB, technical characteristics and experimental possibilities

    International Nuclear Information System (INIS)

    Sotic, O.; Vranic, S.

    1978-01-01

    Nuclear research reactor RB tn the Nuclear Engineering Laboratory at the Institute of Nuclear Sciences 'Boris Kidric' in Vinca is the first reactor system built in Yugoslavia in 1958. In this report, the basic technical characteristics of this reactor are described, as well as the experimental possibilities it offers to the users. Its relatively simple construction and flexibility enables direct measurements of a series of physical parameters, and the absence of the biological protection shield makes it very useful for Various biological and other irradiations and dosimetric measurements Where strong neutron source is required. (author) [sr

  7. Report 1984-1985. Department of Basic Research

    International Nuclear Information System (INIS)

    1986-01-01

    A report is presented of the activities performed by the Department of Basic research of the Bariloche Atomic Center during the period 1984-1985. In this report, works on different subjects related to Physics, are grouped in six sections: Low temperatures, Atomic collisions, Metals, Neutrons and Reactors, Magnetic Resonances and Theory. In addition, a list of publications, made by the Department during said period, is included. (M.E.L.) [es

  8. Reactor-specific spent fuel discharge projections: 1985 to 2020

    International Nuclear Information System (INIS)

    Heeb, C.M.; Libby, R.A.; Walling, R.C.; Purcell, W.L.

    1986-09-01

    The creation of four spent-fuel data bases that contain information on the projected amounts of spent fuel to be discharged from US commercial nuclear reactors through the year 2020 is described. The data bases contain detailed spent-fuel information from existing, planned, and projected pressurized water reactors (PWR) and boiling water reactors (BWR). The projections are based on individual reactor information supplied by the US reactor owners. The basic information is adjusted to conform to Energy Information Agency (EIA) forecasts for nuclear installed capacity, generation, and spent fuel discharged. The EIA cases considered are: (1) No New Orders with Extended Burnup, (2) No New Orders with Constant Burnup, (3) Middle Case with Extended Burnup, and (4) Middle Case with Constant Burnup. Detailed, by-reactor tables are provided for annual discharged amounts of spent fuel, for storage requirements assuming maximum-at-reactor storage, and for storage requirements assuming maximum-at-reactor plus intra-utility transshipment of spent fuel

  9. Basic design report of SMART

    International Nuclear Information System (INIS)

    Chang, M. H.; Yeo, J. W.; Zee, Q. S.; Lee, D. J.; Park, K. B.; Koo, I. S.; Kim, H. C.; Kim, J. I.

    2002-03-01

    KAERI has been developing a 330MWt integral reactor, SMART and its application system since 1997. SMART is being developed for use as an energy source for small-scale power generation and seawater desalination. The SMART system can produce portable water of 40.000m 3 /day using the MED-TVC desalination process and about 90MW of electricity. Although the design of SMART is based on the current pressurized water reactor technology, new technologies such as inherent safety and passive safety have been applied, and system simplification and modularization, innovations in manufacturing and installation technologies have been implemented culminating in a design that has enhanced safety and economy, and is environment-friendly. The objective of this design report is to provide the overall information on the basic design of SMART NSSS, and the applied technologies. The information covers mainly NSSS design with some information on the desalination system. For the secondary system, only the information directly related to the coupling with NSSS are covered

  10. Basic analysis and comparison among GCFR and LMFBR characteristics in thorium cycle by difusion theory in one energy group

    International Nuclear Information System (INIS)

    Sabundjian, G.; Ishiguro, Y.

    1982-01-01

    A preliminary study of the neutronic characteristics of fast of fast breeding reactors with thorium cycle, is done, using models and simplified methods of reactor analysis, aiming to meet an adequate type of breeder reactor with an efficient thorium utilization, that is abundant at Brazil. Basic methods of cross section and reactor calculations are studied, and they are applied for the analysis of GCFRs and LMFBRs breeding characteristics. (E.G.) [pt

  11. The SLOWPOKE-2 reactor with low enrichment uranium oxide fuel

    International Nuclear Information System (INIS)

    Townes, B.M.; Hilborn, J.W.

    1985-06-01

    A SLOWPOKE-2 reactor core contains less than 1 kg of highly enriched uranium (HEU) and the proliferation risk is very low. However, to overcome proliferation concerns a new low enrichment uranium (LEU) fuelled reactor core has been designed. This core contains approximately 180 fuel elements based on the Zircaloy-4 clad UOsub(2) CANDU fuel element, but with a smaller outside diameter. The physics characteristics of this new reactor core ensure the inherent safety of the reactor under all conceivable conditions and thus the basic SLOWPOKE safety philosophy which permits unattended operation is not affected

  12. A fast-running fuel management program for a CANDU reactor

    International Nuclear Information System (INIS)

    Choi, Hangbok

    2000-01-01

    A fast-running fuel management program for a CANDU reactor has been developed. The basic principle of this program is to select refueling channels such that the reference reactor conditions are maintained by applying several constraints and criteria when selecting refueling channels. The constraints used in this program are the channel and bundle power and the fuel burnup. The final selection of the refueling channel is determined based on the priority of candidate channels, which enhances the reactor power distribution close to the time-average model. The refueling simulation was performed for a natural uranium CANDU reactor and the results were satisfactory

  13. Nuclear Reactor RA Safety Report, Vol. 16, Maximum hypothetical accident

    International Nuclear Information System (INIS)

    1986-11-01

    Fault tree analysis of the maximum hypothetical accident covers the basic elements: accident initiation, phase development phases - scheme of possible accident flow. Cause of the accident initiation is the break of primary cooling pipe, heavy water system. Loss of primary coolant causes loss of pressure in the primary circuit at the coolant input in the reactor vessel. This initiates safety protection system which should automatically shutdown the reactor. Separate chapters are devoted to: after-heat removal, coolant and moderator loss; accident effects on the reactor core, effects in the reactor building, and release of radioactive wastes [sr

  14. Reactor Engineering Department annual report (April 1, 1988 - March 31, 1989)

    International Nuclear Information System (INIS)

    1989-09-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1988 (April 1, 1988 - March 31, 1989). The Department has promoted cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and also to PNC's fast reactor project. Other major Department's programs are the assessment of the high conversion light water reactor and the design activities of advanced reactor system. Application of a high energy accelerator to the nuclear engineering is also preliminarily assessed. The report also contains the latest progress in various basic researches as nuclear data and group constants, theoretical methods and code development, reactor physics experiments and analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/ diagnosis and technical developments related to the reactor physics facilities. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  15. The safety of pressurized water reactors

    International Nuclear Information System (INIS)

    Panossian, J.; Tanguy, P.

    1991-01-01

    In this paper we present a review of the status of the safety level of modern pressurized water reactors, that is to say those that meet the safety criteria accepted today by the international nuclear community. We will mainly rely on the operating experience and the Probabilistic Safety Assessments concerning French reactors. We will not back over the basic safety concepts of these reactors, which are well known. We begin with a brief review of some of the lessons learned from the two main accidents discussed in the present meeting. Three Mile Island and Chernobyl, without entering into details presented in previous papers. The presentation ends with a rather lengthy conclusion, aimed more at those not directly involved in the technical details of nuclear safety matters

  16. Inertial-fusion-reactor studies at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Monsler, M.J.; Meier, W.R.

    1982-08-01

    We present results of our reactor studies for inertial-fusion energy production. Design studies of liquid-metal wall chambers have led to reactors that are remarkably simple in design, and that promise long life and low cost. Variants of the same basic design, called HYLIFE, can be used for electricity production, as a fissile-fuel factory, a dedicated tritium breeder, or hybrids of each

  17. An optimization method for parameters in reactor nuclear physics

    International Nuclear Information System (INIS)

    Jachic, J.

    1982-01-01

    An optimization method for two basic problems of Reactor Physics was developed. The first is the optimization of a plutonium critical mass and the bruding ratio for fast reactors in function of the radial enrichment distribution of the fuel used as control parameter. The second is the maximization of the generation and the plutonium burnup by an optimization of power temporal distribution. (E.G.) [pt

  18. Development of physical conceptions of fast reactors

    International Nuclear Information System (INIS)

    Khomyakov, Yu.S.; Matveev, V.I.; Moiseev, A.V.

    2013-01-01

    • Russian experience in developing fast reactors has proved clearly scientific justification of conceptual physical principles and their technical feasibility. • However, the potential of fast reactors caused by their physical features has not been fully realized. • In order to assure the real possibility of transition to the nuclear power with fast reactors by about 2030 it is necessary to consistently update fast reactor designs for solving the following key problems: - increasing of self-protection level of reactor core; - improvement of technical and economical characteristics; - solution of the problems related to the fuel supply of nuclear power and assimilation of closed nuclear fuel cycle; - disposal of long lived radioactive waste and transmutation of minor actinides. • Russian program (2010-2020) on the development of basic concepts of the new generation reactors implies successive solution of the above problems. • New technical decisions will be demonstrated by development and assimilation of the new reactors: - BN-800 – development of the fuel cycle infrastructure and mastering of the new types of fuel; - BN-1200 reactor – demonstration economical efficiency of fast reactor and new level of safety; - BREST development and demonstration new heavy liquid metal coolant technology and alternative design concept

  19. About a fuel for burnup reactor of periodical pulsed nuclear pumped laser

    International Nuclear Information System (INIS)

    Volkov, A.I.; Lukin, A.V.; Magda, L.E.; Magda, E.P.; Pogrebov, I.S.; Putnikov, I.S.; Khmelnitsky, D.V.; Scherbakov, A.P.

    1998-01-01

    A physical scheme of burnup reactor for a Periodic Pulsed Nuclear Pumped Laser was supposed. Calculations of its neutron physical parameters were made. The general layout and construction of basic elements of the reactor are discussed. The requirements for the fuel and fuel elements are established. (author)

  20. Generation IV reactors: economics

    International Nuclear Information System (INIS)

    Dupraz, B.; Bertel, E.

    2003-01-01

    The operating nuclear reactors were built over a short period: no more than 10 years and today their average age rounds 18 years. EDF (French electricity company) plans to renew its reactor park over a far longer period : 30 years from 2020 to 2050. According to EDF this objective implies 3 constraints: 1) a service life of 50 to 60 years for a significant part of the present operating reactors, 2) to be ready to built a generation 3+ unit in 2020 which infers the third constraint: 3) to launch the construction of an EPR (European pressurized reactor) prototype as soon as possible in order to have it operating in 2010. In this scheme, generation 4 reactor will benefit the feedback experience of generation 3 and will take over in 2030. Economic analysis is an important tool that has been used by the generation 4 international forum to select the likely future reactor systems. This analysis is based on 4 independent criteria: the basic construction cost, the construction time, the operation and maintenance costs and the fuel cycle cost. This analysis leads to the evaluation of the global cost of electricity generation and of the total investment required for each of the reactor system. The former defines the economic competitiveness in a de-regulated energy market while the latter is linked to the financial risk taken by the investor. It appears, within the limits of the assumptions and models used, that generation 4 reactors will be characterized by a better competitiveness and an equivalent financial risk when compared with the previous generation. (A.C.)

  1. Use of microcomputers in the environmental analysis of research nuclear reactors

    International Nuclear Information System (INIS)

    Molnary, L. de

    1988-01-01

    An automatic meteorological monitoring system developed by Department of Reactor Technology of IPEN/CNEN-SP, is described. The system integrates an environmental analysis program of research reactors. The basic characteristic of this system is the utilization of personal computers to control all meteorological data aquisition in a several levels instrumented tower. (author) [pt

  2. Preliminary Study for Inventories of Minor Actinides in Thorium Molten Salt Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Choong Wie; Kim, Hee Reyoung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

    2015-05-15

    It has different characteristic with the conventional reactors which use a solid fuel. It can continually supply the fuel by online refueling and reprocessing of minor actinides so that those can be separated and eliminated from the reactor. The MSR maintains steady state except initial stage and the reactor becomes stable. In this research, considering online refueling, bubbling and reprocessing, the basic concept for evaluation of the inventory of minor actinide in the molten salt reactor is driven using the Bateman equation. The simulation results, where REM and MCNP code from CNRS (Centre National de la Recherche Scientifique) applied to the concept equation are analyzed. The analysis of the basic concept was carried out for evaluation of the inventory of the minor actinides in MSR. It was thought that the inventories of the minor actinides should be evaluated by solving the modified Bateman equation due to the MSR characteristic of online refueling, chemical reprocessing and bubbling.

  3. Preliminary Study for Inventories of Minor Actinides in Thorium Molten Salt Reactor

    International Nuclear Information System (INIS)

    Lee, Choong Wie; Kim, Hee Reyoung

    2015-01-01

    It has different characteristic with the conventional reactors which use a solid fuel. It can continually supply the fuel by online refueling and reprocessing of minor actinides so that those can be separated and eliminated from the reactor. The MSR maintains steady state except initial stage and the reactor becomes stable. In this research, considering online refueling, bubbling and reprocessing, the basic concept for evaluation of the inventory of minor actinide in the molten salt reactor is driven using the Bateman equation. The simulation results, where REM and MCNP code from CNRS (Centre National de la Recherche Scientifique) applied to the concept equation are analyzed. The analysis of the basic concept was carried out for evaluation of the inventory of the minor actinides in MSR. It was thought that the inventories of the minor actinides should be evaluated by solving the modified Bateman equation due to the MSR characteristic of online refueling, chemical reprocessing and bubbling

  4. Safety of RBMK reactors: Major results and prospects

    International Nuclear Information System (INIS)

    Sidorenko, V.A.

    1996-01-01

    The paper considers the following issues: basic reasons for the advent of NPPs with RBMK reactors; the logic of identifying top-priority measures immediately after the accident; top-priority measures for improving the safety and reliability of NPPs with RBMK reactors; upgrading NPPs with RBMK reactors in compliance with the Norms; programmes for retrofitting and upgrading of NPPs of the ''Rosnergoatom'' Concern and progress with their implementation as of April 1996; the safety of RBMK plants and the programmes of its enhancement with regard to modern requirements in the light of national and international assessment; objective indicators of safety, reliability, and economic efficiency of NPPs with RBMK reactors; economics: rationale for continuing plants operation till the end of their design lifetime. 8 refs, 3 figs

  5. PROCESAMIENTO DE IMÁGENES PARA LA PLANEACIÓN DE RUTAS PARA ROBOTS MÓVILES BASADOS EN LEGO MINDSTORMS NXT

    Directory of Open Access Journals (Sweden)

    Jesús Alberto Torres Velásquez

    2014-11-01

    Full Text Available El presente artículo contiene el procedimiento para implementar diferentes técnicas de procesamiento de  imágenes y principalmente el algoritmo de esqueletización con el objetivo de planificar rutas libres de obstáculos para robots móviles; mediante una fotografía tomada sobre un área determinada con los obstáculos y el robot (construido con el kit de robótica LEGO MINDSTORMS NXT. Se realiza el debido procesamiento a dicha imagen, para luego, de forma remota enviar una serie de órdenes vía Bluetooth desde un computador usando MATLAB; ordenes generadas por el algoritmo aplicado sobre la imagen ya procesada, con el fin de obtener el desplazamiento de la plataforma móvil a un punto de llegada determinado por el usuario. 

  6. Cost aspects of the research reactor fuel cycle

    International Nuclear Information System (INIS)

    2010-01-01

    Research reactors have made valuable contributions to the development of nuclear power, basic science, materials development, radioisotope production for medicine and industry, and education and training. In doing so, they have provided an invaluable service to humanity. Research reactors are expected to make important contributions in the coming decades to further development of the peaceful uses of nuclear technology, in particular for advanced nuclear fission reactors and fuel cycles, fusion, high energy physics, basic research, materials science, nuclear medicine, and biological sciences. However, in the context of decreased public sector support, research reactors are increasingly faced with financial constraints. It is therefore of great importance that their operations are based on a sound understanding of the costs of the complete research reactor fuel cycle, and that they are managed according to sound financial and economic principles. This publication is targeted at individuals and organizations involved with research reactor operations, with the aim of providing both information and an analytical framework for assessing and determining the cost structure of fuel cycle related activities. Efficient management of fuel cycle expenditures is an important component in developing strategies for sustainable future operation of a research reactor. The elements of the fuel cycle are presented with a description of how they can affect the cost efficient operation of a research reactor. A systematic review of fuel cycle choices is particularly important when a new reactor is being planned or when an existing reactor is facing major changes in its fuel cycle structure, for example because of conversion of the core from high enriched uranium (HEU) to low enriched uranium (LEU) fuel, or the changes in spent fuel management provision. Review and optimization of fuel cycle issues is also recommended for existing research reactors, even in cases where research reactor

  7. Nuclear Burning Wave Modular Fast Reactor Concept

    International Nuclear Information System (INIS)

    Kodochigov, N.G.; Sukharev, Yu.P.

    2014-01-01

    The necessity to provide nuclear power industry, comparable in a scope with power industry based on a traditional fuel, inspired studies of an open-cycle fast reactor aimed at: - solution of the problem of fuel provision by implementing the highest breeding characteristics of new fissile materials of raw isotopes in a fast reactor and applying accumulated fissile isotopes in the same reactor, independently on a spent fuel reprocessing rate in the external fuel cycle; - application of natural or depleted uranium for makeup fuel, which, with no spent fuel reprocessing, forms the most favorable non-proliferation conditions; - application of inherent properties of the core and reactor for safety provision. The present report, based on previously published papers, gives the theoretical backgrounds of the concept of the reactor with a nuclear burning wave, in which an enriched-fuel core (driver) is replaced by a blanket, and basic conditions for nuclear burning wave initiating and keeping are shown. (author)

  8. Australia needs to replace the HIFAR reactor

    International Nuclear Information System (INIS)

    Garnett, Helen

    1993-01-01

    Central to the execution of ANSTO's objectives has been the operation since 1958 of the multipurpose HIFAR research reactor and related infrastructure. However, HIFAR's irradiation facilities, which are used for the provision of radiopharmaceuticals essential for nuclear medicine in Australia, have a limited capacity. The author stated that HIFAR's neutron beam facilities, which are needed by Australian scientists to undertake basic structural studies on a wide range of materials, are unable to provide the resolution and information required to keep Australia in the league of technologically advanced nations. The neutron flux and design limitations of older reactors such as HIFAR inhibit the upgrading of neutron beam facilities to modern standards. It is emphasised that while the cost of the new reactor is a vital issue, what is a prevailing importance is analyses of the cost-benefit and effectiveness of the new reactor, which will be undertaken by the Research Reactor Review. Some of these benefits are briefly outlined. ills

  9. Safety assessment of Department of Energy nuclear reactors

    International Nuclear Information System (INIS)

    1981-03-01

    One of the first tasks of the NFPQT Committee was to determine which DOE reactors would be assessed. The Committee determined that in view of the limited time available to conduct the assessment, 13 DOE reactors were of such size (physical, power or fission product inventory) to warrant review. This determination was approved by the Under Secretary. A decision was also made in the cases of three weapons material production reactors, C, K and P, to concentrate on the K reactor only, since all three are of the same basic design, have the same operating features, are all at the same site, and are all operated by the same contractor. The assessment was accomplished in the following ways: reviewing the results of assessments conducted by the DOE organizations with reactor safety responsibilities, which were undertaken in compliance with the request of the various program directors; reviewing selected documents that were requested by the Committee and assembled at DOE Headquarters; interviewing DOE Headquarters and Field Office personnel; and conducting on-site reviews of four reactors located at four different sites. The four reactors for on-site reviews were: Advanced Test Reactor (ATR); K Production Reactor; High Flux Beam Reactor (HFBR); and High Flux Isotope Reactor (HFIR). Specific findings and recommendations from the assessment are presented

  10. Use of the VR-1 ''Vrabec'' training reactor

    International Nuclear Information System (INIS)

    Matejka, K.; Kolros, A.; Krops, S.; Polach, S.; Sklenka, L.

    1994-01-01

    An overview is presented of the extent and ways of using the VR-1 training reactor, which is operated by the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague. A list and the characteristics of 16 problems developed for teaching purposes is given, and the 14 faculties and 2 research institutes participating in the teaching activities are listed. The reactor is used in the education and training of nuclear scientists and engineers. The instrumentation, experimental, handling and operating tools, as well as documentation and texts relating to the reactor are described. The following examples of the teaching activities are included: a guided visit to the operating reactor site, reactor dynamics study and delayed neutron measurement, training course, and the basic criticality experiment. Nuclear safety aspects (hypothetical accidents, quality control and system qualification demonstration, safety culture) are stressed during the education. The reactor department is involved in international cooperation projects. (J.B.). 3 refs

  11. Design of micro-reactors and solar photocatalytic prototypes; Diseno de micro-reactores y prototipos fotocataliticos solares

    Energy Technology Data Exchange (ETDEWEB)

    Flores E, R.M.; Hernandez H, M.; Perusquia del Cueto, M.R.; Bonifacio M, J.; Jimenez B, J.; Ortiz O, H.B.; Castaneda J, G.; Lugo H, M. [ININ, Km. 36.5 Carr. Mexico-Toluca, 52750 La Marquesa, Ocoyoacac (Mexico)]. e-mail: rmfe@nuclear.inin.mx

    2007-07-01

    In the ININ is carried out research in heterogeneous photocatalysis using artificial light for to degrade organic compounds. In this context, it is sought to use the solar radiation as energy source to knock down costs. Of equal form it requires to link the basic and applied research. For it, a methodology that allows to design and to build micro-reactors and plants pilot has been developed, like previous step, to request external supports and to a future commercialization. The beginning of these works gave place to the partial construction of a prototype of photocatalytic reactor of the cylinder-parabolic composed type (CPC)

  12. Reactor physics using a microcomputer

    International Nuclear Information System (INIS)

    Murray, R.L.

    1983-01-01

    The object of the work reported is to develop educational computer modules for all aspects of reactor physics. The modules consist of a description of the theory, mathematical method, computer program listing, sample calculations, and problems for the student, along with a card deck. Modules were first written in FORTRAN for an IBM 360/75, then later in BASIC for microcomputers. Problems include: limitation of equipment, choice of format for the program, the variety of dialects of BASIC used in the different microcomputer and peripherals brands, and knowing when to quit in the process of developing a program

  13. Reactor-specific spent fuel discharge projections: 1986 to 2020

    International Nuclear Information System (INIS)

    Heeb, C.M.; Walling, R.C.; Purcell, W.L.

    1987-03-01

    The creation of five reactor-specific spent fuel data bases that contain information on the projected amounts of spent fuel to be discharged from US commercial nuclear reactors through the year 2020 is described. The data bases contain detailed spent-fuel information from existing, planned, and projected pressurized water reactors (PWR) and boiling water reactors (BWR). The projections are based on individual reactor information supplied by the US reactor owners. The basic information is adjusted to conform to Energy Information Agency (EIA) forecasts for nuclear installed capacity, generation, and spent fuel discharged. The EIA cases considered are: (1) No new orders with extended burnup, (2) No new orders with constant burnup, (3) Upper reference (which assumes extended burnup), (4) Upper reference with constant burnup, and (5) Lower reference (which assumes extended burnup). Detailed, by-reactor tables are provided for annual discharged amounts of spent fuel, for storage requirements assuming maximum-at-reactor storage, and for storage requirements assuming maximum-at-reactor plus intra-utility transshipment of spent fuel. 6 refs., 8 figs., 8 tabs

  14. Corrosion Behaviour of Mg Alloys in Various Basic Media: Application of Waste Encapsulation of Fuel Decanning from UNGG Nuclear Reactor

    Science.gov (United States)

    Lambertin, David; Frizon, Fabien; Blachere, Adrien; Bart, Florence

    The dismantling of UNGG nuclear reactor generates a large volume of fuel decanning. These materials are based on Mg-Zr alloy. The dismantling strategy could be to encapsulate these wastes into an ordinary Portland cement (OPC) or geopolymer (aluminosilicate material) in a form suitable for storage. Studies have been performed on Mg or Mg-Al alloy in basic media but no data are available on Mg-Zr behaviour. The influence of representative pore solution of both OPC and geopolymer with Mg-Zr alloy has been studied on corrosion behaviour. Electrochemical methods have been used to determine the corrosion densities at room temperature. Results show that the corrosion densities of Mg-Zr alloy in OPC solution is one order of magnitude more important than in a geopolymer solution environment and the effect of an inhibiting agent has been undertaken with Mg-Zr alloy. Evaluation of corrosion hydrogen production during the encapsulation of Mg-Zr alloy in both OPC and geopolymer has also been done.

  15. TekkiKids: Technology clubs for children

    CSIR Research Space (South Africa)

    Marais, Mario A

    2007-04-01

    Full Text Available to be a good testing ground for the use of novel ways of introducing concepts such as programming. The difficulty that some of the learners experienced in constructing devices using Lego and other materials highlighted the need for basic skills that can...

  16. Quality assurance in the manufacture of metallic uranium fuel for research reactors

    International Nuclear Information System (INIS)

    Shah, B.K.; Kumar, Arbind; Nanekar, P.P.; Vaidya, P.R.

    2009-01-01

    Two Research Reactors viz. CIRUS and DHRUVA are operating at Trombay since 1960 and 1985 respectively. Cirus is a 40 MWth reactor using heavy water as moderator and light water as coolant. Dhruva is a 100 MWth reactor using heavy water as moderator and coolant. The maximum neutron flux of these reactors are 6.7 x 10 13 n/cm 2 /s (Cirus) and 1.8 x 10 14 n/cm 2 /s (Dhruva). Both these reactors are used for basic research, R and D in reactor technology, isotope production and operator training. Fuel material for these reactors is natural uranium metallic rods claded in finned aluminium (99.5%) tubes. This presentation will discuss various issues related to fabrication quality assurance and reactor behavior of metallic uranium fuel used in research reactors

  17. Reactor Engineering Department annual report (April 1, 1990 - March 31, 1991)

    International Nuclear Information System (INIS)

    1991-09-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1990 (April 1, 1990 - March 31, 1991). The major Department's programs promoted in the year are the assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  18. Reactor Engineering Department annual report (April 1, 1991-March 31, 1992)

    International Nuclear Information System (INIS)

    1992-08-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1991 (April 1, 1991-March 31, 1992). The major Department's programs promoted in the year are assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researchers on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative work to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  19. The system for diagnostics and monitoring of the IBR-2 reactor state. Data acquisition, accumulation and storage of information

    International Nuclear Information System (INIS)

    Ermilov, V.G.; Ivanov, V.V.; Korolev, V.S.; Pepelyshev, Yu.N.; Semashko, S.V.; Tulaev, A.B.

    2000-01-01

    The architectural decisions for a developed distributed system of the IBR-2 pulsed reactor conditions monitoring are described. The system is intended for measurement of the basic reactor parameters, acquisition, storage and processing of information, the current reactor state monitoring, analysis of reactor parameters for a long time operation period both in on-line, and in off-line modes. The system is constructed in the architecture client-server using DBMS MS SQL Server 7.0 The basic hardware components of the system are measuring workstations and devices, processing and user workstations and the central server. The software of the system consists of the measuring programs, data flows dispatching services, client applications for data processing and visualization, and means for preparing data for subsequent presentation in WWW. The basic results of the first system operation phase and prospect of its development are discussed. (author)

  20. Analysis of an accelerator-driven subcritical light water reactor

    International Nuclear Information System (INIS)

    Kruijf, W.J.M. de; Wakker, P.H.; Wetering, T.F.H. van de; Verkooijen, A.H.M.

    1997-01-01

    An analysis of the basic characteristics of an accelerator-driven light water reactor has been made. The waste in the nuclear fuel cycle is considerably less than in the light water reactor open fuel cycle. This is mainly caused by the use of equilibrium nuclear fuel in the reactor. The accelerator enables the use of a fuel composition with infinite multiplication factor k ∞ < 1. The main problem of the use of this type of fuel is the strongly peaked flux distribution in the reactor core. A simple analytical model shows that a large core is needed with a high peak power factor in order to generate net electric energy. The fuel in the outer regions of the reactor core is used very poorly. 7 refs., 4 figs., 1 tab

  1. Design study of ship based nuclear power reactor

    International Nuclear Information System (INIS)

    Su'ud, Zaki; Fitriyani, Dian

    2002-01-01

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

  2. Reactor design for nuclear electric propulsion

    International Nuclear Information System (INIS)

    Koenig, D.R.; Ranken, W.A.

    1979-01-01

    Conceptual design studies of a nuclear power plant for electric propulsion of spacecrafts have been on going for several years. An attractive concept which has evolved from these studies and which has been described in previous publications, is a heat-pipe cooled, fast spectrum nuclear reactor that provides 3 MW of thermal energy to out-of-core thermionic converters. The primary motivation for using heat pipes is to provide redundancy in the core cooling system that is not available in gas or liquid-metal cooled reactors. Detailed investigation of the consequences of heat pipe failures has resulted in modifications to the basic reactor design and has led to consideration of an entirely different core design. The new design features an integral laminated core configuration consisting of alternating layers of UO 2 and molybdenum sheets that span the entire diameter of the core. Design characteristics are presented and compared for the two reactors

  3. Remote maintenance for fusion experimental reactor

    International Nuclear Information System (INIS)

    Koizumi, Koichi; Takeda, Nobukazu

    2000-01-01

    Here was introduced on maintenance of reactor core portion operated by remote control among maintenance of the International Thermonuclear Experimental Reactor (ITER) begun on its design since 1988 under international cooperation of U.S.A., Europe, Russia and Japan. Every appliances constructing the reactor core portion is necessary to carry out all of their inspection and maintenance by using remote controlled apparatus because of their radiation due to neutron generated by DT combustion of plasma. For engineering design activity (EDA) in ITER, not only design and development of the remote control appliances but also design under consideration of remote maintenance for from structural design of maintained objective appliances to access method to appliances, transportation and preservation method of radiated matters, and out-reactor maintenance in a hot cell, is now under progress. Here were also reported on basic concept on maintenance and conservation of ITER, maintenance design of diverter and blanket with high maintenance frequency and present state on development of maintenance appliances. (G.K.)

  4. Implementation of a basic principle simulator

    International Nuclear Information System (INIS)

    De Greef, J.F.

    1982-01-01

    During the last twenty years, the Belgian Nuclear Energy Centre (SCK-CEN) gained a lot of experience in mathematical modelling and simulation of nuclear reactor power plant operation. The framework, in which these activities took place, was mainly concerned with security analysis of these devices and with training operation personnel of these plants. In the last years a fourth generation hybrid computer including an AD/FIVE analog computer of Applied Dynamics Inc. (ADI) and a PDP-11/34 digital computer of Digital Equipment Corporation (DEC) were installed. Furthermore, a home made operator's desk simulating the elements of the control room of a nuclear power plant completes the computer system for real-time training purposes. The described equipment is typically that of a Basic Principle Simulator, a device that quickly and effectively imparts the basic concepts of a nuclear power plant operation

  5. Development of source term evaluation method for Korean Next Generation Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Keon Jae; Cheong, Jae Hak; Park, Jin Baek; Kim, Guk Gee [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1997-10-15

    This project had investigate several design features of radioactive waste processing system and method to predict nuclide concentration at primary coolant basic concept of next generation reactor and safety goals at the former phase. In this project several prediction methods of source term are evaluated conglomerately and detailed contents of this project are : model evaluation of nuclide concentration at Reactor Coolant System, evaluation of primary and secondary coolant concentration of reference Nuclear Power Plant(NPP), investigation of prediction parameter of source term evaluation, basic parameter of PWR, operational parameter, respectively, radionuclide removal system and adjustment values of reference NPP, suggestion of source term prediction method of next generation NPP.

  6. Acoustic emission and estimation of flaw significance in reactor pressure boundaries

    International Nuclear Information System (INIS)

    Hutton, P.H.; Kurtz, R.J.

    1982-01-01

    The work discussed is intended to establish the feasibility of using acoustic emission (AE) to detect and evaluate growing flaws in nuclear reactor pressure boundaries. Basic AE identification and interpretation methods have grown out of Phase 1. Phases 2 and 3 to test and demonstrate developed methodology on a vessel test and on a reactor are in progress

  7. Status of national programmes on fast reactors in Korea

    International Nuclear Information System (INIS)

    Kim, Y.I.; Hahn, D.

    2002-01-01

    The role of nuclear power plants in electricity generation in Korea is expected to become more important in the years to come due to poor natural resources and green house gases. This heavy dependence on nuclear power eventually raises the issues of efficient utilization of uranium resources and of spent fuel storage. Fast reactors can resolve these issues. Korea Atomic Energy Research Institute started development of a Liquid Metal Reactor design in 1997 and completed the Conceptual Design in March of 2002. Efforts are currently directed toward the development of advanced fast reactor concepts and basic key technologies. (author)

  8. Computation of nuclear reactor parameters using a stretch Kalman filtering

    International Nuclear Information System (INIS)

    Zwingelstein, G.; Poujol, A.

    1976-01-01

    A method of nonlinear stochastic filtering, the stretched Karman filter, is used for the estimation of two basic parameters involved in the control of nuclear reactor start-up. The corresponding algorithm is stored in a small Multi-8 computer and tested with data recorded for the Ulysse reactor (I.N.S.T.N.). The various practical problems involved in using the algorithm are examined: filtering initialization, influence of the model... The quality and time saving obtained in the computation make it possible for a real time operation, the computer being connected with the reactor [fr

  9. Design characteristics of zero power fast reactor Lasta; Osnovne karakteristike brzog reaktora nulte snage Lasta

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M; Stefanovic, D; Pesic, M; Popovic, D; Nikolic, D; Antic, D; Zavaljevski, N [Institut za nuklearne nauke Boris Kidric, Vinca, Beograd (Yugoslavia)

    1987-07-01

    The concept, purpose and preliminary design of a zero power fast reactor LASTA are described. The methods of computing the reactor core parameters and reactor kinetics are presented with the basic calculated results and analysis for one selected LASTA configuration. The nominal parameters are determined according to the selected reactor safety criteria and results of calculations. Important aspects related to the overall safety are examined in detail. (author)

  10. A report of the Basic Energy Sciences Advisory Committee: 1992 review of the Basic Energy Sciences Program of the Department of Energy

    International Nuclear Information System (INIS)

    1993-09-01

    The general quality of BES research at each of the 4 laboratories is high. Diversity of management at the different laboratories is beneficial as long as the primary BES mission and goals are clearly identified and effectively pursued. External sources of personnel should be encouraged. DOE has been designing a new high flux research reactor, the Advanced Neutron Source, to replace DOE's two aging research reactors; BESAC conducted a panel evaluation of neutron sources for the future. The two new light sources, Advanced Light Source and Advanced Photon source will come on line well before all of their beamline instrumentation can be funded, developed, and installed. Appointment of a permanent director and deputy for OBES would enhance OBES effectiveness in budget planning and intra-DOE program coordination. Some DOE and DP laboratories have substantial infrastructure which match well industry development-applications needs; interlaboratory partnerships in this area are encouraged. Funding for basic science research programs should be maintained at FY1993 levels, adjusted for inflation; OBES plans should be updated and monitored to maintain the balance between basic research and facilities construction and operation. The recommendations are discussed in detail in this document

  11. The Spin Torque Lego - from spin torque nano-devices to advanced computing architectures

    Science.gov (United States)

    Grollier, Julie

    2013-03-01

    Spin transfer torque (STT), predicted in 1996, and first observed around 2000, brought spintronic devices to the realm of active elements. A whole class of new devices, based on the combined effects of STT for writing and Giant Magneto-Resistance or Tunnel Magneto-Resistance for reading has emerged. The second generation of MRAMs, based on spin torque writing : the STT-RAM, is under industrial development and should be out on the market in three years. But spin torque devices are not limited to binary memories. We will rapidly present how the spin torque effect also allows to implement non-linear nano-oscillators, spin-wave emitters, controlled stochastic devices and microwave nano-detectors. What is extremely interesting is that all these functionalities can be obtained using the same materials, the exact same stack, simply by changing the device geometry and its bias conditions. So these different devices can be seen as Lego bricks, each brick with its own functionality. During this talk, I will show how spin torque can be engineered to build new bricks, such as the Spintronic Memristor, an artificial magnetic nano-synapse. I will then give hints on how to assemble these bricks in order to build novel types of computing architectures, with a special focus on neuromorphic circuits. Financial support by the European Research Council Starting Grant NanoBrain (ERC 2010 Stg 259068) is acknowledged.

  12. Progress report 1986-1987 Basic Research Department

    International Nuclear Information System (INIS)

    1988-01-01

    A report is presented of the activities performed by the Basic Research Department of the Bariloche Atomic Center during the period 1986-1987. In this report, works on different subjects related to physics are grouped: atomic collisions, low temperatures, magnetic resonance, metals, neutrons and reactors and theoretical physics (computational, elementary particles, nuclear physics and solid states). In addition, Appendix I and II regarding the staff and visiting scientists, respectively, and publications and conferences are included [es

  13. A Personal Computer-Based Simulator for Nuclear-Heating Reactors

    International Nuclear Information System (INIS)

    Liu Jie; Zhang Zuoyi; Lu Dongsen; Shi Zhengang; Chen Xiaoming; Dong Yujie

    2000-01-01

    A personal computer (PC)-based simulator for nuclear-heating reactors (NHRs), PC-NHR, has been developed to provide an educational tool for understanding the design and operational characteristics of an NHR system. A general description of the reactor system as well as the technical basis for the design and operation of the heating reactor is provided. The basic models and equations for the NHR simulation are then given, which include models of the reactor core, the reactor coolant system, the containment, and the control system. The graphical user interface is described in detail to provide a manual for the user to operate the simulator properly. Steady state and several transients have been simulated. The results of PC-NHR are in good agreement with design data and the results of RETRAN-02. The real-time capability is also confirmed

  14. Basic principles on the safety evaluation of the HTGR hydrogen production system

    International Nuclear Information System (INIS)

    Ohashi, Kazutaka; Nishihara, Tetsuo; Tazawa, Yujiro; Tachibana, Yukio; Kunitomi, Kazuhiko

    2009-03-01

    As HTGR hydrogen production systems, such as HTTR-IS system or GTHTR300C currently being developed by Japan Atomic Energy Agency, consists of nuclear reactor and chemical plant, which are without a precedent in the world, safety design philosophy and regulatory framework should be newly developed. In this report, phenomena to be considered and events to be postulated in the safety evaluation of the HTGR hydrogen production systems were investigated and basic principles to establish acceptance criteria for the explosion and toxic gas release accidents were provided. Especially for the explosion accident, quantitative criteria to the reactor building are proposed with relating sample calculation results. It is necessary to treat abnormal events occurred in the hydrogen production system as an 'external events to the nuclear plant' in order to classify the hydrogen production system as no-nuclear facility' and basic policy to meet such requirement was also provided. (author)

  15. SILOETTE, a training centre for reactor physics at the Nuclear Research Centre of Grenoble

    International Nuclear Information System (INIS)

    Destot, M.

    1983-10-01

    The Reactor Department of Grenoble has created, based on Siloette, an activity of training in reactor physics, wich is running since 1975 to meet the important needs generated by the development of electronuclear power stations. Its essential goal is to provide an initiation to the basic physical phenomena which determine the operation of the reactors. For that purpose, a rather comprehensive program of practical works on reactor (SILOETTE) and on nuclear power station simulators (PWR, UNGG) is proposed besides lectures and conferences, general and specialized teaching on the reactor operation principle, kinetics, dynamics and thermics

  16. Combined Reactor and Microelectrode Measurements in Laboratory Grown Biofilms

    DEFF Research Database (Denmark)

    Larsen, Tove; Harremoës, Poul

    1994-01-01

    A combined biofilm reactor-/microelectrode experimental set-up has been constructed, allowing for simultaneous reactor mass balances and measurements of concentration profiles within the biofilm. The system consists of an annular biofilm reactor equipped with an oxygen microelectrode. Experiments...... were carried out with aerobic glucose and starch degrading biofilms. The well described aerobic glucose degradation biofilm system was used to test the combined reactor set-up. Results predicted from known biofilm kinetics were obtained. In the starch degrading biofilm, basic assumptions were tested...... with the microelectrode measurements. It was established, that even with a high molecular weight, non-diffusible substrate, degradation took place in the depths of the biofilm. Intrinsic enzymatic hydrolysis was not limiting and the volumetric removal rate of oxygen was zero order....

  17. Reactor Engineering Department annual report (April 1, 1996 - March 31, 1997)

    International Nuclear Information System (INIS)

    1997-10-01

    This report summarizes the research and development activities in the Reactor Engineering Department of JAERI during the fiscal year of 1996 (April 1, 1996 - March 31, 1997). The major Department's programs promoted in the year are the design activities of advanced reactor system and the development of a high power proton linear accelerator to construct an intense neutron source for innovative neutron science. Other Major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analysis, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC's fast reactor project were also progressed. The 99 papers are indexed individually. (J.P.N.)

  18. Reactor engineering department annual report. April 1, 1993-March 31, 1994

    International Nuclear Information System (INIS)

    1994-11-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1993 (April 1, 1993-March 31, 1994). The major Department's programs promoted in the year are the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal-hydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the research committees organized by the Department are also summarized in this report. (author)

  19. Reactor Engineering Department annual report (April 1, 1996 - March 31, 1997)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    This report summarizes the research and development activities in the Reactor Engineering Department of JAERI during the fiscal year of 1996 (April 1, 1996 - March 31, 1997). The major Department`s programs promoted in the year are the design activities of advanced reactor system and the development of a high power proton linear accelerator to construct an intense neutron source for innovative neutron science. Other Major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analysis, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC`s fast reactor project were also progressed. The 99 papers are indexed individually. (J.P.N.)

  20. Reactor engineering department annual report. April 1, 1994 - March 31, 1995

    International Nuclear Information System (INIS)

    1995-09-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1994 (April 1, 1994 - March 31, 1995). The major Department's programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal-hydraulic facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

  1. Activity build-up on the circulation loops of boiling water reactors: Basics for modelling of transport and deposition processes

    International Nuclear Information System (INIS)

    Covelli, B.; Alder, H.P.

    1988-03-01

    In the past 20 years the radiation field of nuclear power plant loops outside the core zone was the object of investigations in many countries. In this context test loops were built and basic research done. At our Institute PSI the installation of a LWR-contamination loop is planned for this year. This experimental loop has the purpose to investigate the complex phenomena of activity deposition from the primary fluid of reactor plants and to formulate analytical models. From the literature the following conclusions can be drawn: The principal correlations of the activity build-up outside the core are known. The plant specific single phenomena as corrosion, crud-transport, activation and deposit of cobalt in the oxide layer are complex and only partially understood. The operational experience of particular plants with low contaminated loops (BWR-recirculation loops) show that in principle the problem is manageable. The reduction of the activity build-up in older plants necessitates a combination of measures to modify the crud balance in the primary circuit. In parallel to the experimental work several simulation models in the form of computer programs were developed. These models have the common feature that they are based on mass balances, in which the exchange of materials and the sedimentation processes are described by global empirical transport coefficients. These models yield satisfactory results and allow parameter studies; the application however is restricted to the particular installation. All programs lack models that describe the thermodynamic and hydrodynamic mechanisms on the surface of deposition layers. Analytical investigations on fouling of process equipment led to models that are also applicable to the activity build-up in reactor loops. Therefore it seems appropriate to combine the nuclear simulation models with the fundamental equations for deposition. 10 refs., 18 figs., 3 tabs

  2. Results on safety research for five years (from fiscal year 1996 to 2000). A field of power reactors

    International Nuclear Information System (INIS)

    2001-10-01

    This safety research carried out by the Japan Nuclear Cycle Development Institute (JNC) for five years ranged from 1996 to 2000 fiscal year, was performed according to the safety research basic plan (from 1996 to 2000 fiscal year) established on March, 1996 (revised again on May, 2000). This report was arranged on a field on power reactors (all subjects on fields of advanced conversion reactor and a subject on power reactor in a field of seismic resistant and probability theoretical safety evaluation) by combining its research results for five years ranged from 1996 to 2000 fiscal year with general outlines on the safety research basic plan. Here were shown outlines on the safety research basic plan, aims and subjects on safety research at a field of power reactors, a list of survey sheets on safety research result, and survey sheets on safety research results. The survey sheets containing research field, title, organization, researcher name, researching period, names of cooperative organization, using facilities, research outline, research results, established contents, application, and research trends, are ranged to 5 items on advanced conversion reactor, 29 items on high breeder reactor, 1 item on seismic resistance, and 5 items on probability theoretical safety evaluation. (G.K.)

  3. Starfire: a commercial tokamak reactor

    International Nuclear Information System (INIS)

    Baker, C.C.; Abdou, M.A.; DeFreece, D.A.; Trachsel, C.A.; Graumann, D.; Kokoszenski, J.

    1979-01-01

    The basic objective of the STARFIRE Project is to develop a design concept for a commercial tokamak fusion electric power plant based on the deuterium/tritium/lithium fuel cycle. The key technical objective is to develop the best embodiment of the tokamak as a power reactor consistent with credible engineering solutions to design problems. Another key goal of the project is to give careful attention to the safety and environmental features of a commercial fusion reactor. The STARFIRE Project was initiated in May 1979, with the goal of completing the design study by October 1980. The purpose of this paper is to present an overview of the major parameters and design features that have been tentatively selected for STARFIRE

  4. Regulation for installation and operation of experimental-research reactor

    International Nuclear Information System (INIS)

    1979-01-01

    The ordinance is stipulated under the Law for regulation of nuclear raw materials, nuclear fuel materials and reactors and the provisions for installation and operation of reactor in the order for execution of the law. Basic concepts and terms are defined, such as, radioactive waste; fuel assembly; exposure dose; accumulative dose; controlled area; preserved area; inspected surrounding area and employee. An application for permission of installation of reactor shall list such matters as: the maximum continuous thermal output of reactor; location and general construction of reactor facilities; construction and equipment of the main reactor and other facilities for nuclear fuel materials; cooling and controlling system and radioactive waste, etc. An operation plan of reactor for three years shall be filed till January 31 of the fiscal year preceding that one the operation begins. Records shall be made and kept for specified periods respectively on inspection of reactor facilities, operation, fuel assembly, radiation control, maintenance, accidents of reactor equipment and weather. Detailed rules are settled for entrance limitation to controlled area, exposure dose, inspection, check up and regular independent examination of reactor facilities, operation of reactor, transportation of substances contaminated by nuclear fuel materials within the works and storage, etc. (Okada, K.)

  5. Conceptual design of imploding liner fusion reactors

    International Nuclear Information System (INIS)

    Turchi, P.J.; Robson, A.E.

    1976-01-01

    The basic new ingredient is the concept of rotationally stabilized liquid metal liners accelerated with free pistons. The liner motion is constrained on its outer surface by the pistons, laterally by channel walls, during acceleration, and on its inner surface, where megagauss field levels are attained by the centrifugal motion of the liner material. In this way, stable, reversible motion of the liner should be possible, permitting repetitive, pulsed operation at interior pressures far greater than can be allowed in static conductor systems. Such higher operating pressures permit the use of simple plasma geometries, such as theta pinches, with greatly reduced dimensions. Furthermore, the implosion of thick, lithium-bearing liners with large radial compression ratios inherently provides the plasma with a surrounding blanket of neutron absorbing liquid metal, thereby substantially reducing the problems of induced radioactivity and first wall damage that haunt conventional fusion reactor designs. The following article discusses the basic operation of liner reactors and several important features influencing their design

  6. Country report: utilization of MINT's research reactor

    International Nuclear Information System (INIS)

    Ab Khalic b Hj Wood; Adnan b Bukhari; Wee Boon Siong

    2004-01-01

    MINT has only one research reactor, i.e. TRIGA MKII reactor, equipped with various neutron irradiation facilities such as rotary rack and rabbit system. Apart from counting facilities for NAA work, other facilities available for the respective studies include facilities for neutron radiography and SANS. At Present most of reactor operation time has been utilized for samples irradiation related to the NAA application. Majority of the samples are from MINT analytical chemistry laboratory where the present authors work, and the rest of the samples are from local universities. They provide analytical chemistry services for other government departments as well as private companies. In order to improve the reactor utilization, the management of MINT has formed Reactor Interest Group (RIG) at the national level in 2002, which embraces members from various institutions in this country. To support the RIG activities, MINT provides seed funding to finance various activities for the reactor utilization, which include financing project to make use of SANS, neutron radiography and radioisotopes production (mainly for tracer studies carried out by MINT's tracer group) facilities, and funding for basic study in BNCT. (author)

  7. History, Development and Future of TRIGA Research Reactors. Companion CD-ROM

    International Nuclear Information System (INIS)

    2016-01-01

    Due to its particular fuel design and resulting enhanced inherent safety features, TRIGA reactors (Training, Research, Isotopes, General Atomics) constitute a ‘class of their own’ among the large variety of research reactors built world-wide. This publication summarizes in a single document the information on the past and present of TRIGA research reactors and presents an outlook in view of potential issues to be solved by TRIGA operating organizations in the near future. It covers the historical development and basic TRIGA characteristics, followed by utilization, fuel conversion and ageing management of TRIGA research reactors. It continues with issues and challenges, introduction to the global TRIGA research reactor network and concludes with future perspectives. This CD-ROM illustrates the historical developments of TRIGA research reactors through individual facility examples and experiences

  8. DOE plutonium disposition study: Analysis of existing ABB-CE Light Water Reactors for the disposition of weapons-grade plutonium

    International Nuclear Information System (INIS)

    1994-01-01

    Core reactivity and basic fuel management calculations were conducted on the selected reactors (with emphasis on the System 80 units as being the most desirable choice). Methods used were identical to those reported in the Evolutionary Reactor Report. From these calculations, the basic mission capability was assessed. The selected reactors were studied for modification, such as the addition of control rod nozzles to increase rod worth, and internals and control system modifications that might also be needed. Other system modifications studied included the use of enriched boric acid as soluble poison, and examination of the fuel pool capacities. The basic geometry and mechanical characteristics, materials and fabrication techniques of the fuel assemblies for the selected existing reactors are the same as for System 80+. There will be some differences in plutonium loading, according to the ability of the reactors to load MOX fuel. These differences are not expected to affect licensability or EPA requirements. Therefore, the fuel technology and fuel qualification sections provided in the Evolutionary Reactor Report apply to the existing reactors. An additional factor, in that the existing reactor availability presupposes the use of that reactor for the irradiation of Lead Test Assemblies, is discussed. The reactor operating and facility licenses for the operating plants were reviewed. Licensing strategies for each selected reactor were identified. The spent fuel pool for the selected reactors (Palo Verde) was reviewed for capacity and upgrade requirements. Reactor waste streams were identified and assessed in comparison to uranium fuel operations. Cost assessments and schedules for converting to plutonium disposition were estimated for some of the major modification items. Economic factors (incremental costs associated with using weapons plutonium) were listed and where possible under the scope of work, estimates were made

  9. Nonproliferation and safeguard considerations: Pebble Bed reactor fuel cycle evaluation

    International Nuclear Information System (INIS)

    1978-09-01

    Nuclear fuel cycles were evaluated for the Pebble Bed Gas Cooled Reactor under development in the Federal Republic of Germany. The basic fuel cycle specified for the HTR-K and PNP is well qualified and will meet the requirements of these reactors. Twenty alternate fuel cycles are described, including high-conversion cycles, net-breeding cycles, and proliferation-resistant cycles. High-conversion cycles, which have a high probability of being successfully developed, promise a significant improvement in resource utilization. Proliferation-resistant cycles, also with a high probability of successful development, conpare very favorably with those for other types of reactors. Most of the advanced cycles could be adapted to first-generation pebble bed reactors with no significant modifications

  10. New training reactor at Dresden Technical University

    International Nuclear Information System (INIS)

    Hansen, W.; Knorr, J.; Wolf, T.

    2006-01-01

    A total of 14 low-power (up to 10 W) training reactors have been operated at German universities, 9 of them officially classified as being operational in 2004, though for very different uses. This number is expected to drop sharply. The only comprehensive upgrading of a training reactor took place at Dresden Technical University: AKR-2, the most modern facility in Germany, started routine operation in April 2005, under a newly granted license pursuant to Sec. 7, Subsec. 1 of the German Atomic Energy Act, for training students in nuclear technology, for suitable research projects, and a a center of information about reactor technology and nuclear technology for the interested public. One special aspect of this refurbishment was the installation of digital safety I and C systems of the TELEPERM XS line, which are used also in other modern plants. This fact, plus the easy possibility to use the plant for many basic experiments in reactor physics and radiation protection, make the AKR-2 attractive also to other users (e.g. for training reactor personnel or other persons working in nuclear technology). (orig.)

  11. Studies on reactor physics

    International Nuclear Information System (INIS)

    1960-01-01

    Most of the peaceful applications of atomic energy are inherently dependent on advances in the science and technology of nuclear reactors, and aspects of this development are part of a major programme of the International Atomic Energy Agency. The most useful role that the Agency can play is as a co-ordinating body or central forum where the trends can be reviewed and the results assessed. Some of the basic studies are carried out by members of the Agency's own scientific staff. The Agency also convenes groups of experts from different countries to examine a particular problem in detail and make any necessary recommendations. Some of the important subjects are discussed at international scientific meetings held by the Agency. One of the subjects covered by such studies is the physics of nuclear reactors and a specific topic recently discussed was Codes for Reactor Computations, on which a seminar was held in Vienna in April this year. Another The members of the Panel described the development of heavy water reactors, the equipment and methods of research currently used, and plans for further development in their respective countries meeting of Panel of Experts on Heavy Water Lattices was held in Vienna in August 1959

  12. Fast pyrolysis of sugarcane and cassava residues in a free-fall reactor

    International Nuclear Information System (INIS)

    Pattiya, Adisak; Sukkasi, Sittha; Goodwin, Vituruch

    2012-01-01

    Fast pyrolysis of agricultural residues from sugarcane and cassava plantations was carried out in a laboratory-scale free-fall reactor unit. The objectives of this work were to investigate the effects of biomass types and pyroysis conditions, such as reactor temperature, condensation temperature, nitrogen flow rate and run duration, on pyrolysis product distribution, as well as to study the basic properties of the products. The results showed that all of the parameters affected the product distribution. The optimum reactor temperatures for maximising bio-oil yield were in the range of 350–450 °C. About 70 wt% of bio-oil yield could be obtained by pyrolysis of cassava stalk at a reactor temperature of 450 °C and a primary condensation temperature of 10 °C. It was also found that the minimum flow rate of nitrogen for obtaining high bio-oil yield was 1.5 l/min. The product characterisation showed that the bio-oil and char produced from the agricultural residues with the free-fall reactor unit were to a certain extent similar to those produced from different types of biomass with different types of pyrolysis reactor configurations. -- Highlights: ► Fast pyrolysis of sugarcane and cassava agricultural residues was carried out in a laboratory-scale free-fall reactor unit. ► The effects of process parameters on product yields were investigated. ► The process parameters included reactor temperature, condensation temperature, nitrogen flow rate and run duration. ► Basic properties of pyrolysis products were examined.

  13. Research reactor support

    International Nuclear Information System (INIS)

    2005-01-01

    Research reactors (RRs) have been used in a wide range of applications including nuclear power development, basic physics research, education and training, medical isotope production, geology, industry and other fields. However, many research reactors are fuelled with High Enriched Uranium (HEU), are underutilized and aging, and have significant quantities of spent fuel. HEU inventories (fresh and spent) pose security risks Unavailability of a high-density-reprocessable fuel hinders conversion and limits back-end options and represents a survival dilemma for many RRs. Improvement of interim spent fuel storage is required at some RRs. Many RRs are under-utilized and/or inadequately funded and need to find users for their services, or permanently shut down and eventually decommission. Reluctance to decommission affect both cost and safety (loss of experienced staff ) and many shut down but not decommissioned RR with fresh and/or spent fuel at the sites invoke serious concern. The IAEA's research reactor support helps to ensure that research reactors can be operated efficiently with fuels and targets of lower proliferation and security concern and that operators have appropriate technology and options to manage RR fuel cycle issues, especially on long term interim storage of spent research reactor fuel. Availability of a high-density-reprocessable fuel would expand and improve back end options. The International Atomic Energy Agency provides assistance to Member States to convert research reactors from High Enriched Uranium fuel and targets (for medical isotope production) to qualified Low Enriched Uranium fuel and targets while maintaining reactor performance levels. The assistance includes provision of handbooks and training in the performance of core conversion studies, advice for the procurement of LEU fuel, and expert services for LEU fuel acceptance. The IAEA further provides technical and administrative support for countries considering repatriation of its

  14. Feasibility review for the fabrication aspects of SMART reactor vessel assembly

    International Nuclear Information System (INIS)

    Kim, K. S.; Choi, S.; Kim, T. W.; Jeong, K. H.; Lee, G. M.; Park, K. B.; Chang, M. H.

    1999-06-01

    In this report, the design functions and requirements for the major components of 330 MWt integral reactor, SMART (System-integrated Modular Advanced ReacTor), are described. The feasibility of major components, the assemblage sequence, and the anticipated difficulties during manufacturing and assemblage are discussed. Also developed are the maintenance and replacement strategy. In addition, the material requirements, welding requirements, the concerns of casting and forging, and the feasibility of procurement of items which are not easily available domestically are reviewed. The contents of this report will be reflected throughout the basic design stage of the SMART, and is expected to serve as the basic reference for the SMART prototype fabrication. (author). 61 figs

  15. Conceptual design for simulator of irradiation test reactors

    International Nuclear Information System (INIS)

    Takemoto, Noriyuki; Ohto, Tsutomu; Magome, Hirokatsu; Izumo, Hironobu; Hori, Naohiko

    2012-03-01

    A simulator of irradiation test reactors has been developed since JFY 2010 for understanding reactor behavior and for upskilling in order to utilize a nuclear human resource development (HRD) and to promote partnership with developing countries which have a plan to introduce nuclear power plant. The simulator is designed based on the JMTR, one of the irradiation test reactors, and it simulates operation, irradiation tests and various kinds of accidents caused by the reactor and irradiation facility. The development of the simulator is sponsored by the Japanese government as one of the specialized projects of advanced research infrastructure in order to promote basic as well as applied researches. The training using the simulator will be started for the nuclear HRD from JFY 2012. This report summarizes the result of the conceptual design of the simulator in JFY 2010. (author)

  16. Course of operators of the RA-3 reactor

    International Nuclear Information System (INIS)

    Caligiuri, G.A.

    1983-01-01

    Description of the fundamental principles of the nuclear reactors' control systems. The RA-3 reactor's control and measurement systems are principally described, without setting aside the basic criteria for the design of an appropriate instrumentation for the control of a nuclear reactor, as well as the theory on which the functioning of the several detectors and equipments used in a nuclear instrumentation are based. The main purpose of this course is that of serving, preferentially as a text, for the training of personnel which shall perform operation tasks in this reactor. The work includes three well-defined sections. The first two ones make an introduction to the subject, while the third one, extending to more than half-work, deals with the general description of the system in which the control and operation logic of RA-3 are included. (R.J.S) [es

  17. Cavity temperature and flow characteristics in a gas-core test reactor

    Science.gov (United States)

    Putre, H. A.

    1973-01-01

    A test reactor concept for conducting basic studies on a fissioning uranium plasma and for testing various gas-core reactor concepts is analyzed. The test reactor consists of a conventional fuel-element region surrounding a 61-cm-(2-ft-) diameter cavity region which contains the plasma experiment. The fuel elements provide the neutron flux for the cavity region. The design operating conditions include 60-MW reactor power, 2.7-MW cavity power, 200-atm cavity pressure, and an average uranium plasma temperature of 15,000 K. The analytical results are given for cavity radiant heat transfer, hydrogen transpiration cooling, and uranium wire or powder injection.

  18. Preliminary assessment of an S.G.H.W. type research reactor

    International Nuclear Information System (INIS)

    Bicevskis, A.; Chapman, A.G.; Hesse, E.W.

    1970-08-01

    A preliminary design study has been made of a research reactor, based on the enriched S.G.H.W.R. concept, to be used for power reactor fuel irradiation, isotope production, basic research, and training in nuclear technology. A reactor physics assessment established a core size which would allow uninterrupted operation for the required irradiation period consistent with low capital and operating costs. A design was selected with 24 channels, a D 2 O calandria diameter of 2.7 m and an overall core height of 4.0 m. The capital cost was estimated as $750,000 for the fuel and $1,600,000 for the moderator, the refuelling cost being $340,000 per annum. A thermal design study showed that the fission heat of 65 MW could be transmitted to pressurised light water at 200 lb/in 2 abs. and rejected to sea water in two conventional U-tube heat exchangers. The basic design is flexible and can be adapted to meet many special requirements. (author)

  19. The brief introduction to decommissioning of nuclear reactor projects

    International Nuclear Information System (INIS)

    Zhao Shixin

    1991-01-01

    The basic concept and procedure of the decommissioning of nuclear reactor project and the three stages of decommissioning defined by IAEA are introduced. The main work of decommissioning of nuclear reactor are as following: (1) the documentary and technological preparation; (2) the site preparation of decommissioning project; (3) the dismantling of equipment piping system and components; (4) the decontamination of the piping system before and after decomminssioning; (5) the storage and disposal of the operational and decommissioning waste

  20. The brief introduction to decommissioning of nuclear reactor projects

    Energy Technology Data Exchange (ETDEWEB)

    Shixin, Zhao [Beijing Inst. of Nuclear Engineering (China)

    1991-08-01

    The basic concept and procedure of the decommissioning of nuclear reactor project and the three stages of decommissioning defined by IAEA are introduced. The main work of decommissioning of nuclear reactor are as following: (1) the documentary and technological preparation; (2) the site preparation of decommissioning project; (3) the dismantling of equipment piping system and components; (4) the decontamination of the piping system before and after decomminssioning; (5) the storage and disposal of the operational and decommissioning waste.