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Sample records for joseph m. farley-2 reactor

  1. A Tribute to Joseph M. Lookofsky

    DEFF Research Database (Denmark)

    of Law, 1971). He became a member of the New York State Bar and started his professional career as an attorney for the United Artists Corporation, specializing in contract law and copyright law. In 1973 he married a Danish woman, Vibeke, and moved to Denmark. He then took a Danish law degree (cand......This book is a tribute to Professor Joseph M. Lookofsky, honoring his work as an internationally respected scholar within the areas of private law, comparative law and private international law. It contains contributions from a wide range of respected scholars and colleagues from around the globe...... on topics like the United Nations Convention on the International Sale of Goods (the CISG), Arbitration and Private International Law. Joseph M. Lookofsky was born in in 1945 in New York, USA, where he studied economics (B.A. Economics, Lehigh University, 1967) and law (J.D., New York University School...

  2. JOSEPH M. JURAN - Human personality and his creation

    OpenAIRE

    Stefan Ragalie

    2004-01-01

    It is well-known the idea that the social welfare level of the nation, more precisely the daily quality life level of the country depend on the quality of goods and services realized and exported by its citizens. In this context, the concepts and principles introduced by Joseph M. Juran in the economic thinking and known as Juran Trilogy (this trilogy puts together the three major activities: the planning, control and improving of the quality) become important for the Romanian firms and offer...

  3. Joseph M. Nyasani It is not only astronomers who have been ...

    African Journals Online (AJOL)

    THE UBICATION OF THE PHYSICAL UNIVERSE. Joseph M. Nyasani. It is not only astronomers who have been wondering about what lies beyond the planetary system and the extent of that reality in terms of the space it occupies. Philosophers have equally been baffled by this same question even though it may not be fair ...

  4. Aerial radiological survey of the Joseph M. Farley Nuclear Plant and surrounding area, Dothan, Alabama

    International Nuclear Information System (INIS)

    Maguire, T.C.; Shipman, G.R.

    1982-03-01

    An aerial radiological survey was performed during the period 8 to 19 December 1979 over a 2000 square kilometer area centered on the two unit Joseph M. Farley Nuclear Plant near Dothan, Alabama. Radiological data were collected by flying north-south lines spaced 900 meters apart at an altitude of 150 meters above ground level. Processed data showed that all gamma rays detected within the survey area were those expected from naturally occurring radionuclides. Count rates obtained from the aerial platform were converted to exposure rates at 1 meter above the ground and are presented in the form of a radiation contour map. The observed exposure rates were between 4 and 12 microroentgens per hour (μR/h), with most of the area ranging between 4 and 10 μR/h. These values include an estimated cosmic ray contribution of 4.0 μR/h but do not include any contribution from airborne radionuclides, i.e., radon. Exposure rates obtained from ground measurements taken within the survey area were in close agreement with the aerial data. The data were also in close agreement with those obtained from a similar survey conducted during March 1977. Comparison of the results from both surveys indicated that no detectable change in the radiological characteristics of the survey area has occurred due to the operation of unit number 1 during the intervening period. The same equipment and procedures were utilized for both surveys

  5. 99mTc-DMSA Uptake in a Sister Mary Joseph's Nodule From Ovarian Cancer.

    Science.gov (United States)

    Naddaf, Sleiman; Azzumeea, Fahad; Fahad Alzayed, Mohammed

    2016-12-01

    A 50-year-old woman with ovarian cancer underwent Tc-DMSA scan to evaluate the functional status of the right hydronephrotic kidney. The images incidentally revealed a well-defined focus of mild radiotracer uptake at the midanterior abdominal wall, which correlated with a metastatic Sister Mary Joseph's nodule seen on CT performed a week earlier.

  6. USA saadik loodab võita eestlaste poolehoiu / Joseph M. DeThomas

    Index Scriptorium Estoniae

    DeThomas, Joseph M.

    2003-01-01

    USA suursaadik Eestis Joseph DeThomas vastab on-line intervjuus Eesti Päevalehe lugejate küsimustele Iraagi ründamise, USA ja Euroopa vahelise lõhe, USA Eesti saatkonna võimaliku ümberkolimise kohta

  7. Conformance to Regulatory Guide 1.97, Joseph M. Farley Nuclear Plant, Unit Nos. 1 and 2 (Docket No. 50-348 and 50-364)

    International Nuclear Information System (INIS)

    Stoffel, J.W.

    1985-05-01

    This EG and G Idaho, Inc., report reviews the submittals for Regulatory Guide 1.97 for Unit Nos. 1 and 2 of the Joseph M. Farley Nuclear Plant and identifies areas of nonconformance to the regulatory guide. Exceptions to Regulatory Guide 1.97 are evaluated and those areas where sufficient basis for acceptability is not provided are identified

  8. Machado-Joseph Disease

    Science.gov (United States)

    ... Caregiver Education » Fact Sheets Machado-Joseph Disease Fact Sheet What is Machado-Joseph disease? What are the ... the repeat is in a protein-producing or coding region of the gene. Modifications of the mutant ...

  9. Jean Baptiste Joseph Fourier

    Science.gov (United States)

    Sterken, C.

    2003-03-01

    This paper gives a short account of some key elements in the life of Jean Baptiste Joseph Fourier (1768-1830), specifically his relation to Napoleon Bonaparte. The mathematical approach to Fourier series and the original scepticism by French mathematicians are briefly illustrated.

  10. La música de Franz Joseph Haydn en España: recopilación, catalogación e interpretación de las fuentes musicales conservadas en Madrid hasta 1833

    OpenAIRE

    Montero García, María del Rosario

    2013-01-01

    La música de Franz Joseph Haydn (1732-1809) fue adquirida e interpretada en España durante su vida. Prueba de esto es la existencia de un abundante número de impresos y copias manuscritas de obras musicales suyas dispersas por toda la geografía española, así como las frecuentes alusiones al compositor austriaco en fuentes españolas hemerográficas, teóricas, literarias y epistolares. Dichas fuentes muestran que la música de Haydn gozó de gran prestigio, incluso años después de su muerte, reper...

  11. Joseph Mountin Lecture

    Centers for Disease Control (CDC) Podcasts

    2009-10-26

    In this podcast, William H. Foege, MD, MPH delivers the 29th Annual Joseph W. Mountin Lecture. Dr. Foege was a key leader in the smallpox effort and worked as an epidemiologist in the successful eradication campaign in the 1970s. Dr. Foege became chief of the Smallpox Eradication Program at CDC, and was appointed director of CDC in 1977.  Created: 10/26/2009 by Centers for Disease Control and Prevention (CDC).   Date Released: 10/29/2009.

  12. Interview: Joseph Agassi

    Directory of Open Access Journals (Sweden)

    Joseph Agassi

    2016-12-01

    Full Text Available Joseph Agassi is an Israeli scholar born in Jerusalem on May 7, 1927. He has many books and articles published contributing to the fields of logic, scientific method, foundations of sciences, epistemology and, most importantly for this Journal, in the historiography of science. He studied with Karl Popper, who was definitely his biggest influence. He taught around the world in different universities. He currently lives in Herzliya, Israel. For his important contribution to the historiography of science, we chose to open the first issue of this journal with this interview recognizing his importance for the field, as well as paying our homage to him.

  13. Recepción histórica de la música eclesiástica de Joseph Haydn en los archivos musicales catedralicios de la Comunidad Valenciana

    Directory of Open Access Journals (Sweden)

    Aparisi Aparisi, José

    2008-12-01

    Full Text Available As far as I know, no research has been done so far on the reception of Joseph Haydn’s music, particularly that concerning the liturgical repertoire, in Latin, in the main centres of production of church music in the Valencian Community. The first source with music by Haydn, dated in Valencia in 1789, when the musician’s composing activity was at its best —the organ part of the “Grosse Orgelsolomesse” (“Great Organ Solo Mass”—, appears in Valencia only three years after he composed Die sieben letzten Worte unseres Erlösers am Kreuze (“The Seven Last Words of our Saviour on the Cross” commissioned to Haydn by the Hermandad of the Santa Cueva in Cadiz. On the other hand, the number of compositions wrongly attributed to Joseph Haydn is, in all probability, much higher when it comes to church music than any other genre, which offers a wide and interesting fi eld to study.

    Hasta donde conozco, no se ha realizado hasta la fecha un estudio sobre la recepción de la música, particularmente en lo referido al repertorio litúrgico —en latín— de Joseph Haydn, en los principales centros de producción musical eclesiástica de la Comunidad Valenciana. La primera fuente con música de Haydn datada en Valencia, en 1789, en plena actividad compositiva del músico de Rohrau —la parte para el órgano de la “Grosse Orgelsolomesse” (“Gran Misa para solo de órgano”—, aparece en Valencia sólo tres años después de la composición de Die sieben letzten Worte unseres Erlösers am Kreuze (“Las Siete últimas Palabras de Nuestro Salvador en la Cruz”, fruto del encargo que hiciera la Hermandad de la Santa Cueva de Cádiz al compositor. Por lo demás, el número de atribuciones de composiciones, equivocadamente adjudicadas a Joseph Haydn es, seguramente en el campo de la música de iglesia, mucho mayor que en otros géneros, lo que ofrece un amplio e interesante campo sobre el cual poder

  14. Dual pressurized light water reactor producing 2000 M We

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-10-15

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

  15. Joseph Hooker: a philosophical botanist

    Indian Academy of Sciences (India)

    2008-04-24

    Apr 24, 2008 ... The nineteenth-century British botanist, Joseph Dalton Hooker, was one of the people whose career became a model for that of the modern, professional scientist. However, he preferred to refer to himself as a philosophical botanist, rather than a professional. This paper explores the reasons for this choice, ...

  16. Where was Joseph Babinski born?

    Directory of Open Access Journals (Sweden)

    H A G Teive

    2011-01-01

    Full Text Available There is controversy in the neurological literature about where Joseph Babinski was born, including a myth propounded by various important authors that he was born in Lima, Peru. However, according to the most consistent biographical data, he was in fact born in Paris, France, and became a medical celebrity there and in Poland as well as around the world.

  17. story from the joseph narrative

    African Journals Online (AJOL)

    The story of Judah within the longer Joseph story (Genesis 37-50) provides an apt place for .... from the center, to honor all humans with absolute justice, equity, respect; to refrain ..... they were simply general behavior types with no relation to me (too abstract) ... the Bible and extract theology and then replicate it into theory.

  18. UWTOR-M, a stellarator power reactor utilizing modular coils

    International Nuclear Information System (INIS)

    Sviatoslavsky, I.N.; Van Sciver, S.W.; Kulcinski, G.L.

    1981-10-01

    We briefly describe the parametric considerations which led to the UWTOR-M reference design point. The design has 18 twisted coils utilizing a multipolarity of 3, a major radius of 24 m, a coil radius of 4.77 m and a plasma aspect ratio of 14. An assumed β of 5% was used. This configuration leads to a rotational transform on the edge of 1.125 giving favorable plasma physics conditions. The natural stellarator divertor is used for impurity control in conjunction with innovative high performance divertor targets. A unique blanket design is proposed which minimizes tritium inventory in the reactor. Finally, since maintainability is a prime consideration, we describe a scheme for servicing the first wall/blanket and other reactor components

  19. Polarization of fast neutrons in VVR-M reactor

    International Nuclear Information System (INIS)

    Garusov, E.A.; Lifshits, E.P.; Petrov, Yu.V.

    1987-01-01

    Neutron polarization in the reactor leads to circular polarization of γ quanta emitted both in radiational capture of neutrons and in the transition of nuclei excited as a result of inelastic scattering to the ground state. This may be used to determine the polarization of reactor neutrons. The circular polarization of γ quanta at light-water and graphite targets at the center of the active zone of the VVR-M reactor at the B.P. Konstantinov Leningrad Institute of Nuclear Physics was recently measured. A simplified experimental scheme is shown. Fast neutrons leaving the active zone of the reactor were excited in the inelastic scattering at the target nuclei. The polarization of the γ quanta emitted by nuclei in transitions to the ground state was measured by a polarimeter positioned above the active zone. The reason for the circular polarization of γ quanta may also be nonconservation of P parity on account of weak interaction in the capture of a neutron by hydrogen

  20. Joseph Conrad's Lord Jim: Reconsiderations

    Directory of Open Access Journals (Sweden)

    Ali Albashir Mohammed Al-Haj

    2014-12-01

    Full Text Available The present study aims at reconsidering critically Joseph Conrad's Lord Jim. Joseph Conrad is a great master of English prose who writes normally of the sea, of the Eastern islands, of the English character as seen against a background of the exotic or faced with difficulties. The power of Conrad's feelings for Jim, as well as the force of his judgment  against him, are the responses  of a man mightily involved on two planes, one personal and one public , with the dynamics of good and evil. The evil in Lord Jim is one thing on the surface and another beneath our grasp. It is of course the evil of men who have no sense of loyalty to anything.

  1. Thai Research Reactor (TRR-1/M1) Neutron Beam Measurements

    International Nuclear Information System (INIS)

    Ratanatongchai, Wichian

    2009-07-01

    Full text: Neutron beam tube of neutron radiography facility at Thai Research Reactor (TRR-1/M1) Thailand Institute of Nuclear Technology (public organization) is a divergent beam. The rectangular open-end of the beam tube is 16 cm x 17 cm while the inner-end is closed to the reactor core. The neutron beam size was measured using 20 cm x 40 cm neutron imaging plate. The measurement at the position 100 cm from the end of the collimator has shown that the beam size was 18.2 cm x 19.0 cm. Gamma ray in neutron the beam was also measured by the identical position using industrial X ray film. The area of gamma ray was 27.8 cm x 31.1 cm with the highest intensity found to be along the neutron beam circumference

  2. A Tribute to Joseph M. Lookofsky

    DEFF Research Database (Denmark)

    of Law, 1971). He became a member of the New York State Bar and started his professional career as an attorney for the United Artists Corporation, specializing in contract law and copyright law. In 1973 he married a Danish woman, Vibeke, and moved to Denmark. He then took a Danish law degree (cand......) and The United Nations Model Law on Arbitration (MAL). He is the General Secretary for the Danish Committee on Comparative Law, Titular Member of the International Academy of Comparative Law (Académie Internationale de Droit Comparé) and has been a visiting professor or lecturer at, among others, Duke University...

  3. Substantiation of the TVR-M reactor parameter selection and specific features of the research program

    International Nuclear Information System (INIS)

    Abov, Yu.G.; Kiselev, G.V.; Shvedov, O.V.

    1986-01-01

    Comparative analysis of characteristics of the T-VR-M(ITEP, USSR), GRHF(France) and PIK(LNPI USSR) high-flux heavy water cooled and moderated research reactors is given. The TVR-M reactor design concepts are mainly based on a 35-year experience in operating of the first Soviet heavy water research TVR reactor. As a result of the reactor reconstruction its thermal power will increase up to 25 MW neutron flux in experimental channels will increase 10 fold and reach 5.6x10 14 neutron/cm 2 xc. The TVR-M reactor has the quality value the ratio of maximum thermal neutron flux value the reflector to reactor power in practically the same as for the GRHF reactor (2.24x10 13 (neutron/cm 2 xc)/MW) which allows one to place it among the best research reactors in the world. Maximum fuel burnup of the order of 50% and minimum fuel loading are forseen for the TVR-M reactor which provides for operation cost minimum as compared to the GRHF and PIK reactors. The TVR-M reactor practically does not yield to the PIK and GRMF reactors in experimental channel quantity and exceeds the in the number of vertical channels. The TVR-M reactor experimental capabilities allow one to reduce measuring time and provide for conducting the experiments at a qualitatively new level. At the same time capabilities of radioactive nuclide production in qualitative and quantitative senses are increased

  4. Design of first reactor protection system prototype for C A R E M reactor

    International Nuclear Information System (INIS)

    Azcona, A; Lorenzo, G.; Maciel, F.; Fittipaldi, A

    2006-01-01

    In this paper we present the design of a prototype of the C A R E M Reactor Protection System, which is implemented on a basis of the digital platform T E L E P E R M X S.The proposed architecture for the Reactor Protection System (R P S) has 4 redundant trains composed by a complete set of sensors, a data acquisition computer and a processing computer.The information from the 4 processing computers goes into to a two voting units with a two out of four (2004) logic and its outputs are combined by a final actuation logic with a voting scheme of one out of two (1002).The prototype is implemented with a unique train.The train inputs are simulated by an Automatic Testing Unit.The pre-established test case or procedure results are fed back into the A T U.The choice of the digital platform T E L E P E R M X S for the R P S implementation allows versatility in the design stage and permits the prototype expansion due to its modular characteristic and the software tools flexibility [es

  5. Astronaut Joseph Kerwin takes blood sample from Astronaut Charles Conrad

    Science.gov (United States)

    1973-01-01

    Scientist-Astronaut Joseph P. Kerwin (right), Skylab 2 science pilot and a doctor of medicine, takes a blood sample from Astronaut Charles Conrad Jr., Sylab 2 commander, as seen in this reproduction taken from a color television transmission made by a TV camera aboard the Skylab 1 and 2 space station cluster in Earth orbit. The blood sampling was part of the Skylab Hematology and Immunology Experiment M110 series.

  6. Remembering Joseph Mayo and His Contributions to Animal Science | Poster

    Science.gov (United States)

    By Carolynne Keenan, Guest Writer In the 1990s, when Joseph Mayo, D.V.M, ran out of gas leading coworkers home from a meeting in Bethesda, he pulled over to the side of the road on I-270 and waited for help. He didn’t have to wait long; within a few minutes a passing motorist took pity on the group of scientists and offered them a lift back to Fort Detrick.

  7. 75 FR 15430 - Chief Joseph Hatchery Program

    Science.gov (United States)

    2010-03-29

    ... production program and hatchery facilities. The National Oceanic and Atmospheric Administration's National... DEPARTMENT OF ENERGY Bonneville Power Administration Chief Joseph Hatchery Program AGENCY: Bonneville Power Administration (BPA), Department of Energy (DOE). ACTION: Notice of availability of Record...

  8. Joseph Conrad's tormented Rescue (fantasy).

    Science.gov (United States)

    Freedman, William

    2014-02-01

    Joseph Conrad was a notoriously tormented writer for whom the creative act was often a punishment severe enough to drive him into paralyzing depressions that delayed the completion of his novels, sometimes for years. By far the most agonizing of these projects was The Rescue, a novel he began in 1898, abandoned a year later, tried unsuccessfully to continue several times over the next two decades, but was only able to resume in 1918 and to complete, after another tortured two-year struggle, in 1920. An explanation for this incapacity, that is powerfully suggested by the novel's evocative title and perhaps unintentionally ironic subtitle (A Romance of the Shallows) has not yet been explored. Using Freud's 1910 essay on the rescue fantasy, "Contributions to the Psychology of Love: A Special Type of Choice of Object Made by Men," and Emanuel Berman's instructive revision and expansion of the concept in his 2003 American Imago essay, "Ferenczi, Rescue, and Utopia," I argue that a substantial explanation for Conrad's tormented history with The Rescue is ascribable to its quite remarkably faithful treatment of a rescue fantasy with deep and disabling resonance for its author. More specifically, the difficulty was compounded by the novel's dramatization of the soul-crushing conflict between two such fantasies: one in the service of the masculine ideal of unflinching dedication to a heroic purpose, the other promising satisfaction to the equally potent demands of emotional and sexual desire. Features of Conrad's narrative fit so tightly and consistently with the theory as Freud (and Abraham) proposed and as Berman elaborated it that The Rescue offers itself as one of those rare and reinforcing instances wherein the literary text seems to validate the psychoanalytic theory at least as persuasively as the theory "understands" the text.

  9. Comparison of thermal capabilities of the fuel assemblies for the WWR-M reactor

    International Nuclear Information System (INIS)

    Kirsanov, G.A.; Konoplev, K.A.; Findeisen, A.; Shishkina, Zh.A.

    1989-01-01

    On the basis of measurement results of the WWR-M2, WWR-M3 and WWR-M5 fuel element can temperature in the WWR-M reactor core their thermal capabilities are compared. The use of the WWR-M5 fuel assemblies instead of the WWR-M2 ones in the WWR-M reactor permits to increase specific heat loading by a factor of 2.7. The possibility to increase fuel can temperature up to 110 deg C is confirmed experimentally which corresponds to specific heat loading of 900 kW/l

  10. Joseph Dzhugashvili (Stalin and the Terror

    Directory of Open Access Journals (Sweden)

    Teimuraz Vakhtangishvili

    2014-08-01

    Full Text Available Joseph Vissarionovich Dzhugashvili (Stalin was born in Georgia, where he spent the significant part of his life. Materials and documents, preserved in the funds of the Central Historic Archive of Georgia and in the Archive of the Ministry of Internal Affairs of Georgia, which haven’t been published yet, present a new view of Joseph Dzhugashvili’s (Stalin revolutionary activities during the revolution of 1905-1907. The mentioned documents state the fact that the Bolsheviks and the Mensheviks made active use of terrorist methods and acts against tsar’s government. Besides, the archive materials, we have obtained, state that young Joseph Dzhugashvili (Stalin while residing in Georgia was involved in the organization of military struggle and terrorist acts against government by the socially-democratic party of the Bolsheviks.

  11. Production of Sn-117m in the BR2 high-flux reactor.

    Science.gov (United States)

    Ponsard, B; Srivastava, S C; Mausner, L F; Russ Knapp, F F; Garland, M A; Mirzadeh, S

    2009-01-01

    The BR2 reactor is a 100MW(th) high-flux 'materials testing reactor', which produces a wide range of radioisotopes for various applications in nuclear medicine and industry. Tin-117m ((117m)Sn), a promising radionuclide for therapeutic applications, and its production have been validated in the BR2 reactor. In contrast to therapeutic beta emitters, (117m)Sn decays via isomeric transition with the emission of monoenergetic conversion electrons which are effective for metastatic bone pain palliation and radiosynovectomy with lesser damage to the bone marrow and the healthy tissues. Furthermore, the emitted gamma photons are ideal for imaging and dosimetry.

  12. Estimation of reactor pool water temperature after shutdown in JRR-3M

    International Nuclear Information System (INIS)

    Yagi, Masahiro; Sato, Mitsugu; Kakefuda, Kazuhiro

    1999-01-01

    The reactor pool water temperature increasing by the decay heat was estimated by calculation. The reactor pool water temperature was calculated by increased enthalpy that was estimated by the reactor decay heat, the heat released from the reactor biological shielding concrete, reactor pool water surface, the heat conduction from the canal and the core inlet piping. These results of calculation were compared with the past measured data. As the results of estimation, after the JRR-3M shutdown, the calculated reactor pool temperature first increased sharply. This is because the decay heat was the major contribution. And then, rate of increased reactor pool temperature decreased. This is because the ratio of heat released from reactor biological shielding concrete and core inlet piping to the decay heat increased. Besides, the calculated reactor pool water temperature agreed with the past measured data in consequence of correcting the decay heat and the released heat. The corrected coefficient k 1 of decay heat was 0.74 - 0.80. And the corrected coefficient k 2 of heat released from the reactor biological shielding concrete was 3.5 - 4.5. (author)

  13. WWR-M reactor fuel elements as objects of permanent study and modernization

    International Nuclear Information System (INIS)

    Kirsanov, G.A.; Konoplev, K.A.; Poltavski, A.S.; Zakharov, A.S.

    2005-01-01

    Brief description of WWR-M5 thin-walled fuel elements and review of possible improvement of parameters for reactor type WWR-M and WWR-SM during transition from fuel elements HEU and LEU WWR-M2 to LEU WWR-M5 is presented. (author)

  14. Obituary: Richard Joseph Elston, 1960-2004

    Science.gov (United States)

    Jannuzi, Buell Tomasson; Bechtold, Jill

    2004-12-01

    Richard Joseph Elston, known for his development of innovative astronomical instrumentation, died on 26 January 2004 in Gainesville, Florida, after a four-year battle with Hodgkin's lymphoma. A professor of astronomy at the University of Florida, Richard had an unusually broad range of interests and skills, and a willingness to share his passion for astronomy with others, which made him a highly valued member of the astronomical community. Born 1 July 1960, in Albuquerque, New Mexico, Richard was the son of a geologist father and journalist mother. His childhood interest in astronomy and instrumentation matured as he majored in physics and astronomy at the University of New Mexico (BS, 1983) under the mentorship of Michael Zeilik. Richard pursued his PhD in astronomy at the University of Arizona and earned his degree in 1988. He pioneered the use of IR arrays for deep imaging surveys of the sky to study galaxy formation, and completed his thesis Search for Rapidly Forming Galaxies at High Redshift under the direction of George Rieke. Richard's graduate work included the first detection of galaxies at intermediate redshifts with evolved populations too red to have been identifiable from optical imaging surveys alone. In the Astrophysical Journal Letters in 1988, he, George Rieke, and Marcia Rieke reported the discovery of this new class of galaxies, now known as EROs (Extremely Red Objects), important as the possible progenitors of present day elliptical galaxies. Following post-doctoral positions at Kitt Peak National Observatory from 1988 to 1991 and at the Observatories of the Carnegie Institution of Washington from 1991 to 1992, Richard joined the scientific staff of Cerro Tololo Inter-American Observatory in Chile, part of the NSF's National Optical Astronomy Observatory. By 1994, he had become head of CTIO's IR instrumentation program and was leading the development of new instruments for the US astronomical community. In 1996, Richard married astronomer

  15. Current status of the Thai Research Reactor (TRR-1/M1)

    International Nuclear Information System (INIS)

    Chueinta, Siripone; Julanan, Mongkol; Charncanchee, Decharchai

    2006-01-01

    The first Thai Research Reactor, TRR-1 went critical on 27 October 1962 at the maximum power of 1 MW. It was located at Office of Atoms for Peace (OAP) in Bangkok. Since then, TRR-1 was continuously operated and eventually shut down in 1975. Plate type, high-enriched uranium (HEU) and U 3 O 8 A1 cladding were used as the reactor fuel. Light water was used as moderator and coolant as well. In 1975, because of the problem from fuel supplier and also to supporting the Treaty of Non Proliferation of Nuclear Weapon or NPT, TRR-1 was shut down for modification. The reactor core and control system were disassembled and replaced by TRIGA Mark III. A new core was a hexagonal core shape designed by General Atomics (GA). Afterwards, TRR-1 was officially renamed to the Thai Research Reactor-1/Modification 1 (TRR-1/M1). TRR-1/M1 is a multipurpose swimming pool type reactor with nominal power of 2 MW. The TRR-1/M1 uses uranium enriched at 20% in U-235 (LEU) and ZrH alloy as fuel. Light water is also used as coolant and moderator. At present, the reactor is operating with core No.14. The reactor has been serving for various kinds of utilization namely, radioisotope production, neutron activation analysis, beam experiments and reactor physics experiments. (author)

  16. TEMP-M program for thermal-hydraulic calculation of fast reactor fuel assemblies

    International Nuclear Information System (INIS)

    Bogoslovskaya, C.P.; Sorokin, A.P.; Tikhomirov, B.B.; Titov, P.A.; Ushakov, P.A.

    1983-01-01

    TEMP-M program (Fortran, BESM-6 computer) for thermal-hydraulic calculation of fast reactor fuel assemblies is described. Results of calculation of temperature field in a 127 fuel element assembly of BN-600, reactor accomplished according to TEMP-N program are considered as an example. Algorithm, realized in the program, enables to calculate the distributions of coolant heating, fuel element temperature (over perimeter and length) and assembly shell temperature. The distribution of coolant heating in assembly channels is determined from a solution of the balance equation system which accounts for interchannel exchange, nonadiabatic conditions on the assembly shell. The TEMP-M program gives necessary information for calculation of strength, seviceability of fast reactor core elements, serves an effective instrument for calculations when projecting reactor cores and analyzing thermal-hydraulic characteristics of operating reactor fuel assemblies

  17. Estimation of power feedback parameters of pulse reactor IBR-2M on transients

    International Nuclear Information System (INIS)

    Pepyolyshev, Yu.N.; Popov, A.K.

    2013-01-01

    Parameters of the IBR-2M reactor power feedback (PFB) on a model of the reactor dynamics by mathematical treatment of two registered transients are estimated. Frequency characteristics and the pulse transient characteristics corresponding to these PFB parameters are calculated. PFB parameters received thus can be considered as their express tentative estimation as real measurements in this case occupy no more than 30 minutes. Total PFB is negative at 1 and 2 MW. At the received estimations of PFB parameters in a self-regulation mode it is possible to consider the stability margins of the IBR-2M reactor satisfactory

  18. Verlossing: van Pelagius tot Joseph Smith

    Directory of Open Access Journals (Sweden)

    H.F. van Wyk

    2010-07-01

      During this time Joseph Smith started to seek the true church and founded the Mormon Church. Although his theology differs quite strongly from the Methodist Church in which he grew up, the core of the way of salvation is the same: man has free will in choosing his salvation.

  19. The great neurosis of Dr. Joseph Gerard.

    Science.gov (United States)

    Lefrère, Jean-Jacques; Rouillon, Frédéric

    2013-01-01

    The Great Neurosis, of Dr. Joseph Gerard, was published in 1889 in Paris. The book, intended for the general public, shows the different varieties of neuroses through picturesque and instructive examples. Its scientific and medical value is poor, but provides us with the various meanings of the word 'neurosis' in the late nineteenth century. Copyright © 2013 S. Karger AG, Basel.

  20. Estimation of power feedback parameters of the IBR-2M reactor by square wave reactivity

    International Nuclear Information System (INIS)

    Pepelyshev, Yu.N.; Popov, A.K.; Sumkhuu, D.

    2016-01-01

    Parameters of the IBR-2M reactor power feedback (PFB) are estimated based on the analysis of power transients caused by deliberate square wave reactivity when the pulsed reactor operates in the self-regulation mode. The PFB of the IBR-2M is described by three linear first-order differential equations. Two components of the PFB are responsible for the negative feedback and one, for the positive. The overall feedback is negative, i.e., it has a stabilizing effect for the operation of the reactor. The slowest negative component of the PFB is probably caused by heating of the fuel. Periodically repeated in the process of exploitation, estimation of the PFB parameters is one of the methods to ensure safety operation of the reactor. [ru

  1. A history of effluent releases from the Texas A and M University reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bates, E F; Neff, R D; Sandel, P S; Schoenbucher, B [Texas A and M University (United States)

    1974-07-01

    Since 1966 records of radioactive effluents releases from the Texas A and M University Research Reactor have been compiled. These data include particulate activity, noble gases, and liquid effluent releases. Particulate activity releases with half-lives greater than eight days were negligible and are not included in this presentation. Conversion from an MTR plate reactor to a TRIGA fueled reactor was completed in August 1968. Records of effluent releases of Argon-4l and liquids for the past, five years are summarized, in this presentation. These release data are compared to the current limits specified: in 10 CPR 20 and the limits appearing in proposed Appendix.

  2. Course of pin fuel test In WWR-M reactor core

    International Nuclear Information System (INIS)

    Zakharov, A.S.; Kirsanov, G.A.; Konoplev, K.A.

    2005-01-01

    Pin type fuel element (FE) of square form with twisted ribs was developed in VNIINM as an alternative for tube type FE of research reactors. Two variants of full-scale fuel assemblies (FA) are under test in the core of PNPI WWR-M reactor. One FA contains FE with UO 2 LEU and other - UMo LEU. Both types of FE have an aluminum matrix. Results of the first stages of the test are presented. (author)

  3. Design and experience of HEU and LEU fuel for WWR-M reactor

    International Nuclear Information System (INIS)

    Enin, A.A.; Erykalov, A.N.; Zakharov, A.S.; Zvezdkin, V.S.; Kirsanov, G.A.; Konoplev, K.A.; L'vov, V.S.; Petroc, Y.V.; Saikov, Y.P.

    1997-01-01

    A research reactor for providing high neutron fluxes has to have a compact, well breeding core with high specific heat removal. The WWR-M fuel elements meet these demands. They have optimum metal-to-water ratio and the recordly developed specific heat-transfer surface providing in a pool-type reactor at atmospheric pressure the unit heat of (900±100) kW. (author)

  4. A human reliability analysis of the University of New Mexico's AGN- 201M nuclear research reactor

    International Nuclear Information System (INIS)

    Brumburgh, G.P.; Heger, A.S.

    1992-01-01

    During 1990--1991, a probabilistic risk assessment was conducted on the University of New Mexico's AGN-201M nuclear research reactor to address the risk and consequence of a maximum hypothetical release accident. The assessment indicated a potential for consequential human error to precipitate Chis scenario. Subsequently, a human reliability analysis was performed to evaluate the significance of human interaction on the reactor's safety systems. This paper presents the results of that investigation

  5. Development of the Decommissioning Planning System for the WWR-M Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lobach, Y. [Institute for Nuclear Research, Kiev (Ukraine)

    2013-08-15

    Kiev's research reactor WWR-M is in operation for more than 50 years and its continued operation is planned. At the same time the development of a decommissioning plan is a mandatory requirement of the national legislation and it must be performed at the operational stage of nuclear installation as early as possible. Recently, the Decommissioning Programme for the WWR-M reactor has been developed. The programme covers the whole decommissioning process and represents the main guiding document during the whole decommissioning period, which determines and substantiates the principal technical and organizational activities on the preparation and implementation of the reactor decommissioning, the consequence of the decommissioning stages, the sequence of planned works and measures as well as the necessary conditions and infrastructure for the provision and safe implementation. The programme contains the basic directions of further decommissioning planning aimed on the timely preparation for the reactor decommissioning. This paper describes the status of the WWR-M reactor decommissioning planning attained by the middle of 2011. (author)

  6. Gas-cooled reactor thermal-hydraulics using CAST3M and CRONOS2 codes

    International Nuclear Information System (INIS)

    Studer, E.; Coulon, N.; Stietel, A.; Damian, F.; Golfier, H.; Raepsaet, X.

    2003-01-01

    The CEA R and D program on advanced Gas Cooled Reactors (GCR) relies on different concepts: modular High Temperature Reactor (HTR), its evolution dedicated to hydrogen production (Very High Temperature Reactor) and Gas Cooled Fast Reactors (GCFR). Some key safety questions are related to decay heat removal during potential accident. This is strongly connected to passive natural convection (including gas injection of Helium, CO 2 , Nitrogen or Argon) or forced convection using active safety systems (gas blowers, heat exchangers). To support this effort, thermal-hydraulics computer codes will be necessary tools to design, enhance the performance and ensure a high safety level of the different reactors. Accurate and efficient modeling of heat transfer by conduction, convection or thermal radiation as well as energy storage are necessary requirements to obtain a high level of confidence in the thermal-hydraulic simulations. To achieve that goal a thorough validation process has to ve conducted. CEA's CAST3M code dedicated to GCR thermal-hydraulics has been validated against different test cases: academic interaction between natural convection and thermal radiation, small scale in-house THERCE experiments and large scale High Temperature Test Reactor benchmarks such as HTTR-VC benchmark. Coupling with neutronics is also an important modeling aspect for the determination of neutronic parameters such as neutronic coefficient (Doppler, moderator,...), critical position of control rods...CEA's CAST3M and CRONOS2 computer codes allow this coupling and a first example of coupled thermal-hydraulics/neutronics calculations has been performed. Comparison with experimental data will be the next step with High Temperature Test Reactor experimental results at nominal power

  7. Formation of the high-spin Hf-179m2 isomer in reactor irradiations

    Czech Academy of Sciences Publication Activity Database

    Karamian, S. A.; Carroll, J. J.; Adam, Jindřich; Kulagin, EN.; Shabalin, EP.

    2004-01-01

    Roč. 14, č. 4 (2004), s. 438-441 ISSN 1054-660X R&D Projects: GA MŠk(CZ) ME 134 Keywords : reactor irradiation * high-spin Hf-179m2 Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.836, year: 2004

  8. Ethical Concern in Joseph Heller’s Catch-22

    Institute of Scientific and Technical Information of China (English)

    XIAN Yu-jing

    2015-01-01

    In Catch-22, Joseph Heller shows his ethical concern behind absurdity, which is manifested from his attitude toward individualism and utilitarianism, religious belief, sexual promiscuity, interpersonal relationship, etc.

  9. A Reading of Joseph Conrad's The Tale

    OpenAIRE

    Zadeh, Mohammad Reza Modarres

    2013-01-01

    The Tale is a short story by Joseph Conrad. Typical of a Conrad story it is set at sea. The sea is symbolic of the unconscious and this story may be read as a story of the unconscious. On the outside, it seems simple; a man tells a woman a tale of the commanding officer of a patrol ship who gives false directions to another ship and sends it to its doom. In between the lines of the seemingly simple plot, however, can be read another tale; one which speaks of a human sea deeper than the sea of...

  10. Study of nitrifying sequencing batch reactor in presence of m-Cresol

    International Nuclear Information System (INIS)

    Gonzalez-Alvarez, E.; Steed, E.; Ben-youssef, C.; Zepeda, A.

    2009-01-01

    The process of the nitrification has been studied scantly in presence of phenolic compounds such as m-cresol. the aim of this study was evaluate the tolerance of a nitrifying SBR (Sequencing Batch Reactor) to m-cresol and the ability of the sludge to consume this phenolic compound. Nitrification is the process of oxidation of ammonia to nitrite and nitrate by lithoautotrophic ammonia-and nitrite-oxidizing bacteria. (Author)

  11. First TREAT [Transient Reactor Test Facility] transient overpower tests on U-Pu-Zr fuel: M5 and M6

    International Nuclear Information System (INIS)

    Robinson, W.R.; Bauer, T.H.; Wright, A.E.; Rhodes, E.A.; Stanford, G.S.; Klickman, A.E.

    1987-01-01

    Transient Reactor Test Facility (TREAT) tests M5 and M6 were the first transient overpower (TOP) tests of the margin to cladding breach and prefailure elongation of metallic U-Pu-Zr ternary fuel, the reference fuel of the Integral Fast Reactor concept. Similar tests on U-Fs fueled EBR-II driver pins were previously performed and reported [1,2]. Results from these earlier tests indicated a margin to failure of about 4 times nominal power and significant axial elongation prior to failure, a feature that was very pronounced at low burnups. While these two fuel types are similar in many respects, the ternary alloy exhibits a much more complex physical structure and is typically irradiated at much higher temperatures. Thus, a prime motivation for performing M5 and M6 was to compare the safety related fuel performance characteristics of U-Fs and U-Pu-Zr. This report described conditions, results, and conclusions of testing of these fuel types

  12. Experimental estimations of the kinetics parameters of the IBR-2M reactor by stochastic noises

    International Nuclear Information System (INIS)

    Pepelyshev, Yu.N.; Tajybov, L.A.; Garibov, A.A.; Mekhtieva, R.N.

    2012-01-01

    Experimental investigations of stochastic fluctuations of pulse energy of the IBR-2M reactor have been carried out which allowed us to obtain some of the parameters of the reactor kinetics. At different levels of average power a sequence of values of pulse energy was recorded with the calculation of the distribution parameters. An ionization chamber with boron installed near the active zone was used as a neutron detector. The research results allowed us to estimate the average lifetime of prompt neutrons τ = (6.53±0.2)·10 -8 s, absolute power of the reactor and intensity of the source of spontaneous neutrons S sp ≤(6.72±0.12)·10 6 s -1 . It was shown that the experimental results are close to the calculated ones

  13. Biblisch-koranische Figuren – feminin: Jesus, Joseph and Job Characters from the Bible and the Quran—Feminine: Jesus, Joseph and Job

    Directory of Open Access Journals (Sweden)

    Barbara Winckler

    2003-07-01

    Full Text Available Jesus, Joseph and Job stellt drei Texte aus der Feder zeitgenössischer libanesischer Autorinnen vor, die auf unterschiedliche Weise die Geschichten religiöser Figuren neu schreiben, und diskutiert sie im Hinblick auf ihr subversives Potential für gesellschaftlichen Wandel. Dazu werden in der Analyse neben der Intertextualität Konzepte genderorientierter und postkolonialer Ansätze wie métissage und borderlands herangezogen.In Jesus, Joseph and Job Hartman introduces three texts, written by contemporary Lebanese women authors who re-write the history of religious characters, and discusses these texts with respect to their subversive potential for societal change. In her analysis, Hartman does not only use intertextuality, but also gender-informed and post-colonial approaches such as, métissage and border spaces.

  14. Operational characteristics analysis of a 8 mH class HTS DC reactor for an LCC type HVDC system

    International Nuclear Information System (INIS)

    Kim, S. K.; Go, B. S.; Dinh, M. C.; Park, M.; Yu, I. K.; Kim, J. H.

    2015-01-01

    Many kinds of high temperature superconducting (HTS) devices are being developed due to its several advantages. In particular, the advantages of HTS devices are maximized under the DC condition. A line commutated converter (LCC) type high voltage direct current (HVDC) transmission system requires large capacity of DC reactors to protect the converters from faults. However, conventional DC reactor made of copper causes a lot of electrical losses. Thus, it is being attempted to apply the HTS DC reactor to an HVDC transmission system. The authors have developed a 8 mH class HTS DC reactor and a model-sized LCC type HVDC system. The HTS DC reactor was operated to analyze its operational characteristics in connection with the HVDC system. The voltage at both ends of the HTS DC reactor was measured to investigate the stability of the reactor. The voltages and currents at the AC and DC side of the system were measured to confirm the influence of the HTS DC reactor on the system. Two 5 mH copper DC reactors were connected to the HVDC system and investigated to compare the operational characteristics. In this paper, the operational characteristics of the HVDC system with the HTS DC reactor according to firing angle are described. The voltage and current characteristics of the system according to the types of DC reactors and harmonic characteristics are analyzed. Through the results, the applicability of an HTS DC reactor in an HVDC system is confirmed

  15. Operational characteristics analysis of a 8 mH class HTS DC reactor for an LCC type HVDC system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. K.; Go, B. S.; Dinh, M. C.; Park, M.; Yu, I. K. [Changwon National University, Changwon (Korea, Republic of); Kim, J. H. [Daejeon University, Daejeon (Korea, Republic of)

    2015-03-15

    Many kinds of high temperature superconducting (HTS) devices are being developed due to its several advantages. In particular, the advantages of HTS devices are maximized under the DC condition. A line commutated converter (LCC) type high voltage direct current (HVDC) transmission system requires large capacity of DC reactors to protect the converters from faults. However, conventional DC reactor made of copper causes a lot of electrical losses. Thus, it is being attempted to apply the HTS DC reactor to an HVDC transmission system. The authors have developed a 8 mH class HTS DC reactor and a model-sized LCC type HVDC system. The HTS DC reactor was operated to analyze its operational characteristics in connection with the HVDC system. The voltage at both ends of the HTS DC reactor was measured to investigate the stability of the reactor. The voltages and currents at the AC and DC side of the system were measured to confirm the influence of the HTS DC reactor on the system. Two 5 mH copper DC reactors were connected to the HVDC system and investigated to compare the operational characteristics. In this paper, the operational characteristics of the HVDC system with the HTS DC reactor according to firing angle are described. The voltage and current characteristics of the system according to the types of DC reactors and harmonic characteristics are analyzed. Through the results, the applicability of an HTS DC reactor in an HVDC system is confirmed.

  16. Ludwig Boltzmann, Albert Einstein and Franz Joseph

    International Nuclear Information System (INIS)

    Broda, E.

    1983-01-01

    Under the Emperor Francis Joseph (1848-1916) the natural sciences were less weIl supported in Austria than in other countries of Europe. This is explained by the fact that the German speaking middle classes accepted the preeminence of the feudal forces with their antiscientific attitude. The reason for this readiness to subordination was that those middle classes feIt threatened in their relatively favourable situation by Slavs and Latins. Francis Joseph was the typical representative of the aristocracy. Personally, he did his duty conscientiously and was not corrupt, but progressive ideas and scientific thought were alien to him. From his desk he treated Boltzmann benevolently, but he had no wish to meet personally the greatest mind of the Empire or in any respect to ask his views. Another famous subject of the Emperor, Albert Einstein, was apparently ignored altogether. The structural weakness of Austria, due to the national problems, led to immobilism in her scientific life, but also, up to a point, to tolerance. The impression of Victor Adler on Einstein is considered in this historical context. (author) [de

  17. Jacques Joseph: Father of modern aesthetic surgery

    Directory of Open Access Journals (Sweden)

    Bhattacharya Surajit

    2008-10-01

    Full Text Available When we review the history of modern aesthetic surgery, a name that stands out as bright as a beacon and precious as gold is undoubtedly that of Jacques Joseph. A surgeon, par excellence, far ahead of his time, who chose to think out of the box, Joseph, despite all odds set out to give respectability to Aesthetic Surgery without depriving it of any scientific core values. By his words and deeds proved beyond doubt that only the very best in the field of reconstructive surgery, can visualize the hidden perfection in imperfection and formulate a treatment plan and a surgical strategy to achieve that elusive perfection. The rich surgical literature that he has left behind, the wealth of surgical instruments that he had designed and above all a way of thinking that he propagated, that aesthetic surgery is not frivolous but very serious endeavor, and treating the psychology of the patient is as important as treating his disease, undoubtedly makes him the revered ′Father of Modern Aesthetic Surgery′.

  18. Status and future of the WWR-M research reactor in Kiev

    Energy Technology Data Exchange (ETDEWEB)

    Bazavov, D.A.; Gavrilyuk, V.I.; Kirischuk, V.I.; Kochetkov, V.V.; Lysenko, M.V.; Makarovskiy, V.N.; Scherbachenko, A.M.; Shevel, V.N.; Slisenko, V.I. [Institute for Nuclear Research, Kiev (Ukraine)

    2001-07-01

    Kiev WWR-M Research Reactor, operated at maximum power of 10 MW, was put into operation in 1960 and during its 40-years history has been used to perform numerous studies in different areas of science and technology. Due to a number of technical problems the Research Reactor, the only one in Ukraine, was shut down in 1993 and then put into operation in 1999 again. Now there is an intention to reconstruct Kiev Research Reactor. The upgraded Research Reactor would allow solving such problems as the safe operation of Ukrainian NPPs, radioisotope production and, naturally, fundamental and applied research. The main problem for the successful operation of Kiev Research Reactor is the management and storage of spent fuel at the site, since after core unloading the spent fuel storage appears to be practically completed. So it is absolutely necessary to ship the most part of the spent fuel for reprocessing and as soon as possible. Besides, there is a need to build up the new spent fuel storage, because the tank of available storage requires careful inspection for corrosion. (author)

  19. Joseph Roth, tradutor do Império perdido

    Directory of Open Access Journals (Sweden)

    Luis S. Krausz

    2015-06-01

    Full Text Available Este artigo discute um folhetim jornalístico do escritor austríaco Joseph Roth que trata de uma miniatura do Templo de Salomão, encontrada por ele num café da Hirtenstrasse berlinense, no coração do que foi, na década de 1920, o bairro habitado pelos judeus do Leste da Europa na capital alemã. A nostalgia, sob cujo signo foi criada tal miniatura, torna-se uma metáfora da nostalgia pelo império Austro-Húngaro, chave para a compreensão da obra romanesca deste escritor. Ao mesmo tempo, esta nostalgia rothiana é contextualizada no âmbito das crenças místicas e messiânicas do judaísmo tradicional.

  20. Tribes of Men: John Joseph Mathews and Indian Internationalism

    Science.gov (United States)

    Lutenski, Emily

    2012-01-01

    In this article, the author discusses John Joseph Mathews and Indian internationalism. As an old man, Osage intellectual, writer, and historian, John Joseph Mathews recalled his expatriation from the United States during the 1920s. After growing up in Pawhuska, Oklahoma, seat of the Osage Nation, where he had been born in 1894 to a white mother…

  1. Application of Raptor-M3G to reactor dosimetry problems on massively parallel architectures - 026

    International Nuclear Information System (INIS)

    Longoni, G.

    2010-01-01

    The solution of complex 3-D radiation transport problems requires significant resources both in terms of computation time and memory availability. Therefore, parallel algorithms and multi-processor architectures are required to solve efficiently large 3-D radiation transport problems. This paper presents the application of RAPTOR-M3G (Rapid Parallel Transport Of Radiation - Multiple 3D Geometries) to reactor dosimetry problems. RAPTOR-M3G is a newly developed parallel computer code designed to solve the discrete ordinates (SN) equations on multi-processor computer architectures. This paper presents the results for a reactor dosimetry problem using a 3-D model of a commercial 2-loop pressurized water reactor (PWR). The accuracy and performance of RAPTOR-M3G will be analyzed and the numerical results obtained from the calculation will be compared directly to measurements of the neutron field in the reactor cavity air gap. The parallel performance of RAPTOR-M3G on massively parallel architectures, where the number of computing nodes is in the order of hundreds, will be analyzed up to four hundred processors. The performance results will be presented based on two supercomputing architectures: the POPLE supercomputer operated by the Pittsburgh Supercomputing Center and the Westinghouse computer cluster. The Westinghouse computer cluster is equipped with a standard Ethernet network connection and an InfiniBand R interconnects capable of a bandwidth in excess of 20 GBit/sec. Therefore, the impact of the network architecture on RAPTOR-M3G performance will be analyzed as well. (authors)

  2. A neutronic feasibility study for LEU conversion of the WWR-M reactor at Gatchina

    International Nuclear Information System (INIS)

    Petrov, Yu. V.; Erykalov, A.N.; Onegin, M.S.

    2000-01-01

    In this report we present the results of computations of the full scale reactor core with HEU (90%), MEU (36%) and LEU (19.75%) fuel. The reactor computer model for the MCU RFFI Monte Carlo code includes all peculiarities of the core. Calculations show that a uranium density of 3.3gU/cm 3 of MEU (36%) fuel and 8/25gU/cm 3 of LEU (19.75%) in WWR-M5 fuel assembly (FA) geometry is required to match the fuel cycle length of the HEU (90%) case with the same end of cycle (EOEC) excess reactivity. For the equilibrium fuel cycle the fuel burnup and poisoning, the fast and thermal neutron fluxes, the reactivity worth of control rods were calculated for the reference case with HEU (90%) FA and for the MEU and LEU FA. The relative accuracy of this neutronic feasibility study of fuel enrichment reduction of the WWR-M reactor in Gatchina is sufficient to start the fabrication feasibility study of MEU (36%) WWR-M5 fuel assemblies. At the present stage of technology it seems hardly possible to manufacture LEU (19.75%) fuel elements in WWR-M5 geometry due to too high uranium density. Only a future R and D can solve the problem. (author)

  3. Disartria e doença de Machado-Joseph: relato de caso Dysarthria in Machado-Joseph disease: case report

    Directory of Open Access Journals (Sweden)

    Angela Ruviaro Busanello

    2007-09-01

    Full Text Available O objetivo deste estudo foi descrever os principais aspectos fonoaudiológicos relacionados à fala na doença de Machado-Joseph, em um indivíduo do sexo masculino, selecionado entre outros pacientes portadores desta doença com limitações significativas de fala. O paciente foi atendido no Setor de Fonoaudiologia do Serviço de Fisiatria do Hospital de Clínicas de Porto Alegre. Especificamente quanto à fala e seus processos, observou-se quadro disártrico predominantemente atáxico, que piorou com a evolução da doença, passando de leve para severo. Estes resultados permitiram a conclusão de que as alterações tornam-se significativas na fala do portador de doença de Machado-Joseph, associadas ao comprometimento da respiração, articulação, fonação e ressonância. Concluiu-se também quanto à importância do tratamento fonoaudiológico na doença de Machado-Joseph, sugerindo-se novos estudos, com número maior de indivíduos, sejam realizados, a fim de melhor caracterizar as alterações de fala observadas neste estudo.The aim of this study was to describe the essential speech aspects of Machado-Joseph disease in a male patient with this diagnosis, selected among others with the same disease that received treatment at the Speech-Language Pathology and Audiology department of Hospital de Clínicas de Porto Alegre (Brazil. Regarding the speech process, it was observed ataxic dysarthria, which worsened from light to severe with the evolution of the disease. These results allowed the conclusion that speech alterations become more and more significant for Machado-Joseph patients, together with deficits in breathing, articulation, phonation and resonance. Finally, it was possible to suggest that Speech Pathology treatment is essential in Machado-Joseph disease, although more studies are necessary, with larger samples, in order to better characterize the speech alterations observed this study.

  4. Ludwig Boltzmann, Albert Einstein and Franz Joseph; Ludwig Boltzmann, Albert Einstein und Franz Joseph

    Energy Technology Data Exchange (ETDEWEB)

    Broda, E.

    1983-07-01

    Under the Emperor Francis Joseph (1848-1916) the natural sciences were less weIl supported in Austria than in other countries of Europe. This is explained by the fact that the German speaking middle classes accepted the preeminence of the feudal forces with their antiscientific attitude. The reason for this readiness to subordination was that those middle classes feIt threatened in their relatively favourable situation by Slavs and Latins. Francis Joseph was the typical representative of the aristocracy. Personally, he did his duty conscientiously and was not corrupt, but progressive ideas and scientific thought were alien to him. From his desk he treated Boltzmann benevolently, but he had no wish to meet personally the greatest mind of the Empire or in any respect to ask his views. Another famous subject of the Emperor, Albert Einstein, was apparently ignored altogether. The structural weakness of Austria, due to the national problems, led to immobilism in her scientific life, but also, up to a point, to tolerance. The impression of Victor Adler on Einstein is considered in this historical context. (author) [German] Die Naturwissenschaften wurden in Österreich unter Franz Joseph (1848-1916) weniger gefördert als in anderen Staaten Europas. Dies wird darauf zurückgeführt, daß das deutschsprechende Bürgertum sich mit der Vorherrschaft der feudalen Kräfte abfand, die nicht wissenschafts-freundlich waren. Für die Bereitschaft zur Unterordnung unter die Feudalen war maßgebend, daß das deutschsprechende Bürgertum sich durch Slawen und Romanen in seiner relativen Vorzugsstellung bedroht sah. Franz Joseph war der typische Repräsentant des konservativen Feudalismus. Er war persönlich pflichtbewußt und integer, doch waren ihm fortschrittliche Gedanken und wissenschaftliche Denkweise fremd. Boltzmann behandelte er von seinem Schreibtisch aus wohlwollend, doch hegte er keinen Wunsch, den größten Geist seines Reiches persönlich kennen zu lernen oder ihn in

  5. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

    Purpose: To provide a lmfbr type reactor wherein effusion of coolants through a loop contact portion is reduced even when fuel assemblies float up, and misloading of reactor core constituting elements is prevented thereby improving the reactor safety. Constitution: The reactor core constituents are secured in the reactor by utilizing the differential pressure between the high-pressure cooling chamber and low-pressure cooling chamber. A resistance port is formed at the upper part of a connecting pipe, and which is connect the low-pressure cooling chamber and the lower surface of the reactor core constituent. This resistance part is formed such that the internal sectional area of the connecting pipe is made larger stepwise toward the upper part, and the cylinder is formed larger so that it profiles the inner surface of the connecting pipe. (Aizawa, K.)

  6. Impact of the 37M fuel design on reactor physics characteristics

    International Nuclear Information System (INIS)

    Perez, R.; Ta, P.

    2013-01-01

    For CANDU nuclear reactors, aging of the Heat Transport System (HTS) leads to, among other effects, a reduction on the Critical Heat Flux (CHF) and dryout margin. In an effort to mitigate the impact of aging of the HTS on safety margins, Bruce Power is introducing a design change to the standard 37-element fuel bundle known as the modified 37-element fuel bundle, or 37M for short. As part of the overall design change process it was necessary to assess the impact of the modified fuel bundle design on key reactor physics parameters. Quantification of this impact on lattice cell properties, core reactivity properties, etc., was reached through a series of calculations using state-of-the-art lattice and core physics models, and comparisons against results for the standard fuel bundle. (author)

  7. The Experience of Storage and Shipment for Reprocessing of HEU Nuclear Fuel Irradiated in the IRT-M Research Reactor and Pamir-630 Mobile Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Sikorin, S. N.; Polazau, S. A.; Luneu, A. N.; Hrigarovich, T. K. [Joint Institute for Power and Nuclear Research–Sosny of the National Academy of Sciences of Belarus, Minsk (Belarus)

    2014-08-15

    At the end of 2010 under the Global Threat Reduction Initiative (GTRI), the Joint Institute for Power and Nuclear Research–“Sosny” (JIPNR–Sosny) of the National Academy of Sciences of the Republic of Belarus repatriated HEU spent nuclear fuel to the Russian Federation. The spent nuclear fuel was from the decommissioned Pamir-630D mobile reactor and IRT-M research reactor. The paper discusses the Pamir-630D spent nuclear fuel; experience and problems of spent nuclear fuel storage; and various aspects of the shipment including legal framework, preparation activities and shipment logistics. The conceptual project of a new research reactor for Belarus is also presented.

  8. Reactor

    International Nuclear Information System (INIS)

    Ikeda, Masaomi; Kashimura, Kazuo; Inoue, Kazuyuki; Nishioka, Kazuya.

    1979-01-01

    Purpose: To facilitate the construction of a reactor containment building, whereby the inspections of the outer wall of a reactor container after the completion of the construction of the reactor building can be easily carried out. Constitution: In a reactor accommodated in a container encircled by a building wall, a space is provided between the container and the building wall encircling the container, and a metal wall is provided in the space so that it is fitted in the building wall in an attachable or detatchable manner. (Aizawa, K.)

  9. Development of M3C code for Monte Carlo reactor physics criticality calculations

    International Nuclear Information System (INIS)

    Kumar, Anek; Kannan, Umasankari; Krishanani, P.D.

    2015-06-01

    The development of Monte Carlo code (M3C) for reactor design entails use of continuous energy nuclear data and Monte Carlo simulations for each of the neutron interaction processes. BARC has started a concentrated effort for developing a new general geometry continuous energy Monte Carlo code for reactor physics calculation indigenously. The code development required a comprehensive understanding of the basic continuous energy cross section sets. The important features of this code are treatment of heterogeneous lattices by general geometry, use of point cross sections along with unionized energy grid approach, thermal scattering model for low energy treatment, capability of handling the microscopic fuel particles dispersed randomly. The capability of handling the randomly dispersed microscopic fuel particles which is very useful for the modeling of High-Temperature Gas-Cooled reactor fuels which are composed of thousands of microscopic fuel particle (TRISO fuel particle), randomly dispersed in a graphite matrix. The Monte Carlo code for criticality calculation is a pioneering effort and has been used to study several types of lattices including cluster geometries. The code has been verified for its accuracy against more than 60 sample problems covering a wide range from simple (like spherical) to complex geometry (like PHWR lattice). Benchmark results show that the code performs quite well for the criticality calculation of the system. In this report, the current status of the code, features of the code, some of the benchmark results for the testing of the code and input preparation etc. are discussed. (author)

  10. Machado-Joseph Disease in Pedigrees of Azorean descent is Linked to Chromosome 14

    OpenAIRE

    George-Hyslop, P. St; Rogaeva, E.; Huterer, J.; Tsuda, T.; Santos, J.; Haines, J. L.; Schlumpf, K.; Rogaev, E. I.; Liang, Y.; McLachlan, D. R. Crapper; Kennedy, J.; Weissenbach, J.; Billingsley, G. D.; Cox, D. W.; Lang, A. E.

    1994-01-01

    A locus for Machado-Joseph disease (MJD) has recently been mapped to a 30-cM region of chromosome 14q in five pedigrees of Japanese descent. MJD is a clinically pleomorphic neurodegenerative disease that was originally described in subjects of Azorean descent. In light of the nonallelic heterogeneity in other inherited spinocere-bellar ataxias, we were interested to determine if the MJD phenotype in Japanese and Azorean pedigrees arose from mutations at the same locus. We provide evidence tha...

  11. reflection on the theology of joseph ratzinger (pope benedict xvi)

    African Journals Online (AJOL)

    the Faith which issued, in 1985, a Notification on his book, Church, Charism and Power (1981), signed by Joseph ... Ratzinger's doctoral studies in the ecclesiology of Augustine and ...... Harvard Divinity Bulletin (autumn):56-62. Gutierrez, G.

  12. Joseph Rotblat: influences, scientific achievements and legacy

    Science.gov (United States)

    Underwood, Martin

    2008-11-01

    Joseph Rotblat was one of the most distinguished nuclear physicists and peace campaigners of the post Second World War period. His peace activities rank alongside those of Albert Einstein and Bertrand Russell; he won the Nobel Peace Prize, jointly with the Pugwash movement, that he helped found. However, he made significant contributions to science, and in particular to the medical applications of accelerators, radiation and radio-nuclides. In this article his early work and influences in Poland are described. He then joined James Chadwick at Liverpool University and began work on the cyclotron recently constructed there. Rotblat then, together with Chadwick, joined the Manhattan Project. This experience was to shape his life. He stayed at Los Alamos for less than a year before walking out. He was suspected of being a spy. Rotblat then became Professor of Physics at St Bartholomew's Medical College and pioneered the use of a 15 MeV linear accelerator in treatment and research. He made fundamental contributions to understanding the effects of the fallout from nuclear bomb tests. He also, together with Patricia Lindop, made important contributions to understanding the biological effects of radiation.

  13. Joseph de Maistre and Retributionist Theology

    Directory of Open Access Journals (Sweden)

    Gabriel Andrade

    2017-12-01

    Full Text Available Joseph de Maistre is usually portrayed as Edmund Burke’s French counterpart, as they both wrote important treatises against the French Revolution. Although Maistre did share many of Burke’s conservative political views, he was much more than a political thinker. He was above all a religious thinker who interpreted political events through the prism of a particular retributionist theology. According to this theology, God punishes evil deeds, not only in the afterlife, but also in this terrestrial life; and sometimes, he may even use human tyrants as instruments of his wrath. This interpretation especially evident in Maistre’s Considerations sur la France, an early work in his philosophical career. In that book, Maistre interprets the French Revolution as divine punishment, and in that regard, his views bear some similarities to the Deuteronomist historian in the Hebrew Bible, who interpreted the destruction of Jerusalem and the Babylonian Exile, as divine punishment in retribution of Israel’s sins.

  14. Joseph Priestley, oxygen, and the enlightenment.

    Science.gov (United States)

    West, John B

    2014-01-01

    Joseph Priestley (1733–1804) was the first person to report the discovery of oxygen and describe some of its extraordinary properties. As such he merits a special place in the history of respiratory physiology. In addition his descriptions in elegant 18th-century English were particularly arresting, and rereading them never fails to give a special pleasure. The gas was actually first prepared by Scheele (1742–1786) but his report was delayed. Lavoisier (1743–1794) repeated Priestley's initial experiment and went on to describe the true nature of oxygen that had eluded Priestley, who never abandoned the erroneous phlogiston theory. In addition to oxygen, Priestley isolated and characterized seven other gases. However, most of his writings were in theology because he was a conscientious clergyman all his life. Priestley was a product of the Enlightenment and argued that all beliefs should be able to stand the scientific scrutiny of experimental investigations. As a result his extreme liberal views were severely criticized by the established Church of England. In addition he was a supporter of both the French and American Revolutions. Ultimately his political and religious attitudes provoked a riot during which his home and his scientific equipment were destroyed. He therefore emigrated to America in 1794 where his friends included Thomas Jefferson and Benjamin Franklin. He settled in Northumberland, Pennsylvania although his scientific work never recovered from his forced departure. But the descriptions of his experiments with oxygen will always remain a high point in the history of respiratory physiology.

  15. Joseph Henry's Conception of Scientific Knowledge

    Science.gov (United States)

    Theerman, Paul

    1997-04-01

    Joseph Henry, America's premier physicist and physics teacher in the mid-nineteenth century, had decided views of scientific knowledge. These were expressed in two ways. First of all, scientific knowledge led to moral betterment. Thus the study of science was a morally good thing. This was not only because it led to the contemplation of God's creation, which was a standard reason justifying the study of science dating from the Scientific Revolution and even earlier. More importantly, the study of science itself was a moral discipline, imparting to scientists the habits and virtues of truthfulness, respect for others, care and diligence, and the discernment of meaningful patterns from experience. The moral ideals of science were expressed most strongly in Henry's upholding the international "Republic of Science"; conversely, cheapening science was a sign of moral failure. Second, for Henry and his generation, science provided a path to sure truth, separate from falsehood of both the politics and the quackery that characterized mid-century public life. Henry promoted this in his championing of the Smithsonian Institution a scientific establishment, against the ideas of others who wanted to make it a literary establishment or a training school for teachers. For Henry, the Smithsonian's scientific reputation would be established by relying on careful peer review in its publications, and supporting established scientists to write authoritative popular works. The purpose of both these activities was to raise the profile of science in the United States and further establish science and the scientific method as a guide to public life.

  16. Neutronics analysis of the modular stellarator power reactor UWTOR-M

    International Nuclear Information System (INIS)

    El-Guebaly, L.A.

    1983-05-01

    Neutronics and photonics analysis for UWTOR-M was carried out to assess radiation streaming effects on reactor performance. The effect the lithium enrichment in the Li 17 Pb 83 breeder has on radiation streaming was investigated. Using an enrichment of 35% was found to yield an adequate tritium breeding ratio of 1.08 and an overall energy multiplication of 1.153. The bulk shield was optimized to reduce the radiation effects in the superconducting magnets with the limited shielding space available in the design. Detailed analysis for the radiation streaming into the divertor regions has been performed. The divertor targets were found to recover 91% of the streaming energy

  17. Homogeneous SLOWPOKE reactors for Mo-99/Tc-99m production in North America

    Energy Technology Data Exchange (ETDEWEB)

    Hilborn, J.W., E-mail: hilbovanw@sympatico.ca [Deep River, Ontario (Canada); Bonin, H.W. [Royal Military College of Canada, Kingston, Ontario (Canada)

    2014-07-01

    The 15 month shutdown of NRU in 2009 - 2010 caused an overall isotope shortage of approximately 30%; and in North America, the annual Tc-99m demand decreased from an estimated 20 million unit doses to about 15 million unit doses. Mo-99/Tc-99m is produced from HEU targets, irradiated in NRU for 11 days, and after chemical removal of uranium it is shipped to Nordion in Kanata, Ontario. Nordion further purifies the material and sends it to Lantheus Medical Imaging in the USA for manufacture of Mo-99 generators, which are then distributed to hundreds of hospital radiopharmacies throughout North America. One other American company, Covidien, manufactures and distributes Mo-99 generators like Lantheus, but they import bulk Mo-99 from Europe or South Africa. At the hospitals, Tc-99m is chemically extracted daily from the Mo-99 generators and loaded into syringes for immediate clinical use. Fortuitously, the 66 hour half-life of Mo-99 allows the replenishment of Tc-99m in the generator over a growth period of about 20 hours; and a generator can be 'milked' daily for up to two weeks. A more efficient model is the direct production and distribution of Tc-99m unit doses to regional hospitals from 10 'industrial' radiopharmacies located at existing licensed reactor sites in North America. A 20 kW homogeneous SLOWPOKE reactor at each site would deliver 15 litres of irradiated uranyl sulphate fuel solution daily to industrial-scale hot cells for extraction of Mo-99, which would be incorporated in large Mo-99/Tc-99m generators for extraction of Tc-99m five days a week; and the Low Enriched Uranium (LEU) would be recycled. Each automated hot-cell facility would be designed to load up to 7,000 Tc-99m syringes daily, for courier delivery to all of the Nuclear Medicine hospitals within a 3 hour average range by road transport. Typically, the delivered doses would be in the range 10 to 30 mCi. Assuming an average unit dose of 25 mCi at the hospital and 5 x 52

  18. Uranium transport around the reactor zone at Okelobondo (Oklo). Data evaluation with M3 and HYTEC

    International Nuclear Information System (INIS)

    Gurban, I.; Laaksoharju, M.; Made, B.; Ledoux, E.

    1999-12-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is conducting and participating in Natural Analogue activities as part of various studies regarding the final disposal of high level nuclear waste (HLW). The aim of this study is to use the hydrogeological and hydrochemical data from Okelobondo (Oklo Natural Analogue) to compare the outcome of two independent modelling approaches (HYTEC and M3). The modelling helps to evaluate the processes associated with nuclear natural reactors such as redox, adsorption/desorption and dissolution/precipitation of the uranium and to develop more realistic codes which can be used for site investigations and data evaluation. HYTEC (1D and 2D) represents a deterministic, transport and multi-solutes reactive coupled code developed at Ecole des Mines de Paris. M3 (Multivariate Mixing and Mass balance calculations) is a mathematical-statistical concept code developed for SKB. M3 can relatively easily be used to calculate mixing portions and to identify sinks or sources of element concentrations that may exist in a geochemical system. M3 helped to address the reactions in the coupled code HYTEC. Thus, the major flow-paths and reaction paths were identified and used for transport evaluation. The reactive transport results (one-dimensional and two-dimensional simulations) are in good agreement with the statistical approach using the M3 model. M3 and HYTEC show a dissolution of the uranium layer in contact with upwardly oxidising waters. M3 and HYTEC show a gain of manganese rich minerals downstream the reactor. A comparison of the U and Mn plots for M3 deviation and HYTEC results showed an almost mirror behaviour. The U transport stops when the Mn gain increases. Thus, HYTEC and M3 modelling predict that a possible reason for not having U transport up to the surface in Okelobondo is due to an inorganic trap which may hinder the uranium transport. The two independent modelling approaches can be used to complement each other and to

  19. Justify of implementation of a hot water layer system in swimming pool research reactor IEA-R1m

    International Nuclear Information System (INIS)

    Toyoda, Eduardo Yoshio; Gordon, Ana Maria Pinho Leite; Sordi, Gian-Maria A.A.

    2001-01-01

    The IPEN/CNEN-SP has a swimming pool research reactor (IEA-R1m) in operation since 1957 at 2 MW. In 1998, after some modifications, its nominal power increased to 5 MW. Among these modifications some adaptations had to be accomplished in the radiological protection and operational procedure. The present work aim to study the need of implementation of a hot water layer in order to reduce the dose in the workers in the vicinity of the reactor swimming pool. Applying the principles of radioprotection optimization, it was concluded that the decision of the construction of one hot water layer system in the reactor swimming pool, is not necessary. (author)

  20. Organization of remote control of spectrometers at the IBR-2M reactor

    International Nuclear Information System (INIS)

    Kirilov, A.S.; Murashkevich, S.M.; Okulov, R.Yu.; Petukhova, T.B.

    2008-01-01

    The development of network infrastructure in Dubna creates conditions for the remote supervision/control of experiment at the IBR-2M reactor beyond the JINR local network. The opportunity of observing an experiment from outside makes it possible to respond to errors or unforeseen, to save the reactor time. The principles of organization and peculiarities of implementation of the WebSonix system consisting of the central web-site and communication facilities for spectrometers are considered in the paper. The system allows one to reflect the actual condition of all the components of the instrument, survey log files, visualize the accumulated spectra and to control the experimental procedure on the instruments controlled by the software complex Sonix+ (OS Windows XP). The system is an independent instrument, it is easy to extend or change and easy to adapt to the instrument data specifics. The system is implemented using the PHP and Python scripts. The OS GNU/Linux Debian and web-server Apache 2 are installed on the web-site computer

  1. Decommissioning of the research nuclear reactor IRT-M and problems connected with radioactive waste

    International Nuclear Information System (INIS)

    Abramidze, S.P.; Katamadze, N.M.; Kiknadze, G.G.; Saralidze, Z.K.

    2000-01-01

    The nuclear research reactor IRT-2000 is described, along with modifications and upgrades made over the past three decades. Considerations are outlined which followed a decision to shut-down the reactor and to dismantle it. (author)

  2. Comparison of SERPENT and CASMO-5M for pressurized water reactors models

    International Nuclear Information System (INIS)

    Hursin, M.; Vasiliev, A.; Ferroukhi, H.; Pautz, A.

    2013-01-01

    The objective of this work is to perform a preliminary assessment of the capability of SERPENT to generate cross sections for a PWR Beginning-of-Life (BOL) isothermal mini-core by comparing a SERPENT/PARCS solution with the results obtained using a CASMO-5M/PARCS approach. The PARCS code is used instead of the usual SIMULATE-3 to analyze the Swiss Reactors, because interfaces with PARCS already exist to obtain neutronic data from SERPENT. For the PWR configurations, the differences between CASMO-5M and SERPENT solutions are within 200 pcm at the assembly level and thus rather small when considering the deterministic transport method (energy/angular/space discretization) in CASMO-5M versus the stochastic treatment of SERPENT, the statistical uncertainties in the Monte-Carlo approach as well as the eventual differences in nuclear data used by both codes. At the 2D mini-core level, no major difference is observed when comparing PARCS run with CASMO-5M versus SERPENT cross sections. For the generation of kinetic parameters, non trivial differences are observed due both to the methods and the data used. For the relatively limited number of configurations considered, it is hard to make any definitive statement on the benefits of using Monte Carlo codes in terms of nuclear data generation. (authors)

  3. Transactions of the 9th international conference on structural mechanics in reactor technology. Vol. M

    International Nuclear Information System (INIS)

    Wittmann, F.H.

    1987-01-01

    For obvious reasons reliability plays a dominant role in reactor technology. The area to be covered by Division M which deals with this subject, can be briefly summarized as follows: Probabilistic safety assessment (PSA) of structures and uncertainty modelling in structural design. Pre-service and in-service inspection with respect to evaluation of the probability of failure in time of structure. Stochastic loads modelling. External events (earthquakes, aircraft-impacts, etc.). Stochastic damage models of materials and structures. Probabilistic fracture mechanics. Model for ageing of components and structures. Reliability analysis of large and complex systems. Benchmark exercises. Analysis of operational experience. Precursor-studies. Man-machine interactions. Relationship between availability and PSA. Using probabilistic methods in setting up codes, standards and safety goals. Risk assessment of nuclear power plants and of nuclear fuel cycle installations. All 65 papers are separately indexed in the database. (orig./HP)

  4. Diversification of 99Mo/99mTc separation: non–fission reactor production of 99Mo as a strategy for enhancing 99mTc availability.

    Science.gov (United States)

    Pillai, Maroor R A; Dash, Ashutosh; Knapp, Furn F Russ

    2015-01-01

    This paper discusses the benefits of obtaining (99m)Tc from non-fission reactor-produced low-specific-activity (99)Mo. This scenario is based on establishing a diversified chain of facilities for the distribution of (99m)Tc separated from reactor-produced (99)Mo by (n,γ) activation of natural or enriched Mo. Such facilities have expected lower investments than required for the proposed chain of cyclotrons for the production of (99m)Tc. Facilities can receive and process reactor-irradiated Mo targets then used for extraction of (99m)Tc over a period of 2 wk, with 3 extractions on the same day. Estimates suggest that a center receiving 1.85 TBq (50 Ci) of (99)Mo once every 4 d can provide 1.48-3.33 TBq (40-90 Ci) of (99m)Tc daily. This model can use research reactors operating in the United States to supply current (99)Mo needs by applying natural (nat)Mo targets. (99)Mo production capacity can be enhanced by using (98)Mo-enriched targets. The proposed model reduces the loss of (99)Mo by decay and avoids proliferation as well as waste management issues associated with fission-produced (99)Mo.

  5. Reactors

    DEFF Research Database (Denmark)

    Shah, Vivek; Vaz Salles, Marcos António

    2018-01-01

    The requirements for OLTP database systems are becoming ever more demanding. Domains such as finance and computer games increasingly mandate that developers be able to encode complex application logic and control transaction latencies in in-memory databases. At the same time, infrastructure...... engineers in these domains need to experiment with and deploy OLTP database architectures that ensure application scalability and maximize resource utilization in modern machines. In this paper, we propose a relational actor programming model for in-memory databases as a novel, holistic approach towards......-level function calls. In contrast to classic transactional models, however, reactors allow developers to take advantage of intra-transaction parallelism and state encapsulation in their applications to reduce latency and improve locality. Moreover, reactors enable a new degree of flexibility in database...

  6. Transportable nuclear power plant T3C-M with two reactor plants of improved safety

    International Nuclear Information System (INIS)

    Ogloblin, B.G.; Gromov, B.F.

    1993-01-01

    Development and cultivating of districts in Siberia, North, Far East, Kamchatka and other remote or almost inaccessible district of the country depends to a large degree on their providing with power. The specific character of these districts imposes in turn a wide variety of special requirements upon the power sources. In particular, it is essential to provide the following; maximum manufacture availability of the whole equipment at the minimum volume of construction and installation work on operation site, high safety, longterm service life, ecologically, minimum scope of work on equipment in-service maintenance and inspection, etc. Taking into account the well-known difficulties connected with the delivery of conventional energy carriers to the above-mentioned districts and the situation with the alternative power sources, the application of the low-power nuclear plants (NPP) for these purposes looks definitely promising. Among the probable trends in creating the NPPs of this type as very promising is considered the possibility to apply the two-circuit reactor plant of the vessel type with the liquid lead as a primary coolant and free air as a secondary coolant and working medium in the open gas-turbine cycle. The nuclear plant T3C-M of improved safety with two of this type reactor plants with total electric power of 8 MW is developed by CDB of Machine Building with participation of several enterprises of St. Petersburg under the scientific leadership and is intended for generation of electric power and up to 4 Gcal/h of heat for populated areas and installations placed at long distance from the main electric power supply sources where it is difficult or non-efficient economically to deliver the conventional kinds of fuel. The main principles being laid as a basis when developing the proposed NPP will allow one to create mobile power sources which possess a high degree of safety and inherent self-protection

  7. Development of Neutron Imaging System for Neutron Tomography at Thai Research Reactor TRR-1/M1

    Science.gov (United States)

    Wonglee, S.; Khaweerat, S.; Channuie, J.; Picha, R.; Liamsuwan, T.; Ratanatongchai, W.

    2017-09-01

    The neutron imaging is a powerful non-destructive technique to investigate the internal structure and provides the information which is different from the conventional X-ray/Gamma radiography. By reconstruction of the obtained 2-dimentional (2D) images from the taken different angle around the specimen, the tomographic image can be obtained and it can provide the information in more detail. The neutron imaging system at Thai Research Reactor TRR-1/M1 of Thailand Institute of Nuclear Technology (Public Organization) has been developed to conduct the neutron tomography since 2014. The primary goal of this work is to serve the investigation of archeological samples, however, this technique can also be applied to various fields, such as investigation of industrial specimen and others. This research paper presents the performance study of a compact neutron camera manufactured by Neutron Optics such as speed and sensitivity. Furthermore, the 3-dimentional (3D) neutron image was successfully reconstructed at the developed neutron imaging system of TRR-1/M1.

  8. Production of radiopharmaceutical 99mTc using wasteless reactor Zr-Mo gel-technology

    International Nuclear Information System (INIS)

    Savushkin, I.; Gurko, O.; Ravkova, E.

    2002-01-01

    An original methodology and technological process of the wasteless reactor gel-technology of 99m Tc producing on the basis of centralised Zr-Mo gel-generator have been developed by the Institute of Power Engineering Problems, National Academy of Sciences of Belarus in co-operation with the Research Institute of Oncology and Medical Radiology, Ministry of Health of Belarus. This approach allows 99m Tc to be produced on the basis of MoO 3 with an 99 Mo activity of 3-20 Ci. The technological process of 99m Tc sodium pertechnetate production is remotely controlled and automated. Based on clinical tests performed by the Ministry of Health of Belarus, the clinical application of 99m Tc produced by this technology has been approved. The irradiation conditions of the target, consequence of technological process, technological yield of objective product on the example of operation of one generator, reprocessing and rendering of the wastes are analysed and described. The distinctive features of the technology developed are as follows: (a) Use of native molybdenum as the starting target. (b) Absence of deleterious and toxic impurities from the final product (nitrates, organics, etc.). (c) Application of a modified method of 99m Tc extraction from 99 Mo with the help of the Zr-Mo-gel (that is, application of a true gel, not the powder obtained by gel drying), reducing the number of process stages and simplifying the technology. (d) Easy automation and remote control. (e) Simplicity of design and compactness, opening up wide application fields for the unit. It is suggested that clinical centres should be equipped with centralised high-performance 99m Tc generators. Such centres can supply 99m Tc sodium pertechnetate daily to radioisotope laboratories within the radius of 100 km. Technical and economic calculations show that the centralised gel-generators possess industrial, technical and economic parameters making them superior to small/portable generators based on loading with

  9. CDC's 29th Annual Joseph W. Mountin Lecture

    Centers for Disease Control (CDC) Podcasts

    In this podcast, William H. Foege, MD, MPH delivers the 29th Annual Joseph W. Mountin Lecture. Dr. Foege was a key leader in the smallpox effort and worked as an epidemiologist in the successful eradication campaign in the 1970s. Dr. Foege became chief of the Smallpox Eradication Program at CDC, and was appointed director of CDC in 1977.

  10. Science and Worldviews in the Classroom: Joseph Priestley and Photosynthesis

    Science.gov (United States)

    Matthews, Michael R.

    2009-01-01

    This paper elaborates on the life and publications of Joseph Priestley, the eighteenth-century polymath. The paper outlines his particular place in the European Enlightenment; it stresses the importance of philosophy and worldview in his scientific work on pneumatic chemistry, the composition of air, and his discovery of the process of…

  11. Using Joseph Campbell to Improve Students' Response to Literature.

    Science.gov (United States)

    Barnum, Carol M.

    1992-01-01

    Shows how teachers can use the videotapes and writings of Joseph Campbell to help students see patterns in literature and respond personally to it. Presents Campbell's explanation of the monomyth of the hero's journey, and discusses three works in which the pattern is present. (SR)

  12. Franz Joseph Gall and music: The faculty and the bump

    NARCIS (Netherlands)

    Eling, P.A.T.M.; Finger, S.; Whitaker, H.A.

    2015-01-01

    The traditional story maintains that Franz Joseph Gall's (1758-1828) scientific program began with his observations of schoolmates with bulging eyes and good verbal memories. But his search to understand human nature, in particular individual differences in capacities, passions, and tendencies, can

  13. The lssue of Guilt in Oedipus and Joseph K.

    Directory of Open Access Journals (Sweden)

    Janez Vrečko

    2002-07-01

    Full Text Available This essay addresses hamartia in Oedipus and Joseph K., originally guilt without sin later turned in to guilt of sin, as well as freedom and fate, death and redemption. The tragedy Oedipus the King starts with the plague in Thebes, while The Trial starts with the arrest of Joseph K., both events leading to the source of »misfortune«; since the source of misfortune is external, the two protagonists are guilty without committing a crime. In both works Aristotle's concept of hamartia is understood as an objective »tragic flaw« as well as a subjective decision taken by the hero. Since »guiltiness invites judgment«, both Oedipus and Joseph K. choose to flee in a »Wrong direction«, which leads to the fulfilment of the prophecy and to a verdict respectively. They misunderstand the objective hamartia and transform their guilt without sin in to the guilt of sin. But Oedipus' uncovering of his own past once the prophecy is fulfilled leads him to a theophanic death, while Joseph's recognition that his life has come to ruin leads to a bestial death. Iocasta and several female characters in The Trial attempt to thrust both men back in to the arena of objective hamartia, to restore them to the state of guilt without crime, but they fail. They do succeed, however, in leading the heroes to anagnorisis. This recognition enables Oedipus to evince his sense of responsibility by carrying out his self-punishment. Joseph's recognition, by contrast, includes neither responsibility nor self-punishment. The scene with Titorelli shows that Joseph's trial can only take place between two extremes -justice and manhunt - and as such it has parallels with the Chorus song following the scene with Oedipus and Teiresias. Moreover, it has a connection with the chapter taking place in the Cathedral, since the protagonists of each scene are identified at this point and their destinies linked to their names. On another level this scene reveals a similarity between the Sphinx

  14. Real-time neutron radiography at the Iea-R1 m nuclear research reactor

    International Nuclear Information System (INIS)

    Menezes, M.O. de; Pugliesi, R.; Pereira, M.A.S.; Andrade, M.L.G.

    2003-01-01

    A LIXI (Light Intensifier X-ray Image) device has been employed in a real-time neutron radiography system. The LIXI is coupled to a video camera and the real-time images can be observed in a TV monitor, and processed in a computer. In order to get the real-time system operational, the neutron radiography facility installed at the IEA-R1 m nuclear research reactor of the IPEN-CNEN/S P has been optimized. The most important improvements were the neutron/gamma ratio, the effective energy of the neutron beam, decrease of the scattered radiation at the irradiation position, and the additional shielding of the video camera. Several one-frame as well as computer processed images are presented. The overall Modulation Transfer Function for the real-time system was obtained from the resolution parameter p = 0:44 +- 0:04 mm; the system sensitivity, evaluated for a Perspex step wedge, was determined and the average value is 0:70 +- 0:09 mm. (author)

  15. Clinical evaluation of oropharyngeal dysphagia in Machado-Joseph disease

    Directory of Open Access Journals (Sweden)

    Sabrina Mello Alves Corrêa

    2010-12-01

    Full Text Available CONTEXT: In Machado-Joseph disease, poor posture, dystonia and peripheral neuropathy are extremely predisposing to oropharyngeal dysphagia, which is more commonly associated with muscular dystrophy. OBJECTIVE: To evaluate the clinical characteristics of oropharyngeal dysphagia in Machado-Joseph disease patients. METHOD: Forty individuals participated in this study, including 20 with no clinical complaints and 20 dysphagic patients with Machado-Joseph disease of clinical type 1, who were all similar in terms of gender distribution, average age, and cognitive function. The medical history of each patient was reviewed and each subject underwent a clinical evaluation of deglutition. At the end, the profile of dysphagia in patients with Machado-Joseph disease was classified according to the Severity Scale of Dysphagia, as described by O'Neil and collaborators. RESULTS: Comparison between dysphagic patients and controls did not reveal many significant differences with respect to the clinical evaluation of the oral phase of deglutition, since afflicted patients only demonstrated deficits related to the protrusion, retraction and tonus of the tongue. However, several significant differences were observed with respect to the pharyngeal phase. Dysphagic patients presented pharyngeal stasis during deglutition of liquids and solids, accompanied by coughing and/or choking as well as penetration and/or aspiration; these signs were absent in the controls. CONCLUSIONS: Oropharyngeal dysphagia is part of the Machado-Joseph disease since the first neurological manifestations. There is greater involvement of the pharyngeal phase, in relation to oral phase of the deglutition. The dysphagia of these patients is classified between mild and moderate.

  16. Reactor

    International Nuclear Information System (INIS)

    Fujibayashi, Toru.

    1976-01-01

    Object: To provide a boiling water reactor which can enhance a quake resisting strength and flatten power distribution. Structure: At least more than four fuel bundles, in which a plurality of fuel rods are arranged in lattice fashion which upper and lower portions are supported by tie-plates, are bundled and then covered by a square channel box. The control rod is movably arranged within a space formed by adjoining channel boxes. A spacer of trapezoidal section is disposed in the central portion on the side of the channel box over substantially full length in height direction, and a neutron instrumented tube is disposed in the central portion inside the channel box. Thus, where a horizontal load is exerted due to earthquake or the like, the spacers come into contact with each other to support the channel box and prevent it from abnormal vibrations. (Furukawa, Y.)

  17. Excitation of 107m,109m Ag isomeric states in the fast neutron inelastic scattering at the Ibr-2 reactor of JINR

    International Nuclear Information System (INIS)

    Alpatov, V.G.; Davydov, A.V.; Isaev, Yu.N.

    1997-01-01

    The excitation cross sections of long-living isomers of 107m,109m Ag nuclei were measured for the fast neutron inelastic scattering reactions at the Ibr-2 reactor of JINR (Dubna) by means of a comparison with the yield of the 103m Rh isomer. The excitation cross sections of the latter are known for analogous reactions in the wide energy range. The measured cross sections are the following: σ( 107m Ag) 204 ± 18 mb, σ( 109m Ag) = 262 ± 26 mb. These values are essentially lower than the excitation cross section of the 103m Rh isomer. The analysis of the data on level structures and transitions between these levels for rhodium and silver nuclei together with the data on γ-spectra created in the reactions (n, n ' γ) shows that the essential difference between excitation cross sections of Rh and Ag isomers can be explained by different populations of corresponding levels

  18. Kepentingan Rusia Dalam Memberikan Suaka Politik Kepada Edward Joseph Snowden

    OpenAIRE

    ", Ibrahim; Iskandar, Irwan

    2017-01-01

    This research to explain interest of Russia with Snowden. Edward Joseph Snowden is a former Central Intelligence Agency (CIA) employee and a former contractor for National Security Agency (NSA) who leaked classified information to The Guardian and The Washington Post. Snowden who leaked classified information have Surveillance program doing by United State of America. The Surveillance Program is a cooperate between 9 big companies from United States, which: Yahoo!, Facebook, Google, Apple, Sk...

  19. Astronaut Joseph Tanner is assisted into his EMU during training

    Science.gov (United States)

    1994-01-01

    Astronaut Joseph R. Tanner, STS-66 mission specialist, is assisted by Boeing suit expert Steve Voyles in donning the gloves for his extravehicular mobility unit (EMU) as he prepares to be submerged in a 25-feet deep pool at JSC's Weightless Environment Training Facility (WETF). Though no extravehicular activity (EVA) is planned for the mission, at least two astronauts are trained to perform tasks that would require a space walk in the event of failure of remote systems.

  20. 1398-IJBCS-Article-Joseph Kouassi+

    African Journals Online (AJOL)

    hp

    3Université d'Abobo-Adjamé, Laboratoire de Chimie Bio-Organique et de Substances Naturelles,. 02 BP 801 Abidjan 02, Côte d'Ivoire. 4INRA Science du Sol, BP 20619, 45166 Olivet cedex, ...... Mobilité relative des métaux lourds issus de la décharge d'Akouédo et risque de contamination de la nappe du Continental.

  1. Thermal hydraulic analyses of LVR-15 research reactor with IRT-M fuel

    International Nuclear Information System (INIS)

    Macek, J.

    1997-01-01

    The LVR-15 pool-type research reactor has been in operation at the Nuclear Research Institute at Rez since 1955. Following a number of reconstructions and redesigning, the current reactor power is 15 MW. Thermal hydraulic analyses to demonstrate that the core heat will be safely removed during operation as well as in accident situations were performed based on methodology which had been specifically developed for the LVR-15 research reactor. This methodology was applied to stationary thermal hydraulic computations, as well as to transients, particularly with reactivity failure and loss of circulation pumps emergencies. The applied methodology and the core configuration as used in the Safety Report are described. The initial and boundary conditions are then considered and the summary of the calculated failures with regard to the defined safety limits is presented. The results of the core configuration analyses are also discussed with respect to meeting the safety limits and to the applicability of the methodology to this purpose

  2. Measurement of the^ 235U(n,n')^235mU Integral Cross Section in a Pulsed Reactor

    Science.gov (United States)

    Vieira, D. J.; Bond, E. M.; Belier, G.; Meot, V.; Becker, J. A.; Macri, R. A.; Authier, N.; Hyneck, D.; Jacquet, X.; Jansen, Y.; Legrendre, J.

    2009-10-01

    We will present the integral measurement of the neutron inelastic cross section of ^235U leading to the 26-minute, E*=76.5 eV isomer state. Small samples (5-20 microgm) of isotope-enriched ^235U were activated in the central cavity of the CALIBAN pulsed reactor at Valduc where a nearly pure fission neutron spectrum is produced with a typical fluence of 3x10^14 n/cm^2. After 30 minutes the samples were removed from the reactor and counted in an electrostatic-deflecting electron spectrometer that was optimized for the detection of ^235mU conversion electrons. From the decay curve analysis of the data, the 26-minute ^235mU component was extracted. Preliminary results will be given and compared to gamma-cascade calculations assuming complete K-mixing or with no K-mixing.

  3. Selecting a MAPLE research reactor core for 1-10 mW operation

    International Nuclear Information System (INIS)

    Smith, H.J.; Roy, M.-F.; Carlson, P.A.

    1986-06-01

    The MAPLE class of research reactors is designed so that a single reactor concept can satisfy a wide range of practical applications. This paper reports the results of physics studies performed on a number of potential core configurations fuelled with either 5 w/o or 8 w/o enriched UO 2 or 20 w/o U 3 Si-Al and assesses the relative merits of each. Recommended core designs are given to maximize the neutron fluxes available for scientific application and isotope production

  4. Reactors

    International Nuclear Information System (INIS)

    Onuki, Koji; Sasanuma, Katsumi.

    1980-01-01

    Purpose: To make it possible to correctly measure the flow rate and temperatures of the coolants flowing through fuel assemblies. Constitution: One or more holes are formed at the side surface of the guide tube of a control rod driving mechanism thereby to reduce the flow path resistance within the guide tube of the control rod driving mechanism and to prevent the outlet coolant of the control rod guide tube from flowing into the guide tube of the mechanism as it is and also from flowing into ambient rectifying lattice guide tubes, so that the quantities and temperatures of the coolants flowing through respective fuel assemblies can be measured correctly. (Kamimura, M.)

  5. Safety-evaluation report related to renewal of the operating license for the Texas A and M University Research Reactor. Docket No. 50-128, License R-83

    International Nuclear Information System (INIS)

    1983-03-01

    This Safety Evaluation Report for the application filed by the Texas A and M University (Texas A and M) for a renewal of operating license number R-83 to continue to operate a research reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Texas Engineering and Experiment Station of the Texas A and M University and is located on the campus in College Station, Brazos County, Texas. The staff concludes that the TRIGA reactor facility can continue to be operated by Texas A and M University without endangering the health and safety of the public

  6. An extended conventional fuel cycle for the B and W mPower{sup TM} small modular nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Scarangella, M. J. [Babcock and Wilcox Company, 109 Ramsey Place, Lynchburg, VA 24502 (United States)

    2012-07-01

    The B and W mPower{sup TM} reactor is a small pressurized water reactor (PWR) with an integral once-through steam generator and a thermal output of about 500 MW; it is intended to replace aging fossil power plants of similar output. The core is composed of 69 reduced-height PWR assemblies with the familiar 17 x 17 fuel rod array. The Babcock and Wilcox Company (B and W) is offering a core loading and cycle management plan for a four-year cycle based on its presumed attractiveness to potential customers. This option is a once-through fuel cycle in which the entire core is discharged and replaced after four years. In addition, a conventional fuel utilization strategy, employing a periodic partial reload and shuffle, was developed as an alternative to the four-year once-through fuel cycle. This study, which was performed using the Studsvik core design code suite, is a typical multi-cycle projection analysis of the type performed by most fuel management organizations such as fuel vendors and utilities. In the industry, the results of such projections are used by the financial arms of these organizations to assist in making long-term decisions. In the case of the B and W mPower reactor, this analysis demonstrates flexibility for customers who consider the once-through fuel cycle unacceptable from a fuel utilization standpoint. As expected, when compared to the once-through concept, reloads of the B and W mPower reactor will achieve higher batch average discharge exposure, will have adequate shut-down margin, and will have a relatively flat hot excess reactivity trend at the expense of slightly increased peaking. (authors)

  7. Operating characteristic analysis of a 400 mH class HTS DC reactor in connection with a laboratory scale LCC type HVDC system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung-Kyu, E-mail: power@changwon.ac.kr [Changwon National University, 55306 Sarim-dong, Changwon 641-773 (Korea, Republic of); Kim, Kwangmin; Park, Minwon [Changwon National University, 55306 Sarim-dong, Changwon 641-773 (Korea, Republic of); Yu, In-Keun, E-mail: yuik@changwon.ac.kr [Changwon National University, 55306 Sarim-dong, Changwon 641-773 (Korea, Republic of); Lee, Sangjin [Uiduk University, Gyeongju 780-713 (Korea, Republic of)

    2015-11-15

    Highlights: • A 400 mH class HTS DC reactor and a laboratory scale test-bed for line-commutated converter type HVDC transmission system. • The 400 mH class HTS DC reactor was connected to real power network via the HVDC system. • The DC current flowed in HTS DC reactor has several harmonic components and it was analyzed using FFT. - Abstract: High temperature superconducting (HTS) devices are being developed due to their advantages. Most line commutated converter based high voltage direct current (HVDC) transmission systems for long-distance transmission require large inductance of DC reactor; however, generally, copper-based reactors cause a lot of electrical losses during the system operation. This is driving researchers to develop a new type of DC reactor using HTS wire. The authors have developed a 400 mH class HTS DC reactor and a laboratory scale test-bed for line-commutated converter type HVDC system and applied the HTS DC reactor to the HVDC system to investigate their operating characteristics. The 400 mH class HTS DC reactor is designed using a toroid type magnet. The HVDC system is designed in the form of a mono-pole system with thyristor-based 12-pulse power converters. In this paper, the investigation results of the HTS DC reactor in connection with the HVDC system are described. The operating characteristics of the HTS DC reactor are analyzed under various operating conditions of the system. Through the results, applicability of an HTS DC reactor in an HVDC system is discussed in detail.

  8. Operating characteristic analysis of a 400 mH class HTS DC reactor in connection with a laboratory scale LCC type HVDC system

    International Nuclear Information System (INIS)

    Kim, Sung-Kyu; Kim, Kwangmin; Park, Minwon; Yu, In-Keun; Lee, Sangjin

    2015-01-01

    Highlights: • A 400 mH class HTS DC reactor and a laboratory scale test-bed for line-commutated converter type HVDC transmission system. • The 400 mH class HTS DC reactor was connected to real power network via the HVDC system. • The DC current flowed in HTS DC reactor has several harmonic components and it was analyzed using FFT. - Abstract: High temperature superconducting (HTS) devices are being developed due to their advantages. Most line commutated converter based high voltage direct current (HVDC) transmission systems for long-distance transmission require large inductance of DC reactor; however, generally, copper-based reactors cause a lot of electrical losses during the system operation. This is driving researchers to develop a new type of DC reactor using HTS wire. The authors have developed a 400 mH class HTS DC reactor and a laboratory scale test-bed for line-commutated converter type HVDC system and applied the HTS DC reactor to the HVDC system to investigate their operating characteristics. The 400 mH class HTS DC reactor is designed using a toroid type magnet. The HVDC system is designed in the form of a mono-pole system with thyristor-based 12-pulse power converters. In this paper, the investigation results of the HTS DC reactor in connection with the HVDC system are described. The operating characteristics of the HTS DC reactor are analyzed under various operating conditions of the system. Through the results, applicability of an HTS DC reactor in an HVDC system is discussed in detail.

  9. Experimental study of nitrogen oxides in the IRT-M reactor

    International Nuclear Information System (INIS)

    Brazovskij, I.I.; Doroshevich, V.N.; Gvozdev, A.A.; Nesterenko, V.B.; Trubnikov, V.P.

    1982-01-01

    A critical review of different approaches to the radiolysis study of nitrogen oxide under mixed radiation conditions of a nuclear reactor was presented. Loop reactor piant opereted following gas-liquid cycle. It was shown in the process of long experiment in the operating conditions that irreversible radiation-thermal decomposition of the coolant increases little with temperature and pressure and radioactivity of the coolant and thermophysical equipment was moderate. Numerous kinetic experiments were conducted on the ampoule plant wherein all coolant existed in the zone of ionizing radiation effect. Initial pressure in the ampoule plant was set in the range of 0.1-16 MPa, depending on conditions of the experiment, and temperature 200-500 deg C. Dosimetry of the ampoule was carried out by the radiolysis of nitrogen monoxide. The analysis of the radiolysis products was conducted utilizing gas chromatography method, coolant vapours were removed in the process of low-temperature condensation under - 70 deg C

  10. HESTER: a hot-electron superconducting tokamak experimental reactor at M.I.T

    International Nuclear Information System (INIS)

    Schultz, J.H.; Montgomery, D.B.

    1983-04-01

    HESTER is an experimental tokamak, designed to resolve many of the central questions in the tokamak development program in the 1980's. It combines several unique features with new perspectives on the other major tokamak experiments scheduled for the next decade. The overall objectives of HESTER, in rough order of their presently perceived importance, are the achievement of reactor-like wall-loadings and plasma parameters for long pulse periods, determination of a good, reactor-relevant method of steady-state or very long pulse tokamak current drive, duplication of the planned very high temperature neutral injection experiments using only radio frequency heating, a demonstration of true steady-state tokamak operation, integration of a high-performance superconducting magnet system into a tokamak experiment, determination of the best methods of long term impurity control, and studies of transport and pressure limits in high field, high aspect ratio tokamak plasmas. These objectives are described

  11. The first critical experiment with a new type of fuel assemblies IRT-3M on the training reactor VR-I

    International Nuclear Information System (INIS)

    Matejka, Karel; Sklenka, Lubomir

    1997-01-01

    The paper 'The first critical experiment with a new type of fuel assemblies IRT-3M on training reactor VR-1 presents basic information about the replacement of fuel on the reactor VR-1 run on FJFI CVUT in Prague. In spring 1997 the IRT-2M fuel type used till then was replaced by the IRT-3M type. When the fuel was replaced, no change in its enrichment was made, i.e. its level remained as 36% 235 U. The replacement itself was carried out in tight co-operation with the Nuclear Research Institute Rez plc., as related to the operation of the research reactor LVR-15. The fuel replacement on the VR-I reactor is a part of the international program RERTR (Reduced Enrichment for Research and Test Reactors) in which the Czech Republic participates. (author)

  12. Status of prompt gamma neutron activation analysis (PGAA) at TRR-1/M1 (Thai Research Reactor-1/Modified 1)

    International Nuclear Information System (INIS)

    Asvavijnijkulchai, Chanchai; Dharmavanij, Wanchai; Siangsanan, Pariwat; Ratanathongchai, Wichian; Chongkum, Somporn

    1999-01-01

    The first prompt gamma activation analysis (PGAA) was designed, constructed and installed at a 6 inch diameter neutron beam port of the Thai Research Reactor-1/Modified 1 (TRR-1/M1) since 1989. Beam characteristic were made by Gd foil irradiation, X-ray film exposing and densitometry scanning consequently. The thermal neutron flux at sample position was measured by Au foil activation, and was about 1 x 10 7 n.cm 2 .sec -1 at 700 kW operating power. The experiments have been conducted successfully. In 1998, the PGAA facility has been developed for the reactor operating power at 1.2 MW. The new PGAA system, e.g., beam shutter, gamma collimator and biological shields have been designed to reduce the leakage of neutrons and gamma radiation to the acceptance levels in accordance with the International Commission on Radiation Protection Publication 60 (ICRP 60). The construction and installation will be completed in April 1999. (author)

  13. Measurement of cold neutron spectra at a model of cryogenic moderator of the IBR-2M reactor

    International Nuclear Information System (INIS)

    Kulikov, S.A.; Chernikov, A.N.; Shabalin, E.P.; Kalinin, I.V.; Morozov, V.M.; Novikov, A.G.; Puchkov, A.V.

    2010-01-01

    The article is dedicated to methods and results of experimental determination of cold neutron spectra from solid mesitylene at neutron moderator temperatures 10-50 K. Experiments were fulfilled at the DIN-2PI spectrometer of the IBR-2 reactor. The main goals of this work were to examine a system of constants for Monte Carlo calculation of cryogenic moderators of the IBR-2M reactor and to determine the temperature dependence of cold neutron intensity from the moderator. A reasonable agreement of experimental and calculation results for mesitylene at 20 K has been obtained. The cold neutron intensity at temperature of moderator 10 K is about 1.8 times higher than at T=50 K

  14. Thermal-Hydraulic Simulations of Single Pin and Assembly Sector for IVG- 1M Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kraus, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Garner, P. [Argonne National Lab. (ANL), Argonne, IL (United States); Hanan, N. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-01-15

    Thermal-hydraulic simulations have been performed using computational fluid dynamics (CFD) for the highly-enriched uranium (HEU) design of the IVG.1M reactor at the Institute of Atomic Energy (IAE) at the National Nuclear Center (NNC) in the Republic of Kazakhstan. Steady-state simulations were performed for both types of fuel assembly (FA), i.e. the FA in rows 1 & 2 and the FA in row 3, as well as for single pins in those FA (600 mm and 800 mm pins). Both single pin calculations and bundle sectors have been simulated for the most conservative operating conditions corresponding to the 10 MW output power, which corresponds to a pin unit cell Reynolds number of only about 7500. Simulations were performed using the commercial code STAR-CCM+ for the actual twisted pin geometry as well as a straight-pin approximation. Various Reynolds-Averaged Navier-Stokes (RANS) turbulence models gave different results, and so some validation runs with a higher-fidelity Large Eddy Simulation (LES) code were performed given the lack of experimental data. These singled out the Realizable Two-Layer k-ε as the most accurate turbulence model for estimating surface temperature. Single-pin results for the twisted case, based on the average flow rate per pin and peak pin power, were conservative for peak clad surface temperature compared to the bundle results. Also the straight-pin calculations were conservative as compared to the twisted pin simulations, as expected, but the single-pin straight case was not always conservative with regard to the straight-pin bundle. This was due to the straight-pin temperature distribution being strongly influenced by the pin orientation, particularly near the outer boundary. The straight-pin case also predicted the peak temperature to be in a different location than the twisted-pin case. This is a limitation of the straight-pin approach. The peak temperature pin was in a different location from the peak power pin in every case simulated, and occurred at an

  15. Late quaternary stratigraphy and sedimentology of the inner part of southwest Joseph Bonaparte Gulf

    International Nuclear Information System (INIS)

    Clarke, J.D.A.

    2000-01-01

    Joseph Bonaparte Gulf is a large embayment on the northwestern continental margin of Australia. It is approximately 300 km east-west and 120 km north-south with a broad continental shelf to seaward. Maximum width from the southernmost shore of Joseph Bonaparte Gulf to the edge of the continental shelf is 560 km. Several large rivers enter the gulf along its shores. The climate is monsoonal. sub-humid, and cyclone-prone during the December-March wet season. A bedrock high (Sahul Rise) rims the shelf margin. The sediments within the gulf are carbonates to seaward, grading into clastics inshore. A seaward-thinning wedge of highstand muds dominates the sediments of the inner shelf of Joseph Bonaparte Gulf. Mud banks up to 15m thick have developed inshore. Coarse-grained sand ridges up to 15m high are found off the mouth of the Ord River. These overlie an Upper Pleistocene transgressive lag of mixed carbonate and gravelly siliciclastic sand. Four drowned strandlines are present on the inner shelf at depths of 20, 25, 28 and 30 m below datum. These are interpreted as having formed during stillstands in the Late Pleistocene transgression. Older strandlines at great depths are inferred as having formed during the fall in sea-level following the last highstand. For the most part the Upper Pleistocene-Holocene marine sediments overlie an erosion surface cut into older Pleistocene sediments. Incised valleys cut into this erosion surface are up to 5 km wide and have a relief of at least 20 m. The largest valley is that cut by the Ord River. Upper Pleistocene sediments deposited in the incised valleys include interpreted lowstand fluvial gravels, early transgressive channel sands and floodplain silts, and late transgressive estuarine sands and gravels. Spot samples were collected and subjected to 14 C dating, x-ray diffraction and palynological studies. Older Pleistocene sediments are inferred to have been deposited before and during the 120 ka highstand (isotope stage 5). They

  16. A Political Approach of the Popular Credit: Pierre-Joseph Proudhon and the mutual credit

    OpenAIRE

    Cyrille Ferraton; David Vallat

    2011-01-01

    Pierre-Joseph Proudhon’s ideas on credit and money have been considered to be not very relevant and above all unrealistic. However, they have known an uncommon posterity. They influenced Silvio Gesell who is John Maynard Keynes’s reference. This article analyses Pierre-Joseph Proudhon’s exchange bank plan. We show that Pierre- Joseph Proudhon’s ideas on credit and money are opened to criticism but require a reexamination because we can draw many lessons from them.

  17. Reactor Dosimetry Applications Using RAPTOR-M3G:. a New Parallel 3-D Radiation Transport Code

    Science.gov (United States)

    Longoni, Gianluca; Anderson, Stanwood L.

    2009-08-01

    The numerical solution of the Linearized Boltzmann Equation (LBE) via the Discrete Ordinates method (SN) requires extensive computational resources for large 3-D neutron and gamma transport applications due to the concurrent discretization of the angular, spatial, and energy domains. This paper will discuss the development RAPTOR-M3G (RApid Parallel Transport Of Radiation - Multiple 3D Geometries), a new 3-D parallel radiation transport code, and its application to the calculation of ex-vessel neutron dosimetry responses in the cavity of a commercial 2-loop Pressurized Water Reactor (PWR). RAPTOR-M3G is based domain decomposition algorithms, where the spatial and angular domains are allocated and processed on multi-processor computer architectures. As compared to traditional single-processor applications, this approach reduces the computational load as well as the memory requirement per processor, yielding an efficient solution methodology for large 3-D problems. Measured neutron dosimetry responses in the reactor cavity air gap will be compared to the RAPTOR-M3G predictions. This paper is organized as follows: Section 1 discusses the RAPTOR-M3G methodology; Section 2 describes the 2-loop PWR model and the numerical results obtained. Section 3 addresses the parallel performance of the code, and Section 4 concludes this paper with final remarks and future work.

  18. Iodine-123-labeled meta-iodobenzylguanidine myocardial scintigraphy evaluation of Machado-Joseph disease

    International Nuclear Information System (INIS)

    Kazuta, Toshinari; Hayashi, Michiyuki; Yoshita, Mitsuhiro; Hirai, Shunsaku

    1998-01-01

    Iodine-123-labeled meta-iodobenzylguanidine (( 123 I)MIBG), an analogue of guanetidine, is used as a tracer for evaluation of the function of sympathetic neurons. To investigate cardiac sympathetic function in Machado-Joseph disease (MJD), ( 123 I)MIBG myocardial scintigraphy was performed in 12 patients with MJD and 20 controls. In planar imaging studies, the heart to the mediastinum of the average count ratio (H/M) was calculated for both early and delayed images. The mean values of H/M in delayed images of MJD was lower than those of controls (p 123 I)MIBG myocardial scintigraphy in MJD can be seen earlier than abnormal sudomotor system detected by SSR. (author)

  19. Operating characteristic analysis of a 400 mH class HTS DC reactor in connection with a laboratory scale LCC type HVDC system

    Science.gov (United States)

    Kim, Sung-Kyu; Kim, Kwangmin; Park, Minwon; Yu, In-Keun; Lee, Sangjin

    2015-11-01

    High temperature superconducting (HTS) devices are being developed due to their advantages. Most line commutated converter based high voltage direct current (HVDC) transmission systems for long-distance transmission require large inductance of DC reactor; however, generally, copper-based reactors cause a lot of electrical losses during the system operation. This is driving researchers to develop a new type of DC reactor using HTS wire. The authors have developed a 400 mH class HTS DC reactor and a laboratory scale test-bed for line-commutated converter type HVDC system and applied the HTS DC reactor to the HVDC system to investigate their operating characteristics. The 400 mH class HTS DC reactor is designed using a toroid type magnet. The HVDC system is designed in the form of a mono-pole system with thyristor-based 12-pulse power converters. In this paper, the investigation results of the HTS DC reactor in connection with the HVDC system are described. The operating characteristics of the HTS DC reactor are analyzed under various operating conditions of the system. Through the results, applicability of an HTS DC reactor in an HVDC system is discussed in detail.

  20. Internment and ministry: A dialogue with Joseph Kitagawa.

    Science.gov (United States)

    Moss, D M

    1993-09-01

    This dialogue presents a profile of the late Joseph Kitagawa-a renowned scholar of the history of religions (Religionswissenschaft). It focuses on comparative religion and philosophy, as well as several other important issues related to his distinguished career as an Episcopal priest and dean of the Divinity School of the University of Chicago. They are: his experience of American concentration camps during World War II; Christian atheism and new theological models; concepts of time in Oriental and Occidental faiths; depth-psychology and contemporary ministry; and Paul Tillich's significance for the pastoral counseling movement.

  1. Researcher Profile: An Interview with Joseph Goetz, Ph.D.

    Directory of Open Access Journals (Sweden)

    2010-10-01

    Full Text Available Dr. Joseph Goetz is an internationally known researcher working in academia to blend financial planning, financial counseling, and therapy approaches into tools and techniques that enhance the well-being of individuals and families. Dr. Goetz’s work in developing the ASPIRE clinic at the University of Georgia has helped place Georgia at the forefront of financial therapy research. In this interview readers of the Journal can learn more about the exciting work Dr. Goetz is doing to advance the Financial Therapy profession.

  2. Experiment on search for neutron-antineutron oscillations using a projected UCN source at the WWR-M reactor

    Science.gov (United States)

    Fomin, A. K.; Serebrov, A. P.; Zherebtsov, O. M.; Leonova, E. N.; Chaikovskii, M. E.

    2017-01-01

    We propose an experiment on search for neutron-antineutron oscillations based on the storage of ultracold neutrons (UCN) in a material trap. The sensitivity of the experiment mostly depends on the trap size and the amount of UCN in it. In Petersburg Nuclear Physics Institute (PNPI) a high-intensity UCN source is projected at the WWR-M reactor, which must provide UCN density 2-3 orders of magnitude higher than existing sources. The results of simulations of the designed experimental scheme show that the sensitivity can be increased by ˜ 10-40 times compared to sensitivity of previous experiment depending on the model of neutron reflection from walls.

  3. Carl Sagan and Joseph Shklovsky: Intelligent Life in the Universe

    Science.gov (United States)

    Kurt, Vladimir

    J. S. Shklovsky and Carl Sagan played an outstanding role in modern astronomy. Their names are well known not only to professional astronomers, but also to millions of educated people in many countries, which are interested in modern state of science research. Among these trends of modern science, which are difficult to define, are such problems, as the creation of Solar system, the origin of life on Earth, the evolution of living organisms on Earth from the simplest viruses to Homo Sapiens, the evolution of intelligence and technology. Finally, both outstanding scientists were deeply interested in the problem of SETI (Search Extraterrestrial Intelligence), i.e. search of extraterrestrial civilizations and methods of making contacts with them. And both scientists were high professionals in their fields. Joseph Shklovsky was a theoretical astronomer in all fields of modern astronomy (geophysics and physics of the upper atmosphere of the Earth, Sun and Solar Corona, Interplanetary Medium and Solar Wind, Interstellar Medium, Supernova and their remnants, the Galaxy and galaxies, Quasars and Cosmology). There is hardly a field in modern astrophysics (except perhaps the theory of the interior structure of stars), where Joseph Shklovsky has not l a bright stamp of his talent…

  4. Kaiser Franz Joseph I und die Serben 1848–1908

    Directory of Open Access Journals (Sweden)

    Wolfgang Rohrbach

    2017-02-01

    Full Text Available A century from death of Emperor Franz Joseph I (+21.11.1916 triggered a great number of publications about life and almost seven decades long reign of a popular monarch. As the political struggle between Russia, Prussia, Italy and Ottoman Empire are depicted with moderation, Serbia is described unidimensional, with an emphasis on the last decade of Emperors rule. In order to remedy this shortcoming, this contribution is focusing on a period between 1848 and 1908. Today we know much more about relations between Franz Joseph and King Milan Obrenović, as well as with dignitaries of Serbian Orthodox Church, and military, academic and artistic elite. It is, therefore, possible to refute entrenched notions about constant enmity and hostility between Austria and Serbia. In this work, an emphasis is put on cooperation between Austria and Serbia from 1848, when Serbs at Emperors request held a number of important political and military positions, whereas Serbian artists took part in the reconstruction of Imperial Vienna. The university of Vienna hosted the oldest institute for slavistic (1849, becoming, therefore, a crossroad of the cultural and social development of the Balkans.

  5. Excitation of 107m,109mAg isomeric states in the inelastic scattering of fast neutrons from the IBR-2 reactor of JINR

    International Nuclear Information System (INIS)

    Alpatov, V. G.; Borzakov, S. B.; Davydov, A. V.; Isaev, Yu. N.; Kartashov, G. R.; Korotkov, M. M.; Nazarov, V. M.; Pavlov, S. S.; Peresedov, V. F.; Rad'ko, V. E.; Samoylov, V. M.; Chinaeva, V. P.

    1997-01-01

    The cross sections for the excitation of long-lived isomers of 107,109 Ag nuclei are measured in the inelastic scattering of fast neutrons from the IBR-2 reactor of JINR (Dubna). The measurements are performed by means of comparison with the yield of the 103m Rh isomer, for which the excitation cross sections are known over a wide energy range for similar reactions induced by monochromatic neutrons. The measured cross sections proved to be σ( 107m Ag)=204±18 mb and σ( 109m Ag)=262±26 mb. These values are significantly smaller than the cross section for the excitation of the 103m Rh isomer. An analysis employing information about the arrangement of energy levels in Rh and Ag and about transitions between these levels, as well as data on the spectra of γ rays emitted in (n,n'γ) reactions, reveals that the distinction between the cross sections for the excitation of Rh and Ag isomers can be explained by the difference in the population of corresponding levels of Rh and Ag nuclei

  6. Joseph Campbell, Jung, Anne Tyler, and "The Cards": The Spiritual Journey in "Searching for Caleb."

    Science.gov (United States)

    Thomson, Karen M.

    Joseph Campbell, Carl Jung, and Anne Tyler have all dealt with spiritual journeys and card reading in their writings. In his book "Tarot Revelations," Joseph Campbell discusses his first association with tarot cards, dating from 1943, when he was introduced to the symoblism of playing cards by his friend and mentor, Heinrich Zimmer. Carl…

  7. Prototypic Enhanced Risk Monitor Framework and Evaluation - Advanced Reactor Technology Milestone: M3AT-15PN2301054

    Energy Technology Data Exchange (ETDEWEB)

    Ramuhalli, Pradeep [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hirt, Evelyn H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Veeramany, Arun [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bonebrake, Christopher A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ivans, William J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Coles, Garill A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Coble, Jamie B. [Univ. of Tennessee, Knoxville, TN (United States); Liu, X. [Univ. of Tennessee, Knoxville, TN (United States); Wootan, David W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mitchell, Mark R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Brass, Mary F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-09-24

    This research report summaries the development and evaluation of a prototypic enhanced risk monitor (ERM) methodology (framework) that includes alternative risk metrics and uncertainty analysis. This updated ERM methodology accounts for uncertainty in the equipment condition assessment (ECA), the prognostic result, and the probabilistic risk assessment (PRA) model. It is anticipated that the ability to characterize uncertainty in the estimated risk and update the risk estimates in real time based on equipment condition assessment (ECA) will provide a mechanism for optimizing plant performance while staying within specified safety margins. These results (based on impacting active component O&M using real-time equipment condition information) are a step towards ERMs that, if integrated with AR supervisory plant control systems, can help control O&M costs and improve affordability of advanced reactors.

  8. Response of the St. Joseph River to lake level changes during the last 12,000 years in the Lake Michigan basin

    Science.gov (United States)

    Kincare, K.A.

    2007-01-01

    The water level of the Lake Michigan basin is currently 177 m above sea level. Around 9,800 14C years B.P., the lake level in the Lake Michigan basin had dropped to its lowest level in prehistory, about 70 m above sea level. This low level (Lake Chippewa) had profound effects on the rivers flowing directly into the basin. Recent studies of the St. Joseph River indicate that the extreme low lake level rejuvenated the river, causing massive incision of up to 43 m in a valley no more than 1.6 km wide. The incision is seen 25 km upstream of the present shoreline. As lake level rose from the Chippewa low, the St. Joseph River lost competence and its estuary migrated back upstream. Floodplain and channel sediments partially refilled the recently excavated valley leaving a distinctly non-classical morphology of steep sides with a broad, flat bottom. The valley walls of the lower St. Joseph River are 12-18 m tall and borings reveal up to 30 m of infill sediment below the modern floodplain. About 3 ?? 108 m3 of sediment was removed from the St. Joseph River valley during the Chippewa phase lowstand, a massive volume, some of which likely resides in a lowstand delta approximately 30 km off-shore in Lake Michigan. The active floodplain below Niles, Michigan, is inset into an upper terrace and delta graded to the Calumet level (189 m) of Lake Chicago. In the lower portion of the terrace stratigraphy a 1.5-2.0 m thick section of clast-supported gravel marks the entry of the main St. Joseph River drainage above South Bend, Indiana, into the Lake Michigan basin. This gravel layer represents the consolidation of drainage that probably occurred during final melting out of ice-marginal kettle chains allowing stream piracy to proceed between Niles and South Bend. It is unlikely that the St. Joseph River is palimpsest upon a bedrock valley. The landform it cuts across is a glaciofluvial-deltaic feature rather than a classic unsorted moraine that would drape over pre-glacial topography

  9. Economic significance of Q for mirror reactors: combinations of Q and M which look promising

    International Nuclear Information System (INIS)

    Werner, R.W.

    1978-01-01

    This term Q is the ratio of the fusion powder produced to the power input. It is a driven device. Q is truly the success parameter for mirrors--widely discussed but not succinctly specified as to required value. The problem is that Q can be treated as a subjective parameter--there are many milestone Qs; for scientific demonstration, for breakeven power, etc. Yet for a successful reactor, there is only one Q and that is the Q which produces mirror fusion power at the busbar that is less than the cost of delivered power in mills/kwhr by other means. We call this Q/sub PRACTICAL/ and believe there is a convincing argument that says this Q/sub PRACTICAL/ can be about 5.0 even assuming modest efficiencies for system components. A direct convertor is necessary. If the direct convertor were deleted, a Q/sub PRACTICAL/ of approximately 7.5 would be required. If we wish to soften the value of Q further, then the technical logic for the fusion fission hybrid is very powerful. With the hybrid a Q/sub PRACTICAL/ of 1.5 to 2.0 appears to be a very reasonable value. The key in being able to specify values of Q/sub PRACTICAL/ lies in economically comparing the capital cost of fusion power to the sum of the capital cost and the present value of all the fuel costs for the competitive fuel intensive plants

  10. Implementation of reactor safety analysis code CATHARE and its use on FACOM M-380

    International Nuclear Information System (INIS)

    Ishiguro, Misako; Shinozawa, Naohisa; Tomiyama, Mineyoshi; Fujisaki, Masahide

    1986-05-01

    CATHARE is an advanced safety analysis code developed at the Nuclear Research Center of Grenoble in France. The code simulates thermohydraulic phenomena involved in loss of coolant accidents in pressurized water reactors. The code has been introduced into JAERI as a part of the technical exchange between the JAERI ROSA-IV Program and the French BETHSY-CATHARE Program. The code was delivered in the form of 23 files containing 115,000 statements in total. A large part of CATHARE code has been written in an extended Fortran language 'Esope' which is mainly used for managing dynamic memory allocation. The JAERI version is created from the IBM version which has been used on Amdhal computer at ISPRA. Some modifications are required in order to implement the CATHARE code at JAERI because of difference in softwares. In this report, the overview of the code structure, the JAERI usage, the implementation method, the error correction method, the problems special to install the code in JAERI, and the distribution of computing time are described. (author)

  11. Application programming interface document for the modernized Transient Reactor Analysis Code (TRAC-M)

    International Nuclear Information System (INIS)

    Mahaffy, J.; Boyack, B.E.; Steinke, R.G.

    1998-05-01

    The objective of this document is to ease the task of adding new system components to the Transient Reactor Analysis Code (TRAC) or altering old ones. Sufficient information is provided to permit replacement or modification of physical models and correlations. Within TRAC, information is passed at two levels. At the upper level, information is passed by system-wide and component-specific data modules at and above the level of component subroutines. At the lower level, information is passed through a combination of module-based data structures and argument lists. This document describes the basic mechanics involved in the flow of information within the code. The discussion of interfaces in the body of this document has been kept to a general level to highlight key considerations. The appendices cover instructions for obtaining a detailed list of variables used to communicate in each subprogram, definitions and locations of key variables, and proposed improvements to intercomponent interfaces that are not available in the first level of code modernization

  12. From Exile to Affirmation: The Poetry of Joseph Brodsky

    Directory of Open Access Journals (Sweden)

    David Patterson

    1993-06-01

    Full Text Available This article examines the relation between the exile of the poet from his homeland and the "exile of the word." The notion of the exile of the word pertains to the poet's problem of re-introducing meaning to the word—an excess of meaning that conveys more than the word can normally convey—through his poetry. Showing how the poet in exile becomes a poet of exile, the article examines what poetry has to do with a larger difficulty of exile and homelessness in human life. Brodsky's poetry, the article argues, addresses this very difficulty. The article concludes that the human capacity to dwell in the world is a capacity to instill the word with meaning, and that this is one important message to come to us through the poetry of Joseph Brodsky.

  13. Joseph Rotblat: Moral Dilemmas and the Manhattan Project

    Science.gov (United States)

    Veys, Lucy

    2013-12-01

    John Fitzgerald Kennedy famously said, "One man can make a difference and every man should try."1 Joseph Rotblat (1908-2005) was the quintessence of Kennedy's conviction. He was the only scientist who left Los Alamos after it transpired that the atomic bomb being developed there was intended for use against adversaries other than Nazi Germany. I explore Rotblat's early research in Warsaw and Liverpool, which established his reputation as a highly capable experimental physicist, and which led him to join the Manhattan Project at Los Alamos in 1944. I examine his motivation for resigning from the project in 1945, and the unwillingness of his fellow scientists to follow suit, which draws attention to the continuing discourse on the responsibility of scientists for the consequences of their research.

  14. Comments on the Poem “Architecture” by Joseph Brodsky

    Directory of Open Access Journals (Sweden)

    Konstantin Lidin

    2016-11-01

    Full Text Available The poem “Architecture” by Joseph Brodsky was commented on by Alexander Rappaport, Konstantin Lidin and Elena Bagina. The poem deserves to be studied at all architectural schools and to be learnt by heart by future architects; and the problems touched upon in this poem deserve to be thought about by architectural theorists. This poem is a quintessence of the contemporary theoretical thought about architecture. It raises such themes as time and memory, space, place and substance. It also speaks about ideal geometric shapes in architecture and dynamics of architectural forms. Architectural works are “a step beyond the drawing”, an unbreakable link of times. The domes of architectural masterpieces form a safety parachute of our civilization. Alexander Rappaport, Konstantin Lidin and Elena Bagina made a comment on each line of this short but remarkably concise, lofty and ironical work by Joseph Brodsky. These comments partially coincide and partially differ. You may either agree or argue with the authors’ opinion. But any meaningful talk about the place and the role of architecture and architectural profession in the present-day world is of importance. It is symptomatic that the modern architectural studies are focused on the history of architecture, being afraid (or unwilling due to a complex and controversial situation in today’s profession to deal with urgent and difficult problems. Wherever the architectural theory of the late 20th century looked for fertility drugs, be it in mathematics, semiotics, sociology, linguistics, it was in vain. In the early 21st century it came to the crossroads. It is no good to verify the death of architecture, because it would mean, according to Brodsky, the end of civilization. Let’s believe that architecture has its future and that it will remain “a thing of stone”, the strongest material on Earth.

  15. Status of prompt gamma neutron activation analysis (PGAA) at TRR-1/M1 (Thai Research Reactor-1/Modified 1)

    Energy Technology Data Exchange (ETDEWEB)

    Asvavijnijkulchai, Chanchai; Dharmavanij, Wanchai; Siangsanan, Pariwat; Ratanathongchai, Wichian; Chongkum, Somporn [Physics Division, Office of Atomic Energy for Peace, Vibhavadi Rangsit Road, Chatuchak, Bangkok (Thailand)

    1999-08-01

    The first prompt gamma activation analysis (PGAA) was designed, constructed and installed at a 6 inch diameter neutron beam port of the Thai Research Reactor-1/Modified 1 (TRR-1/M1) since 1989. Beam characteristic were made by Gd foil irradiation, X-ray film exposing and densitometry scanning consequently. The thermal neutron flux at sample position was measured by Au foil activation, and was about 1 x 10{sup 7} n.cm{sup 2}.sec{sup -1} at 700 kW operating power. The experiments have been conducted successfully. In 1998, the PGAA facility has been developed for the reactor operating power at 1.2 MW. The new PGAA system, e.g., beam shutter, gamma collimator and biological shields have been designed to reduce the leakage of neutrons and gamma radiation to the acceptance levels in accordance with the International Commission on Radiation Protection Publication 60 (ICRP 60). The construction and installation will be completed in April 1999. (author)

  16. The pyrolytic decomposition of o-, m-, and p-terphenyls and other potential reactor coolants

    Energy Technology Data Exchange (ETDEWEB)

    Juppe, G.; Hannaert, H.; Biver, F.

    1963-03-15

    Experiments were made on the pyrolytic decomposition of o-, m-, and p- terphenyls and mixtures of terphenyls with diphenyl. The effects of competing reactions were also studied by initially adding hydrogen, methane, ethane, propane, and benzene. The results indicate that the disappearance of o-, m-, and p-terphenyl seems to follow formally a first order reaction mechanism. The relative stability of the pure individual components increases in the order: oterphenyl (least stable), p-terphenyl, m-terphenyl (most stable). The activation energy was found to be in the neighborhood of 64 kcal/mole. The activation energy for the diphenyl formation during pyrolysis of an irradiated biphenyl-terphenyl mixture was found to be 47.9 kcal/mole. (P.C.H.)

  17. Joseph Jacobs: Apprentice to Crawford W. Long in Athens, GA; Pharmacist and Retailer of Soda Fountain Beverages in Atlanta, GA.

    Science.gov (United States)

    Haridas, Rajesh P

    2018-01-01

    In the 1870s, Joseph Jacobs was employed as an apprentice in the Longs and Billups pharmacy in Athens, GA. Jacobs later established a chain of pharmacies in Atlanta, GA. Coca-Cola was first sold to the public on May 8, 1886, at Jacobs' Pharmacy in the Five Points district of Atlanta, GA. The soda fountain in Jacobs' Pharmacy was owned by Willis E. Venable, who was related to James M. Venable, the first patient etherized by Crawford Long in Jefferson, GA. Copyright © 2018 Elsevier Inc. All rights reserved.

  18. Development of an emergency core cooling system for the converted IEA-R1m research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Torres, Walmir Maximo; Baptista Filho, Benedito Dias; Ting, Daniel Kao Sun [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil). Dept. de Tecnologia de Reatores]. E-mail: wmtorres@net.ipen.br; bdbfilho@net.ipen.br; dksting@net.ipen.br

    1998-07-01

    This present work describes the development program carried out in the design and construction of the Emergency Core Cooling System for the IEA-R1m Research Reactor, including the system design, the experiments performed to validate the design, manufacturing, installation and commissioning. The experiments were performed in two phases. In the first phase, the spray flow rate and distribution were measured, using a full scale mock-up of the entire core, to establish the spray header geometry and specifications. In the second phase, a test section was fitted with electrically heated plates to simulate the fuel plates. Temperature measurements were carried out to demonstrate the effectiveness of the system to keep the temperatures below the limiting value. The experimental results were shown to the licensing authorities during the certification process. The main difficulties during the system assembly are also described. (author)

  19. Taipower plans to cut O and M costs [reactor maintenance management

    International Nuclear Information System (INIS)

    Tsui, S.J.

    1989-01-01

    Taipower aims to reduce operation and maintenance costs at its three BWRs, as well as the time devoted by plant personnel to O and M paper work, by ensuring that maintenance and spare-parts management is systematic and well documented. It is currently developing an on-line maintenance information system, known as the Maintenance Management Computerization System (MMCS), which can be accessed from any of Taipower's plants. MMCS is designed to be an on-line interactive multiple-user system through which the authorized user has immediate access to maintenance information. It will be used for preventive and corrective maintenance, surveillance tests, tagging, document control, instrument calibration and refuelling outage management. The system is simple to operate, using pull-down menus and standard text. (author)

  20. Preliminary validation of computational model for neutron flux prediction of Thai Research Reactor (TRR-1/M1)

    Science.gov (United States)

    Sabaibang, S.; Lekchaum, S.; Tipayakul, C.

    2015-05-01

    This study is a part of an on-going work to develop a computational model of Thai Research Reactor (TRR-1/M1) which is capable of accurately predicting the neutron flux level and spectrum. The computational model was created by MCNPX program and the CT (Central Thimble) in-core irradiation facility was selected as the location for validation. The comparison was performed with the typical flux measurement method routinely practiced at TRR-1/M1, that is, the foil activation technique. In this technique, gold foil is irradiated for a certain period of time and the activity of the irradiated target is measured to derive the thermal neutron flux. Additionally, the flux measurement with SPND (self-powered neutron detector) was also performed for comparison. The thermal neutron flux from the MCNPX simulation was found to be 1.79×1013 neutron/cm2s while that from the foil activation measurement was 4.68×1013 neutron/cm2s. On the other hand, the thermal neutron flux from the measurement using SPND was 2.47×1013 neutron/cm2s. An assessment of the differences among the three methods was done. The difference of the MCNPX with the foil activation technique was found to be 67.8% and the difference of the MCNPX with the SPND was found to be 27.8%.

  1. 2016 Inspection and Annual Site Status Report for the Site A/Plot M, Illinois, Decommissioned Reactor Site July 2016

    Energy Technology Data Exchange (ETDEWEB)

    Murl, Jeffrey [USDOE Office of Legacy Management, Washington, DC (United States); Miller, Michele [Navarro Research and Engineering, Oak Ridge, TN (United States)

    2016-07-01

    The Site A/Plot M, Illinois, Decommissioned Reactor Site was inspected on May 17, 2016. The site, located within Cook County forest preserve that is open to the public, was found to be in good condition with one exception. Erosion on top of the grass-covered mound at Plot M continues to be a concern as presented in previous inspections. Ruts form in the soil on top of Plot M as a result of bike traffic using the open field as a pass thru between established bike trails within the forest preserve. Argonne National Laboratory (ANL) who is contracted directly from U.S. Department of Energy (DOE) has filled in the ruts with top soil and reseeding remains an ongoing process. Reseeded areas from 2015 are progressing nicely. No cause for a follow-up inspection was identified. In 2015, ANL plugged and abandoned 8 of 25 monitoring wells (BH41, BH51, BH52, BH54, DH9, DH10, DH13, and DH17). The 17 groundwater monitoring wells remaining at the site were inspected to confirm that they were locked and in good condition. Preliminary environmental monitoring results for 2015 are provided in a draft report titled Surveillance of Site A and Plot M, Report for 2015, prepared by ANL. The report also contains results of an independent analysis conducted by the Illinois Emergency Management Agency on some of the samples collected by ANL in 2015. The draft report states that the results of the surveillance program continue to indicate that the impact of radioactivity at Site A/Plot M is very low and does not endanger the health of those living in the area or visiting the site. The ANL monitoring report will be made available to the public on the DOE Office of Legacy Management public website when it is issued as final. A new county forest preserve campsite opened in 2015 at Bull Frog Lake, which is east of Plot M. Hiking trails connect Bull Frog Lake with Site A/Plot M. The site might receive more traffic from forest preserve visitors now that this new campsite is opened.

  2. Joseph and Michael Haydn in the Bohemian music archives. An anniversary tribute

    Czech Academy of Sciences Publication Activity Database

    Freemanová, Michaela

    2012-01-01

    Roč. 20, č. 1 (2012), s. 117-126. ISBN 978-3-486-58949-8. ISSN 1865-5696 Institutional support: RVO:68378076 Keywords : Joseph Haydn * Michael Haydn * music archives Subject RIV: AL - Art, Architecture, Cultural Heritage

  3. Reason, Science, Criticism. Joseph Agassi interviewed on his 90th birthday by Zuzana Parusniková

    Czech Academy of Sciences Publication Activity Database

    Parusniková, Zuzana; Agassi, J.

    2017-01-01

    Roč. 24, č. 4 (2017), s. 526-545 ISSN 1335-0668 Institutional support: RVO:67985955 Keywords : Joseph Agassi * interview Subject RIV: AA - Philosophy ; Religion http://klemens.sav.sk/fiusav/organon/?q=sk/reason- science -criticism

  4. “Migrant Women Are Always Added”: In Conversation with Ebun Joseph Akpoveta

    Directory of Open Access Journals (Sweden)

    Asier Altuna-García de Salazar

    2017-03-01

    Ebun Joseph Akpoveta lives in Dublin with her beloved family. I would like to thank her for her patience and kindness in collaborating to expand and finalise the present written version of her interview through e-mail.

  5. Yue Joseph Wang named Grant A. Dove Professor of Electrical and Computer Engineering

    OpenAIRE

    Owczarski, Mark

    2009-01-01

    Yue Joseph Wang, professor of electrical and computer engineering in the College of Engineering at Virginia Tech, has been named the Grant A. Dove Professor of Electrical and Computer Engineering by the Virginia Tech Board of Visitors.

  6. Franz Joseph Gall and music: the faculty and the bump.

    Science.gov (United States)

    Eling, Paul; Finger, Stanley; Whitaker, Harry

    2015-01-01

    The traditional story maintains that Franz Joseph Gall's (1758-1828) scientific program began with his observations of schoolmates with bulging eyes and good verbal memories. But his search to understand human nature, in particular individual differences in capacities, passions, and tendencies, can also be traced to other important observations, one being of a young girl with an exceptional talent for music. Rejecting contemporary notions of cognition, Gall concluded that behavior results from the interaction of a limited set of basic faculties, each with its own processes for perception and memory, each with its own territory in both cerebral or cerebellar cortices. Gall identified 27 faculties, one being the sense of tone relations or music. The description of the latter is identical in both his Anatomie et Physiologie and Sur les Fonctions du Cerveau et sur Celles de Chacune de ses Parties, where he provided positive and negative evidences and discussed findings from humans and lower animals, for the faculty. The localization of the cortical faculty for talented musicians, he explained, is demonstrated by a "bump" on each side of the skull just above the angle of the eye; hence, the lower forehead of musicians is broader or squarer than in other individuals. Additionally, differences between singing and nonsinging birds also correlate with cranial features. Gall even brought age, racial, and national differences into the picture. What he wrote about music reveals much about his science and creative thinking. © 2015 Elsevier B.V. All rights reserved.

  7. Moths on the Flatbed Scanner: The Art of Joseph Scheer

    Directory of Open Access Journals (Sweden)

    Stephen L. Buchmann

    2011-12-01

    Full Text Available During the past decade a few artists and even fewer entomologists discovered flatbed scanning technology, using extreme resolution graphical arts scanners for acquiring high magnification digital images of plants, animals and inanimate objects. They are not just for trip receipts anymore. The special attributes of certain scanners, to image thick objects is discussed along with the technical features of the scanners including magnification, color depth and shadow detail. The work of pioneering scanner artist, Joseph Scheer from New York’s Alfred University is highlighted. Representative flatbed-scanned images of moths are illustrated along with techniques to produce them. Collecting and preparing moths, and other objects, for scanning are described. Highlights of the Fulbright sabbatical year of professor Scheer in Arizona and Sonora, Mexico are presented, along with comments on moths in science, folklore, art and pop culture. The use of flatbed scanners is offered as a relatively new method for visualizing small objects while acquiring large files for creating archival inkjet prints for display and sale.

  8. Joseph Rotblat a man of conscience in the nuclear age

    CERN Document Server

    Underwood, Martin

    2009-01-01

    Professor Sir Joseph Rotblat was a distinguished scientist who made a significant contribution to nuclear physics, worked on the development of the atomic bomb (he was the only person to leave the Manhattan Project), and was suspected of being a Soviet spy. After Hiroshima and Nagasaki he became a peace campaigner and dedicated himself to the medical uses of nuclear physics and radiation.He took up the post of Professor of Physics (as applied to medicine) at St. Bartholomew's Medical College and made major contributions to this field, becoming one of the world's leading researchers into the biological effects of radiation. … His life from the early 1950s until his death in August 2005 was devoted to the abolition of nuclear weapons and the promotion of world peace. His work ranked with that of Albert Einstein and Bertrand Russell. He helped found The Pugwash Conferences on Science and World Affairs, and together with Pugwash he was awarded the Nobel Peace Prize in 1995. Rotblat promoted dialogue between Sov...

  9. Electrical Enlightenment: Joseph Priestley's Historical and Experimental Studies of Electricity

    Science.gov (United States)

    Boantza, Victor

    Joseph Priestley (1733-1804) was one of the most controversial public figures of the eighteenth century. A true Enlightenment polymath, he wrote more than two hundred books, pamphlets, sermons, and essays on subjects ranging from science to politics and from metaphysics to theology. He was a religious dissenter, political radical, vocal supporter of the French Revolution, and lifelong defender of the losing side in the Chemical Revolution. Priestley is best known for having ``discovered'' oxygen in the 1770s and for his lasting contributions to pneumatic chemistry. Yet his first scientific fascination, while teaching at Warrington Academy, was electricity--one of the greatest scientific fads of the Enlightenment. Priestley's work on electricity, both historical and experimental, culminated in his History and Present State of Electricity (1767), which became a standard textbook on the subject for nearly a century, and went through numerous editions and translations. Situating Priestley's electrical investigations against the background of eighteenth-century ideals of scientific theory and practice, especially concerning physics, experimental philosophy, and natural history, illuminates the relations between science, society, and epistemology in the Enlightenment.

  10. May Joseph,Fluid New York: Cosmopolitan Urbanism and the Green Imagination

    OpenAIRE

    Marche, Guillaume

    2015-01-01

    In Fluid New York: Cosmopolitan Urbanism and the Green Imagination, May Joseph, a social science and cultural studies scholar, explores the history, experience, representations, and political implications of New York City’s relation to its natural environment, especially its aquatic surroundings –be they rivers, harbor or ocean. Of particular interest to Joseph, and the reader, is New York’s status as an archipelagic metropolis. While the book does not purport to provide a straightforward his...

  11. Machado-Joseph disease in pedigrees of Azorean descent is linked to chromosome 14.

    Science.gov (United States)

    St George-Hyslop, P; Rogaeva, E; Huterer, J; Tsuda, T; Santos, J; Haines, J L; Schlumpf, K; Rogaev, E I; Liang, Y; McLachlan, D R

    1994-07-01

    A locus for Machado-Joseph disease (MJD) has recently been mapped to a 30-cM region of chromosome 14q in five pedigrees of Japanese descent. MJD is a clinically pleomorphic neurodegenerative disease that was originally described in subjects of Azorean descent. In light of the nonallelic heterogeneity in other inherited spinocerebellar ataxias, we were interested to determine if the MJD phenotype in Japanese and Azorean pedigrees arose from mutations at the same locus. We provide evidence that MJD in five pedigrees of Azorean descent is also linked to chromosome 14q in an 18-cM region between the markers D14S67 and AACT (multipoint lod score +7.00 near D14S81). We also report molecular evidence for homozygosity at the MJD locus in an MJD-affected subject with severe, early-onset symptoms. These observations confirm the initial report of linkage of MJD to chromosome 14; suggest that MJD in Japanese and Azorean subjects may represent allelic or identical mutations at the same locus; and provide one possible explanation (MJD gene dosage) for the observed phenotypic heterogeneity in this disease.

  12. Results of VVER fuel rods tests in the MIR.M1 reactor under power cycling conditions

    International Nuclear Information System (INIS)

    Burukin, A.; Izhutov, A.; Ovchinnikov, V.; Kalygin, V.; Markov, D.; Pimenov, Y.; Novikov, V.; Medvedev, A.; Nesterov, B.

    2011-01-01

    The paper presents the main results of the 50 ... 60 MWd/kgU burnup VVER fuel rods tests performed in the MIR.M1 reactor loop facilities under power cycling. The non-destructive PIE results are presented as well. A series of experiments was performed, including overall measurement of fuel rod parameters test, in one of which 300 cycles were done. Irradiation under power cycling conditions and PIE of high-burnup VVER fuel rods showed the following: 1) all fuel rods claddings preserved their integrity under irradiation at linear heat rate (LHR) higher than the NPP operating one; 2) experimental data were obtained on the axial and radial cladding strain and fission gas release (FGR) from 50 ... 60 MWd/kgU burnup VVER-440 and VVER-1000 fuel rods as well as on the kinetics of the change in these parameters and fuel temperature under the power cycling; 3) non-destructive PIE results are in a satisfactory correlation with the data obtained by means of in-pile measurement gages during irradiation. (authors)

  13. The Chief Joseph Hatchery Program 2013 Annual Report

    Science.gov (United States)

    Baldwin, Casey; Pearl, Andrea; Laramie, Matthew; Rohrback, John; Phillips, Pat; Wolf, Keith

    2016-01-01

    The Chief Joseph Hatchery is the fourth hatchery obligated under the Grand Coulee Dam/Dry Falls project, originating in the 1940s. Leavenworth, Entiat, and Winthrop National Fish Hatcheries were built and operated as mitigation for salmon blockage at Grand Coulee Dam, but the fourth hatchery was not built, and the obligation was nearly forgotten. After the Colville Tribes successfully collaborated with the United States to resurrect the project, planning of the hatchery began in 2001 and construction was completed in 2013. The monitoring program began in 2012 and adult Chinook Salmon were brought on station for the first time in June 2013. BPA is the primary funding source for CJH, and the Mid-Columbia PUDs (Douglas, Grant and Chelan County) have entered into cost-share agreements with the tribes and BPA in order to meet some of their mitigation obligations. The CJH production level was set at 60% in 2013 in order to train staff and test hatchery facility systems during the first year of operation. Leavenworth National Fish Hatchery (LNFH) provided 422 Spring Chinook broodstock in June, 2013; representing the official beginning of CJH operations. In July and August the CCT used a purse seine vessel to collect 814 summer/fall Chinook as broodstock that were a continuation and expansion of the previous Similkameen Pond program. In-hatchery survival for most life stages exceeded survival targets and, as of April 2014, the program was on track to exceed the 60% production target for its start-up year. The CJH monitoring project collected field data to determine Chinook population status, trend, and hatchery effectiveness centered on five major activities; 1) rotary screw traps (juvenile outmigration, natural-origin smolt PIT tagging) 2) beach seine (naturalorigin smolt PIT tagging) 3) lower Okanogan adult fish pilot weir (adult escapement, proportion of hatchery-origin spawners [pHOS], broodstock) 4) spawning ground surveys (redd and carcass surveys)(viable salmonid

  14. Research reactors

    International Nuclear Information System (INIS)

    Kowarski, L.

    1955-01-01

    type of reactors: low power reactors, graphite and natural uranium reactors, heavy water and natural uranium reactors (with water, gas or heavy water as coolant), heavy water and enriched uranium reactors, 'kettle' type reactors, pool type reactors and high power reactors. Finally, additional factors are considered as the correlation of the reactor type with the research program, safety considerations, size of the construction and economical considerations. (M.P.)

  15. A comparison of rat SPECT images obtained using 99mTc derived from 99Mo produced by an electron accelerator with that from a reactor

    International Nuclear Information System (INIS)

    Galea, R; Ross, C K; Moore, K; Wells, R G; Lockwood, J; Harvey, J T; Isensee, G H

    2013-01-01

    Recent shortages of molybdenum-99 ( 99 Mo) have led to an examination of alternate production methods that could contribute to a more robust supply. An electron accelerator and the photoneutron reaction were used to produce 99 Mo from which technetium-99m ( 99m Tc) is extracted. SPECT images of rat anatomy obtained using the accelerator-produced 99m Tc with those obtained using 99m Tc from a commercial generator were compared. Disks of 100 Mo were irradiated with x-rays produced by a 35 MeV electron beam to generate about 1110 MBq (30 mCi) of 99 Mo per disk. After target dissolution, a NorthStar ARSII unit was used to separate the 99m Tc, which was subsequently used to tag pharmaceuticals suitable for cardiac and bone imaging. SPECT images were acquired for three rats and compared to images for the same three rats obtained using 99m Tc from a standard reactor 99 Mo generator. The efficiency of 99 Mo– 99m Tc separation was typically greater than 90%. This study demonstrated the delivery of 99m Tc from the end of beam to the end user of approximately 30 h. Images obtained using the heart and bone scanning agents using reactor and linac-produced 99m Tc were comparable. High-power electron accelerators are an attractive option for producing 99 Mo on a national scale. (paper)

  16. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

    The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

  17. Calculational investigations and analysis of characteristics of research reactor WWR-M as a source of neutrons for solution of scientific and applied tasks

    International Nuclear Information System (INIS)

    Vorona, P.M.; Razbudej, V.F.

    2010-01-01

    Calculational studies and analysis of the neutron fields of WWR-M research reactor of the Institute for Nuclear Research, National Academy of Sciences of Ukraine, as a basic nuclear facility for performing the fundamental and applied investigations and for experimentalindustrial production of radioisotope products for various spheres of application are carried out. The calculations are carried out by the method of statistic tests (Monte Carlo) applying the computer program MCNP-4C. The data on the spectra and the neutron flux density values at the 10 MW reactor power for all technological facilities designed for the works with neutrons: 19 vertical experimental channels for irradiation of specimens and 10 horizontal channels for beams extraction from the reactor are obtained. The effect of the neutron traps (water cavities) mounted in the core on the characteristics of the extracted from the reactor beams is demonstrated. Recommendations associated with optimization of the reactor core are adduced for amplification of its capabilities as a neutron source in experimental researches.

  18. Joseph Smith's tritheism : the prophet's theology in context, critiqued from a Nicene perspective / Keith Dayton Hartman II

    OpenAIRE

    Hartman, Keith Dayton

    2013-01-01

    Joseph Smith is one of the most enigmatic figures in American religious history. From the details of his life story to the eventual formation of his own church, much has been written on the legacy of Joseph Smith. However, there are still numerous areas of Smith’s life and thought that demand further engagement, especially from a Nicene perspective. The purpose of the present research is to substantively add to scholarly knowledge regarding Joseph Smith. In contradistinction...

  19. Home brew technetium : clinical scale desktop plasma fusion neutron source to produce Tc99m as an alternative to industrial scale fission reactor sources

    International Nuclear Information System (INIS)

    Bosi, S.G.; Khachan, J.; Oborn, B.M.

    2011-01-01

    Full text: Tc-99m (decay product of Mo-99) accounts for ∼ 90% of world's production of radiopharmaceuticals. Recent unexpected shutdowns of two fission reactors and routine maintenance closures .e created a global shortage of Tc-99m, hence the large global effort to find alternative sources. This project aims to design and produce a novel prototype Mo-99/Tc-99m source. An operational desktop neutron source is available at the University of Sydney, employing a deuterium fusion-plasma to create 2.45 MeV neutrons. These neutrons will be used to activate Mo-98 thin an activation vessel. In one embodiment, the activation vessel contains an aqueous slurry or gel containing Mo-98 which converts to 0-99 upon activation. The decay product Tc-99m could then be milked, similar to existing Tc-99m generators. Monte Carlo will be :ed to assess yield versus size and geometry for various vessel designs. The neutron source filled with deuterium operating at 250 W, produces 3 x 106 neutrons continuously. The neutron flux can be increased ∼ 100-fold if the fill gas is 50% tritium and by another ∼ 100-1000-fold by increasing the power. This is being designed for local use, perhaps on the scale f one or a few hospitals, so the yield would not need to be industrial ;ale as with fission reactor sources. This device is low cost <$300 K) compared with cyclotrons and fission reactors.

  20. Saint Joseph's University Institute for Environmental Stewardship

    Energy Technology Data Exchange (ETDEWEB)

    McCann, Micahel P. [Saint Joseph' s Univ., Philadelphia, PA (United States); Springer, Clint J. [Saint Joseph' s Univ., Philadelphia, PA (United States)

    2014-06-03

    future climate scenarios is local adaptation and not necessarily genome size as has been hypothesized in the literature. Task B: Installation of an extensive green roof system on the Science Center at Saint Joseph's University for research, research-training and educational outreach activities. An experimental green roof system was designed and installed by an outside contractor (Roofmeadows) on the roof of the Science Center at Saint Joseph's University. The roof system includes four test plots, each with a different drainage system, instrumentation to monitor storm water retention, roof deck temperature, heat flux into and out of the building, rain fall, wind speed and direction, relative humidity and heat emission from the roof system. The vegetative roof was planted with 26 species of plants, distributed throughout the roof area, to assess species/variety growth and coverage characteristics, both in terms of the different drain layer systems, and in terms of the different exposures along the north to south axis of the building. Analysis of the drain layer performance, in terms of storm water retention, shows that the aggregate (stone) drainage layer system performed the best, with the moisture management mat system second, and the geotextile drain layer and reservoir sheet layer systems coming in last. This information is of value in the planning and design of vegetative roof systems since the different types of drainage layer systems have different installation costs and different weights. The different drainage layer systems also seem to be having an impact on plant growth and spread with the test plot with the reservoir sheet layer actually having the poorest plant coverage and plant spread of all areas of the roof studied. Plant growth performance analysis is ongoing, but significant differences have been observed in the third growing season ('13) along the north to south axis, with most species doing better towards the northern end of the roof (in

  1. Vanameelne mähib ennast riigilippu / Jaan Ruus

    Index Scriptorium Estoniae

    Ruus, Jaan, 1938-2017

    2008-01-01

    George Clooney mängufilm "Head õhtut ja õnn kaasa" ("Good Night, and Good Luck") teleajakirjanik Edward R. Murrow võitlusest senaator Joseph McCarthy vastu (Ameerika Ühendriigid 2005). Lühiandmed George Clooney kohta

  2. Experimental studying the effects of horizontal experimental channels on the neutron field in the model of the TVR-M research reactor core

    International Nuclear Information System (INIS)

    Shvedov, O.V.; Aitov, G.M.; Balyuk, S.A.

    1989-01-01

    The effect of horizontal channels on the neutron field in the core of the TVR-M heavy-water cooled high-flux research reactor is experimentally studied. The experiments are carried out in a critical assembly using full-scale core model. The data are obtained characterizing soft and rigid effects of horizontal experimental channels on neutron field. The soft effect is connected with the total mass of experimental channels. It is practically uniform by the core azimuth and reveals itself in the decrease of neutron burst in the reflector, and, consequently in the decrease of neutron field distorsion in the external and middle fuel assembly rows. The rigid effect is conditioned by separate experimental channels located close to the core. It brings about local disturbance in the closest fuel assemblies. The data obtained are a part of experimental program on studying basis power distributions in the TVR-M reactor lattices. 2 refs.; 18 figs

  3. IN THE EARLY JOSEPH ALOIS JULIUS SCHUMPETER'S FOOTSTEPS - MARRIAGE, TRAGEDY AND EMIGRATION

    Directory of Open Access Journals (Sweden)

    J-U. Sandal

    2015-10-01

    Full Text Available At the age of 42 Joseph Alois Schumpeter married the 20 years younger Anna (“Annie” Josefina Reisinger. Joseph Schumpeter is looking forward to being a father, and the couple have a child, Joseph, but both Annie and the baby dies during confinement. The tragedy is a fact, and Schumpeter loses the joy of scientific creativity and concentration. His existence is concurrently burdened by private financial problems. He holds fast to his creative youth work, Theorie der wirtschaftlichen Entwicklung, which is a companion through life and the foundation stone of modern entrepreneurial research worldwide. The article analyzes the important events in Schumpeter’s life and its importance to scientific development in economic theory.

  4. Reactor core in FBR type reactor

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

    1989-01-01

    In a reactor core in FBR type reactors, a portion of homogenous fuels constituting the homogenous reactor core is replaced with multi-region fuels in which the enrichment degree of fissile materials is lower nearer to the axial center. This enables to condition the composition such that a reactor core having neutron flux distribution either of a homogenous reactor core or a heterogenous reactor core has substantially identical reactivity. Accordingly, in the transfer from the homogenous reactor core to the axially heterogenous reactor core, the average reactivity in the reactor core is substantially equal in each of the cycles. Further, by replacing a portion of the homogenous fuels with a multi-region fuels, thereby increasing the heat generation near the axial center, it is possiable to reduce the linear power output in the regions above and below thereof and, in addition, to improve the thermal margin in the reactor core. (T.M.)

  5. [The vitalism of Paul-Joseph Barthez (1734-1806)].

    Science.gov (United States)

    Han, Hee Jin

    2010-06-30

    In The Logic of Life (1970), Francois Jacob (1920- ), Nobel Prize laureate in Physiology or Medicine (1965), proclaimed the end of vitalism based on the concept of life. More than two decades before this capital sentence condemning vitalism was pronounced, Georges Canguilhem (1904-1995), a French philosopher of medicine, already acknowledged that eighteenth-century vitalism was scientifically retrograde and politically reactionary or counter-revolutionary insofar as it was rooted in the animism of Georg Ernst Stahl (1660-1734). The negative preconception of the term 'vitalism' came to be established as an orthodox view, since Claude Bernard (1813-1878) unfairly criticized contemporary vitalism in order to propagate his idea of experimental medicine. An eminent evolutionary biologist like Ernst Mayr (1904-2005) still defended similar views in This is Biology (1997), arguing that if vitalists were decisive and convincing in their rejection of the Cartesian model (negative heuristics), however they were equally indecisive and unconvincing in their own explanatory endeavors (positive heuristics). Historically speaking, vitalists came to the forefront for their outstanding criticism of Cartesian mechanism and physicochemical reductionism, while their innovative concepts and theories were underestimated and received much less attention. Is it true that vitalism was merely a pseudo-science, representing a kind of romanticism or mysticism in biomedical science? Did vitalists lack any positive heuristics in their biomedical research? Above all, what was actually the so.called 'vitalism'? This paper aims to reveal the positive heuristics of vitalism defined by Paul.Joseph Barthez (1734-1806) who was the founder of the vitalist school of Montpellier. To this end, his work and idea are introduced with regard to the vying doctrines in physiology and medicine. At the moment when he taught at the medical school of Montpellier, his colleagues advocated the mechanism of Rene

  6. Component-Level Prognostics Health Management Framework for Passive Components - Advanced Reactor Technology Milestone: M2AT-15PN2301043

    Energy Technology Data Exchange (ETDEWEB)

    Ramuhalli, Pradeep; Roy, Surajit; Hirt, Evelyn H.; Prowant, Matthew S.; Pitman, Stan G.; Tucker, Joseph C.; Dib, Gerges; Pardini, Allan F.

    2015-06-19

    This report describes research results to date in support of the integration and demonstration of diagnostics technologies for prototypical advanced reactor passive components (to establish condition indices for monitoring) with model-based prognostics methods. Achieving this objective will necessitate addressing several of the research gaps and technical needs described in previous technical reports in this series.

  7. Reactor container

    International Nuclear Information System (INIS)

    Fukazawa, Masanori.

    1991-01-01

    A system for controlling combustible gases, it has been constituted at present such that the combustible gases are controlled by exhausting them to the wet well of a reactor container. In this system, however, there has been a problem, in a reactor container having plenums in addition to the wet well and the dry well, that the combustible gases in such plenums can not be controlled. In view of the above, in the present invention, suction ports or exhaust ports of the combustible gas control system are disposed to the wet well, the dry well and the plenums to control the combustible gases in the reactor container. Since this can control the combustible gases in the entire reactor container, the integrity of the reactor container can be ensured. (T.M.)

  8. PREFACE: SANS-YuMO User Meeting at the Start-up of Scientific Experiments on the IBR-2M Reactor: Devoted to the 75th anniversary of Yu M Ostanevich's birth

    Science.gov (United States)

    Gordely, Valentin; Kuklin, Alexander; Balasoiu, Maria

    2012-03-01

    The Second International Workshop 'SANS-YuMO User Meeting at the Start-up of Scientific Experiments on the IBR-2M Reactor', devoted to the 75th anniversary of the birth of Professor Yu M Ostanevich (1936-1992), an outstanding neutron physicist and the founder of small-angle neutron scattering (field, group, and instrument) at JINR FLNPh, was held on 27-30 May at the Frank Laboratory of Neutron Physics. The first Workshop was held in October 2006. Research groups from different neutron centers, universities and research institutes across Europe presented more than 35 oral and poster presentations describing scientific and methodological results. Most of them were obtained with the help of the YuMO instrument before the IBR-2 shutdown in 2006. For the last four years the IBR-2 reactor has been shut down for refurbishment. At the end of 2010 the physical launch of the IBR-2M reactor was finally realized. Nowadays the small-angle neutron scattering (SANS) technique is applied to a wide range of scientific problems in condensed matter, soft condensed matter, biology and nanotechnology, and despite the fact that there are currently over 30 SANS instruments in operation worldwide at both reactor and spallation sources, the demand for beam-time is considerably higher than the time available. It must be remembered, however, that as the first SANS machine on a steady-state reactor was constructed at the Institute Laue Langevin, Grenoble, the first SANS instrument on a 'white' neutron pulsed beam was accomplished at the Joint Institute for Nuclear Research at the IBR-30 reactor, beamline N5. During the meeting Yu M Ostanevich's determinative and crucial contribution to the construction of spectrometers at the IBR-2 high-pulsed reactor was presented, as well as his contribution to the development of the time-of-flight (TOF) small-angle scattering technique, and a selection of other scientific areas. His leadership and outstanding scientific achievements in applications of the

  9. Kr-85m activity as burnup measurement indicator in a pebble bed reactor based on ORIGEN2.1 Computer Simulation

    Science.gov (United States)

    Husnayani, I.; Udiyani, P. M.; Bakhri, S.; Sunaryo, G. R.

    2018-02-01

    Pebble Bed Reactor (PBR) is a high temperature gas-cooled reactor which employs graphite as a moderator and helium as a coolant. In a multi-pass PBR, burnup of the fuel pebble must be measured in each cycle by online measurement in order to determine whether the fuel pebble should be reloaded into the core for another cycle or moved out of the core into spent fuel storage. One of the well-known methods for measuring burnup is based on the activity of radionuclide decay inside the fuel pebble. In this work, the activity and gamma emission of Kr-85m were studied in order to investigate the feasibility of Kr-85m as burnup measurement indicator in a PBR. The activity and gamma emission of Kr-85 were estimated using ORIGEN2.1 computer code. The parameters of HTR-10 were taken as a case study in performing ORIGEN2.1 simulation. The results show that the activity revolution of Kr-85m has a good relationship with the burnup of the pebble fuel in each cycle. The Kr-85m activity reduction in each burnup step,in the range of 12% to 4%, is considered sufficient to show the burnup level in each cycle. The gamma emission of Kr-85m is also sufficiently high which is in the order of 1010 photon/second. From these results, it can be concluded that Kr-85m is suitable to be used as burnup measurement indicator in a pebble bed reactor.

  10. 77 FR 61657 - Indiana Northeastern Railroad Company-Abandonment Exemption-In Branch and St. Joseph Counties, MI

    Science.gov (United States)

    2012-10-10

    ... Northeastern Railroad Company--Abandonment Exemption--In Branch and St. Joseph Counties, MI Indiana... Branch County, Mich., and milepost 100.69 near Sturgis in St. Joseph County, Mich. (the Line). The Line... .'' Decided: October 2, 2012. By the Board, Rachel D. Campbell, Director, Office of Proceedings. Derrick A...

  11. Reactor technology

    International Nuclear Information System (INIS)

    Erdoes, P.

    1977-01-01

    This is one of a series of articles discussing aspects of nuclear engineering ranging from a survey of various reactor types for static and mobile use to mention of atomic thermo-electric batteries of atomic thermo-electric batteries for cardiac pacemakers. Various statistics are presented on power generation in Europe and U.S.A. and economics are discussed in some detail. Molten salt reactors and research machines are also described. (G.M.E.)

  12. Accumulation of Mitochondrial DNA Common Deletion Since The Preataxic Stage of Machado-Joseph Disease.

    Science.gov (United States)

    Raposo, Mafalda; Ramos, Amanda; Santos, Cristina; Kazachkova, Nadiya; Teixeira, Balbina; Bettencourt, Conceição; Lima, Manuela

    2018-04-21

    Molecular alterations reflecting pathophysiologic changes thought to occur many years before the clinical onset of Machado-Joseph disease (MJD)/spinocerebellar ataxia type 3 (SCA3), a late-onset polyglutamine disorder, remain unidentified. The absence of molecular biomarkers hampers clinical trials, which lack sensitive measures of disease progression, preventing the identification of events occurring prior to clinical onset. Our aim was to analyse the mtDNA content and the amount of the common deletion (m.8482_13460del4977) in a cohort of 16 preataxic MJD mutation carriers, 85 MJD patients and 101 apparently healthy age-matched controls. Relative expression levels of RPPH1, MT-ND1 and MT-ND4 genes were assessed by quantitative real-time PCR. The mtDNA content was calculated as the difference between the expression levels of a mitochondrial gene (MT-ND1) and a nuclear gene (RPPH1); the amount of mtDNA common deletion was calculated as the difference between expression levels of a deleted (MT-ND4) and an undeleted (MT-ND1) mitochondrial genes. mtDNA content in MJD carriers was similar to that of healthy age-matched controls, whereas the percentage of the common deletion was significantly increased in MJD subjects, and more pronounced in the preclinical stage (p < 0.05). The BCL2/BAX ratio was decreased in preataxic carriers compared to controls, suggesting that the mitochondrial-mediated apoptotic pathway is altered in MJD. Our findings demonstrate for the first time that accumulation of common deletion starts in the preclinical stage. Such early alterations provide support to the current understanding that any therapeutic intervention in MJD should start before the overt clinical phenotype.

  13. Sauvegarde et valorisation du fonds d’archives familiales de Jean-Joseph Rabearivelo à Madagascar

    Directory of Open Access Journals (Sweden)

    Laurence Ink

    2014-04-01

    Full Text Available Figure essentielle et encore mal connue de la littérature malgache et internationale, Jean-Joseph Rabearivelo (1903‑1937 fut à la fois poète, journaliste et critique, dramaturge et romancier, historien de sa tradition, collecteur et traducteur de textes anciens comme de textes modernes. L’aventure qui débuta fin 2008 pour aboutir à la publication de ses œuvres complètes (AUF/ITEM, CNRS Éditions, Coll. Planète libre, Paris, 2 tomes, 2010 et 2012 consistait à sauvegarder l’important fonds d’archives familiales (plus de 800 manuscrits, tapuscrits, textes édités ou documents de travail confié par les ayant droits à l’Institut Français de Madagascar (Antananarivo, par un travail de tri, de numérisation et de mise en conditionnement neutre, in situ, et à le valoriser par l’édition des textes, pour une grande part inédits, dans une approche scientifique à caractère génétique. Expérience novatrice, structurée par une méthodologie devant constamment s’adapter aux exigences géographique, scientifique et éditoriale, elle est également à considérer comme un cas d’école, pour une meilleure approche des fonds d’archives littéraires, aujourd’hui en péril dans bon nombre de pays du Sud.

  14. Joseph Pulitzer II and Advertising Censorship, 1929-1939. Journalism Monographs Number Seventy-seven.

    Science.gov (United States)

    Pfaff, Daniel W.

    In an age of little or no consumer protection, the St. Louis "Post-Dispatch," under the guidance of Joseph Pulitzer II, was the first and most successful practitioner of self-imposed censorship of advertising, a practice that continues to this day. Beginning on May 1, 1929, the "Post-Dispatch" announced an aggressive program of…

  15. Parkinsonian phenotype in Machado-Joseph disease (MJD/SCA3): a two-case report

    NARCIS (Netherlands)

    Bettencourt, C.; Santos, C.; Coutinho, P.; Rizzu, P.; Vasconcelos, J.; Kay, T.; Cymbron, T.; Raposo, M.; Heutink, P.; Lima, M.

    2011-01-01

    Background: Machado-Joseph disease (MJD), or spinocerebellar ataxia type 3 (SCA3), is an autosomal dominant neurodegenerative disorder of late onset, which is caused by a CAG repeat expansion in the coding region of the ATXN3 gene. This disease presents clinical heterogeneity, which cannot be

  16. From Chemical Analysis to Analyzing Chemical Education: An Interview with Joseph J. Lagowski

    Science.gov (United States)

    Cardellini, Liberato

    2010-01-01

    This interview provides glimpses of Joseph J. Lagowski and his life from the time he played with a Gilbert chemistry set, to his tenure at The University of Texas at Austin. His initial interest in chemistry was further nurtured and developed thanks to an excellent high school teacher. In the interview, Lagowski discusses his research in…

  17. Ethnographic Research and Globalization: A Discussion of Joseph Tobin's Model of Video-Cued Multivocal Ethnography

    Science.gov (United States)

    Watras, Joseph

    2014-01-01

    Joseph Tobin made an impact on the field of comparative education in 2009 when he used a unique form of ethnography to illuminate the effects of world-wide forces, such as modernization, on schools in specific countries. Earlier, in 1989, he published "Preschool in Three Cultures" with co-authors David Wu and Dana Davidson. The…

  18. Resurrecting Democracies : Secularity Recast in Charles Taylor, Paul Valadier, and Joseph Ratzinger

    NARCIS (Netherlands)

    Ossewaarde-Lowtoo, Roshnee

    In this article, the alternative conception of secularity of Charles Taylor, Paul Valadier and Joseph Ratzinger (former Benedict XVI) is explored. A secularized society, which they take as an established condition, does not necessarily exclude religion, Christianity or Christian transcendence, in

  19. Cervical and ocular vestibular evoked potentials in Machado-Joseph disease: Functional involvement of otolith pathways.

    Science.gov (United States)

    Ribeiro, Rodrigo Souza; Pereira, Melissa Marques; Pedroso, José Luiz; Braga-Neto, Pedro; Barsottini, Orlando Graziani Povoas; Manzano, Gilberto Mastrocola

    2015-11-15

    Machado-Joseph disease is defined as an autosomal dominant ataxic disorder caused by degeneration of the cerebellum and its connections and is associated with a broad range of clinical symptoms. The involvement of the vestibular system is responsible for several symptoms and signs observed in the individuals affected by the disease. We measured cervical and ocular vestibular evoked myogenic potentials in a sample of Machado-Joseph disease patients in order to assess functional pathways involved. Bilateral measures of cervical and ocular vestibular evoked myogenic potentials (cVEMP and oVEMP) were obtained from 14 symptomatic patients with genetically proven Machado-Joseph disease and compared with those from a control group of 20 healthy subjects. Thirteen (93%) patients showed at least one abnormal test result; oVEMP and cVEMP responses were absent in 17/28 (61%) and 11/28 (39%) measures, respectively; and prolonged latency of cVEMP was found in 3/28 (11%) measures. Of the 13 patients with abnormal responses, 9/13 (69%) patients showed discordant abnormal responses: four with absent oVEMP and present cVEMP, two with absent cVEMP and present oVEMP, and three showed unilateral prolonged cVEMP latencies. Both otolith-related vestibulocollic and vestibulo-ocular pathways are severely affected in Machado-Joseph disease patients evaluated by VEMPs. Copyright © 2015 Elsevier B.V. All rights reserved.

  20. Psi Chi/APA Edwin B. Newman Graduate Research Award: Joseph H. Hammer

    Science.gov (United States)

    American Psychologist, 2009

    2009-01-01

    Joseph H. Hammer, recipient of the Psi Chi/APA Edwin B. Newman Graduate Research Award, is cited for an outstanding research paper whose findings provide important evidence regarding the promise of a male-sensitive approach to mental health marketing and empirically support the inclusion of theory-driven enhancements in group-targeted mental…

  1. Paula Coutinho's outstanding contribution to the definition of Machado-Joseph disease.

    Science.gov (United States)

    Garcia, Bruno Carniatto Marques; Germiniani, Francisco Manoel Branco; Marques, Paula; Sequeiros, Jorge; Teive, Hélio Afonso Ghizoni

    2017-10-01

    Machado-Joseph disease, also known as spinocerebellar ataxia type 3, is the most common form of autosomal dominant ataxia in the world. Paula Coutinho, a highly-regarded Portuguese neurologist worldwide, had a seminal participation in the definition of this disease, more than 40 years ago.

  2. Spinocerebellar ataxia type 3 (Machado-Joseph disease) : severe destruction of the lateral reticular nucleus

    NARCIS (Netherlands)

    Rub, U; de Vos, RAI; Schultz, C; Brunt, ER; Paulson, H; Braak, H

    The lateral reticular nucleus (LRT) of the medulla oblongata is a precerebellar nucleus involved in proprioception and somatomotor automatisms. We investigated this nucleus in five individuals with clinically diagnosed and genetically confirmed spinocerebellar ataxia type 3 (SCA3, Machado-Joseph

  3. Joseph Davidovich Levit – the oretician and practitioner of national endocrinology (90th birthday anniversary

    Directory of Open Access Journals (Sweden)

    Shmuel Levit

    2016-12-01

    The main works of Dr. Joseph Levit, as well as his scientific biography may serve not only as a source of useful information, but also as an incentive for independent research for both the younger generation and the seasoned experts in various fields of medical science.

  4. A Fourth Way : Joseph Ratzinger’s veluti si Deus daretur

    NARCIS (Netherlands)

    Ossewaarde-Lowtoo, Roshnee

    The rationale behind Joseph Ratzinger’s intriguing proposition to his «non-believing friends» to live as if God exists is here examined. It is argued that his wager makes sense when it is interpreted in the light of his commitment to the transcendent dignity of all humans. His proposition may enable

  5. A Short Biography of Joseph Fourier and Historical Development of Fourier Series and Fourier Transforms

    Science.gov (United States)

    Debnath, Lokenath

    2012-01-01

    This article deals with a brief biographical sketch of Joseph Fourier, his first celebrated work on analytical theory of heat, his first great discovery of Fourier series and Fourier transforms. Included is a historical development of Fourier series and Fourier transforms with their properties, importance and applications. Special emphasis is made…

  6. Reflections on Preparing Educators to Evaluate the Efficacy of Educational Technology: An Interview with Joseph South

    Science.gov (United States)

    Bull, Glen; Spector, J. Michael; Persichitte, Kay; Meiers, Ellen

    2017-01-01

    Joseph South, an educational researcher, technology consultant, and former director of the U.S. Office of Educational Technology participated in a research initiative on Educational Technology Efficacy Research organized by the Jefferson Education Accelerator, Digital Promise, and the Curry School of Education at the University of Virginia. The…

  7. Joseph McCabe: A Forgotten Early Populariser of Science and Defender of Evolution

    Science.gov (United States)

    Cooke, Bill

    2010-01-01

    Joseph McCabe (1867-1955) was one of the most prolific and gifted polymaths of the twentieth century. Long before such a thing was thought respectable, and almost a century before any university established a chair in the public understanding of science, McCabe made a living as a populariser of science and a critic of philosophical and religious…

  8. O crepúsculo da ética imperial habsburga em Bruno Schulz e Joseph Roth The twilight of the Habsburg imperial ethics in Bruno Schulz and Joseph Roth

    Directory of Open Access Journals (Sweden)

    Luis S. Krausz

    2007-05-01

    Full Text Available Os escritores Bruno Schulz e Joseph Roth entraram para a história da literatura, respectivamente, como representantes da literatura polonesa e austríaca, como se pertencessem a mundos diversos. Entretanto ambos compartilharam de uma memória comum, que era a vida nas províncias orientais do Império Austro-Húngaro, nas cidades de Drohobycz e Brody, hoje pertencentes à Ucrânia. As obras de ficção de Schulz e de Roth fazem referência ao universo austro-húngaro e habsburgo, um reino milenar que via a si mesmo não simplesmente como uma realidade política, mas como um império que tinha como missão trazer a seus súditos uma forma de vida considerada superior do ponto de vista espiritual, ético e moral. A idéia do Sacro Império Romano Germânico, que se considerava portador de uma mensagem humana, subsistiu, até o século 20, no longo reinado do Kaiser Francisco José e neste sentido a 1ª Guerra Mundial significa não simplesmente o desmembramento político do Império Austro-Húngaro em seus diferentes componentes, mas também a falência de uma idéia de Estado que transcendia à esfera do meramente político para tornar-se um lar espiritual e cultural para seus súditos. O mundo que sobreveio à 1ª Guerra Mundial é marcado pelas tendências fáustico-titânicas de um individualismo materialista, que devota todas suas energias à produção e à acumulação de capital, e é sobre este novo mundo que Schulz e Roth olham em suas obras, sempre do ponto de vista de um universo anterior, marcado pela nostalgia de um exílio irreversível. Palavras-chave: Nostalgia. Exílio. Império Habsburgo. Joseph Roth. Bruno Schulz. Bruno Schulz and Joseph Roth figure in the history of literature as Representatives of Polish and Austrian literature, respectively, as if they were part of different worlds. However, both share a common memory: the life in the eastern provinces of the Austrian-Hungarian Empire, in the cities of Drohobycz

  9. Joseph M. Nyasani It is not only astronomers who have been ...

    African Journals Online (AJOL)

    Galileo. Gal.ilei is a good example of that. Indeed the Greek Ionian. School, in trying to unravel the mystery of the earth's ... which govern scientific knowledge and indeed all cognitive .... of space or it is itself space confounded in the process of.

  10. Three Experts on Quality Management: Philip B. Crosby, W. Edwards Deming, Joseph M. Juran

    Science.gov (United States)

    1992-07-01

    Department of the Navy Office of the Under Secretary of the Navy Total Quality Leadership Omce THREE EXPERTS ON QUALITY MANAGEMENT : PHILIP B. CROSBY W...research, as the "price of nonconformance." To aid managers in statistical theory , statistical thinking, and the application tracking the cost of doing...Quality Management emphasizes that the process must become a way of life in Theory of Systems. "A system is a series of the organization. Continuance is

  11. 77 FR 14441 - Facility Operating License Amendment From Southern Nuclear Operating, Inc., Joseph M. Farley...

    Science.gov (United States)

    2012-03-09

    .... Similarly, an active or passive failure in the BARS system will not result in loss of the RWST safety... documents over the internet, or in some cases to mail copies on electronic storage media. Participants may.... Participants are requested not to include personal privacy information, such as social security numbers, home...

  12. nkereuwem W. ebiti,1 Joseph o. ike,2 taiwo l. Sheikh,1 Dupe M ...

    African Journals Online (AJOL)

    parenting yield positive effects in adolescents, for example in ... anxiety (Jackson & Crocket 2000; Steinberg,. 1996). Research ... been done on the effects of self esteem on drug use, studies on ...... in behaviour. (Statistics Canada, Ottawa,.

  13. Metallurgical evaluation of failed post-tensioned containment tendon anchors at Joseph M. Farley Unit 2

    International Nuclear Information System (INIS)

    Czajkowski, C.J.

    1986-01-01

    A metallurgical examination has been performed on three failed post-tensioned containment tendon anchors and one intact anchor from the Farley Unit 2 Nuclear Power Station. The evaluation consisted of chemical/mechanical testing, optical microscopy, scanning electron microscopy, and energy dispersive spectroscopy. The conclusions drawn from the investigation were: 1) the anchors met the chemical and mechanical properties of AISI 4140/4142 steel; 2) there was no evidence of phosphorous segregation to the grain boundary (by ethereal picral etch); 3) the observed cracking was generally a mixed mode of intergranular and quasi-cleavage as well as ductile rupture with the intergranular cracking occurring along prior austenite grain boundaries; 4) the results of the mechanical tests coupled with the discontinuous nature of the intergranular areas and the elimination of other modes of failure give sufficient indication that the failure was a hydrogen induced cracking phenomenon

  14. 76 FR 71374 - Joseph Giacchino, M.D.; Decision and Order

    Science.gov (United States)

    2011-11-17

    ... suspension, which by definition is a sanction of finite duration. See Merriam-Webster's Collegiate Dictionary... suspended Respondent's medical license and state registration prior to a hearing, at which he may ultimately... authority under Illinois law to dispense a controlled substance. See Oakland Medical Pharmacy, 71 FR 50,100...

  15. Diseño para la implementación de los procesos de talento humano para la Pyme Producomercio Joseph´s Foods

    OpenAIRE

    Alvarado Villarreal, Maria del Rocio

    2014-01-01

    La empresa Producomercio Joseph´s Foods, es una empresa de tipo familiar, actualmente está formando parte del sector de las PYMES, inició sus operaciones hace 47 años como una pequeña empresa artesanal, con el pasar del tiempo ha ido creciendo progresivamente, por lo que cada día precisa la contratación de más personal con especialización de funciones; el compromiso de sus directivos es ofrecer productos de la mejor calidad y con el mejor servicio, por ello para seguir operando y llegar a tra...

  16. Experimental Design for Evaluating Selected Nondestructive Measurement Technologies - Advanced Reactor Technology Milestone: M3AT-16PN2301043

    Energy Technology Data Exchange (ETDEWEB)

    Ramuhalli, Pradeep [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hirt, Evelyn H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Pitman, Stan G. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Dib, Gerges [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Roy, Surajit [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Good, Morris S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Walker, Cody M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-07-16

    The harsh environments in advanced reactors (AdvRx) increase the possibility of degradation of safety-critical passive components, and therefore pose a particular challenge for deployment and extended operation of these concepts. Nondestructive evaluation technologies are an essential element for obtaining information on passive component condition in AdvRx, with the development of sensor technologies for nondestructively inspecting AdvRx passive components identified as a key need. Given the challenges posed by AdvRx environments and the potential needs for reducing the burden posed by periodic in-service inspection of hard-to-access and hard-to-replace components, a viable solution may be provided by online condition monitoring of components. This report identifies the key challenges that will need to be overcome for sensor development in this context, and documents an experimental plan for sensor development, test, and evaluation. The focus of initial research and development is on sodium fast reactors, with the eventual goal of the research being developing the necessary sensor technology, quantifying sensor survivability and long-term measurement reliability for nondestructively inspecting critical components. Materials for sensor development that are likely to withstand the harsh environments are described, along with a status on the fabrication of reference specimens, and the planned approach for design and evaluation of the sensor and measurement technology.

  17. Reactor container

    International Nuclear Information System (INIS)

    Abe, Yoshihito; Sano, Tamotsu; Ueda, Sabuo; Tanaka, Kazuhisa.

    1987-01-01

    Purpose: To improve the liquid surface disturbance in LMFBR type reactors. Constitution: A horizontal flow suppressing mechanism mainly comprising vertical members is suspended near the free liquid surface of coolants in the upper plenum. The horizontal flow of coolants near the free liquid surface is reduced by the suppressing mechanism to effectively reduce the surface disturbance. The reduction in the liquid surface disturbance further prevails to the entire surface region with no particular vertical variations to the free liquid surface to remarkably improve the preventive performance for the liquid surface disturbance. Accordingly, it is also possible to attain the advantageous effects such as prevention for the thermal fatigue in reactor vessel walls, reactor upper mechanisms, etc. and prevention of burning damage to the reactor core due to the reduction of envolved Ar gas. (Kamimura, M.)

  18. Reactor containment

    International Nuclear Information System (INIS)

    Kawabe, Ryuhei; Yamaki, Rika.

    1990-01-01

    A water vessel is disposed and the gas phase portion of the water vessel is connected to a reactor container by a pipeline having a valve disposed at the midway thereof. A pipe in communication with external air is extended upwardly from the liquid phase portion to a considerable height so as to resist against the back pressure by a waterhead in the pipeline. Accordingly, when the pressure in the container is reduced to a negative level, air passes through the pipeline and uprises through the liquid phase portion in the water vessel in the form of bubbles and then flows into the reactor container. When the pressure inside of the reactor goes higher, since the liquid surface in the water vessel is forced down, water is pushed up into the pipeline. Since the waterhead pressure of a column of water in the pipeline and the pressure of the reactor container are well-balanced, gases in the reactor container are not leaked to the outside. Further, in a case if a great positive pressure is formed in the reactor container, the inner pressure overcomes the waterhead of the column of water, so that the gases containing radioactive aerosol uprise in the pipeline. Since water and the gases flow being in contact with each other, this can provide the effect of removing aerosol. (T.M.)

  19. Five cases of a Joseph disease family with non-REM sleep apnea and MRI study

    International Nuclear Information System (INIS)

    Kitamura, Junichi; Tsuruta, Kazuhito; Yamamura, Yoshinori; Kurihara, Teruyuki; Matsukura, Shigeru

    1987-01-01

    Four male and one female patients of a new Joseph disease family in southern Kyushu are presented. This disorder is inherited by autosomal dominant trait. The clinical symptoms are characterized by bulging eyes, ophthalmoplegia, dysarthria, rigospasticity of the lower limbs, marked dystonia and bradykinesia. In our cases, extrapyramidal symptoms were improved by amantadine and L-Dopa therapy. CSF homovanilic acid (HVA) was markedly reduced. Muscle biopsy and electromyographic studies revealed neurogenic changes. MRI revealed mild atrophy of frontal lobe and cerebellum, and marked atrophy of brain stem. These findings were consistent with the clinical manifestations. Our case had central type sleep apnea by sleep EEG and polygraphic studies. This is the first report about sleep apnea and MRI of Joseph disease. (author)

  20. Five cases of a Joseph disease family with non-REM sleep apnea and MRI study

    Energy Technology Data Exchange (ETDEWEB)

    Kitamura, Junichi; Tsuruta, Kazuhito; Yamamura, Yoshinori; Kurihara, Teruyuki; Matsukura, Shigeru

    1987-09-01

    Four male and one female patients of a new Joseph disease family in southern Kyushu are presented. This disorder is inherited by autosomal dominant trait. The clinical symptoms are characterized by bulging eyes, ophthalmoplegia, dysarthria, rigospasticity of the lower limbs, marked dystonia and bradykinesia. In our cases, extrapyramidal symptoms were improved by amantadine and L-dopa therapy. CSF homovanilic acid (HVA) was markedly reduced. Muscle biopsy and electromyographic studies revealed neurogenic changes. MRI revealed mild atrophy of frontal lobe and cerebellum, and marked atrophy of brain stem. These findings were consistent with the clinical manifestations. Our case had central type sleep apnea by sleep EEG and polygraphic studies. This is the first report about sleep apnea and MRI of Joseph disease.

  1. MRI of the spinocerebellar degeneration (multiple system atrophy, Holmes type, and Menzel-Joseph type)

    International Nuclear Information System (INIS)

    Mukai, Eiichiro; Makino, Naoki.

    1991-01-01

    We have analyzed MRI in 33 patients with several forms of spinocerebellar degeneration; 17 with multiple system atrophy, 10 with Holmes type, and 6 with Menzel-Joseph type. The MRIs were obtained using a 1.5-T GEMR System. Patients with multiple system atrophy demonstrated: atrophy of the brain stem, particularly basis pontis; decreased signal intensity of the white matter of pons; atrophy of the white matter of cerebellum; atrophy and decreased signal intensity of the putamen, particularly along their lateral and posterior portions; and atrophy of the cerebrum. Patients with Holmes type showed: atrophy of the cerebellum; atrophy of the vermis more than hemispheres; and nuclei of the cerebellum with no decreased intensity on T 2 -weighted sequences. Patients with Menzel-Joseph type demonstrated moderate atrophy of the brain stem and mild atrophy of the white matter of cerebellum. MRI is a useful diagnostic tool in the management of the spinocerebellar degeneration. (author)

  2. Green sea turtle age, growth, and population characteristics in St. Joseph Bay, Florida from 1998 to 2010 (NCEI Accession 0159273)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains morphology, sex ratio, body condition, disease status, age structure, and growth patterns of 448 green sea turtles cold stunned in St. Joseph...

  3. Arthur Conan Doyle, Joseph Bell, and Sherlock Holmes. A neurologic connection.

    Science.gov (United States)

    Westmoreland, B F; Key, J D

    1991-03-01

    Neurologists, like physicians in several other medical specialties, can lay claim to Sherlock Holmes as one of their own. This assertion is validated by the number of neurologic conditions, such as seizures, stroke, syncope, encephalopathies, and head trauma, that are mentioned in the stories and novels. In addition, the article reviews the powers of observation and the deductive approach utilized by Conan Doyle and Joseph Bell, the models for Sherlock Holmes, and how these skills can be applied to medical problems.

  4. Water quality and discharge data for St. Joseph Bay, Florida, 1997-98

    Science.gov (United States)

    Berndt, M.P.; Franklin, M.A.

    1999-01-01

    Historical data were compiled on water quality and water levels for the St. Joseph Bay area to assess quality of possible sources of land-derived water into the Bay. Ground-water quality data were compiled from Florida Department of Environmental Protection and surface-water quality data were compiled from U.S.Geological Survey files. Water-quality and water-level data were measured during two sample collection periods in October 1997 and March 1998 to determine water-quality and discharge rates in St. Joseph Bay under two sets of flow conditions. Measurements in the Bay included water level, temperature, pH, specific conductance, dissolved oxygen, and turbidity. Median pH in water from the surficial, intermediate and Floridan aquifer systems ranged from 4.8 to 7.8, and median specific conductance values were less than 500 microsiemens per centimeter. Median nutrient concentrations-- nitrate plus nitrite, ammonia and phosphorus--in the three aquifers were less than 0.5 milligrams per liter. The median pH was 7.0 and the median specific conductance was 81 microsiemens per centimeter for two samples from the Chipola River distribution canal. Water level data were obtained for several wells near St. Joseph Bay but only two wells yielded sufficient data to plot hydrographs. Measurements in St. Joseph Bay during the October and March collection periods were similar for pH and turbidity but differed for temperature, specific conductance and dissolved oxygen. The median temperature was 20.6 degrees Celsius in October and 15.4 degrees Celsius in March, median specific conductance was 39,500 microsiemens per centimeter in October and 43,300 microsiemens per centimeter in March, and median dissolved oxygen was 7.6 milligrams per liter in October and 8.3 milligrams per liter in March. The range in water levels over a tidal cycle in St. Joseph Bay on October 29, 1997 was about 1 foot. During a 24-hour tidal cycle on October 29, 1997, estimated hourly discharge varied from

  5. Accumulation of radioactive corrosion products on steel surfaces of VVER type nuclear reactors. I. 110mAg

    CSIR Research Space (South Africa)

    Hirschberg, G

    1999-03-01

    Full Text Available contaminants in the passive layer formed on austenitic stainless steel. In the first part of the series the accumulation of 110mAg has been investigated. Potential dependent sorption of Ag+. ions (cementation) is found to be the predominant process...

  6. Effect of reactor irradiation on long-term strength and creep of 0Kh16N15M3B steel under plane stressed state

    International Nuclear Information System (INIS)

    Khristov, G.P.; Kosov, B.D.

    1982-01-01

    The paper deals with analysis of results of experimental studies in creep of the austenitic OKh16n15m3b steel with various size of initial-structure grain under conditions of high-intensity reactor irradiation and control tests. It is suggested to consider the material initial structure effect on intensity of minimum creep rates both under ordinary and intrareactor conditions of loading by means of the function grain size effect on the equivalent stress. It is shown that the criterial expression previously suggested by the authors is invariant to the type of stressed and structural states and relative to intensity of minimal creep rates. It is established that the creep rate of the irradiated steel may be calculated from dependence for nonirradiated steel using as an argument a certain reduced equivalent stress which is a function of the acting stress and irradiation parameter

  7. HEU Measurements of Holdup and Recovered Residue in the Deactivation and Decommissioning Activities of the 321-M Reactor Fuel Fabrication Facility at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    DEWBERRY, RAYMOND; SALAYMEH, SALEEM R.; CASELLA, VITO R.; MOORE, FRANK S.

    2005-03-11

    This paper contains a summary of the holdup and material control and accountability (MC&A) assays conducted for the determination of highly enriched uranium (HEU) in the deactivation and decommissioning (D&D) of Building 321-M at the Savannah River Site (SRS). The 321-M facility was the Reactor Fuel Fabrication Facility at SRS and was used to fabricate HEU fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the SRS production reactors. The facility operated for more than 35 years. During this time thousands of uranium-aluminum-alloy (U-Al) production reactor fuel tubes were produced. After the facility ceased operations in 1995, all of the easily accessible U-Al was removed from the building, and only residual amounts remained. The bulk of this residue was located in the equipment that generated and handled small U-Al particles and in the exhaust systems for this equipment (e.g., Chip compactor, casting furnaces, log saw, lathes A & B, cyclone separator, Freon{trademark} cart, riser crusher, ...etc). The D&D project is likely to represent an important example for D&D activities across SRS and across the Department of Energy weapons complex. The Savannah River National Laboratory was tasked to conduct holdup assays to quantify the amount of HEU on all components removed from the facility prior to placing in solid waste containers. The U-235 holdup in any single component of process equipment must not exceed 50 g in order to meet the container limit. This limit was imposed to meet criticality requirements of the low level solid waste storage vaults. Thus the holdup measurements were used as guidance to determine if further decontamination of equipment was needed to ensure that the quantity of U-235 did not exceed the 50 g limit and to ensure that the waste met the Waste Acceptance Criteria (WAC) of the solid waste storage vaults. Since HEU is an accountable nuclear material, the holdup assays and assays of recovered

  8. Utilization of the {sup 93}Nb(n,n'){sup 93}Nb{sup m} Reaction for for Reactor Neutron Dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Czock, K. H.; Houtermans, H. [International Atomic Energy Agency, Division of Research and Laboratories, Vienna (Austria)

    1974-09-15

    For the measurement of large ({Phi}>10{sup 18}n/cm{sup 2}) fast neutron fluences in research reactors, the reaction {sup 93}Nb(n,n'){sup 93}Nb{sup m} is fairly seldom used (Lloret, Hegedus). The reason is that the excitation function for the production of the {sup 93}Nb isomeric state (half-life{approx_equal}11.4 years) by inelastic neutron scattering is nearly unknown. Also the determination of the absolute {sup 93}Nb{sup m} activity is difficult, e.g. due to the bad knowledge of the conversion coefficients {alpha}{sub tot} and {alpha}{sub K}. But for neutron dosimetry purposes one does not necessarily need absolute activity values, if one irradiated niobium foil (e.g. 10 mm empty and 0.1 mm thick) is accepted to be a reference source to other irradiated niobium foils (of the same original material). If the cross section measurements and the fluence determinations are both based on the same reference source {sup 93}Nb{sup m} as an arbitrary activity standard, the possible inaccuracy of this activity value would not matter. Such an accepted reference source could be deposited at one central institution. Once the reference source activity is defined (at present within 30% of the true absolute activity value) niobium sources with activities determined relative to this reference source could be supplied together with non-irradiated niobium foils to interested laboratories. (author)

  9. World's largest DC flywheel generator for the toroidal field power supply of JAERI's JFT-2M Tokamak nuclear fusion reactor

    International Nuclear Information System (INIS)

    Tani, Takashi; Nakanishi, Yuji; Horita, Tsuyoshi; Kawase, Chiharu; Oyabu, Isao; Kishimoto, Takeshi.

    1996-01-01

    Mitsubishi Electric has delivered the world's largest DC generator for the toroidal field coil power supply of the JFT-2M Tokamak at the Japan Atomic Energy Research Institute. The unit rotates at 225 or 460 rpm, providing a maximum rated output of 2,700 V, 19,000 A and 51.3 MW. The toroidal field is a DC field, so use of a DC generator permits a simpler design consuming less floor space than an AC drive system. The generator was manufactured following extensive studies on commutation, mechanical strength and insulation. (author)

  10. Les limites du capitalisme selon Joseph Schumpeter et Karl Marx The limits of capitalism by Joseph Schumpeter and Karl Marx

    Directory of Open Access Journals (Sweden)

    Omer Moussaly

    2012-11-01

    Full Text Available À jongler avec les mérites et les ratés de la théorie de Marx et de ses adeptes, Schumpeter semble vouloir s’imposer en tant qu’arbitre unique et impartial du marxisme. Bien qu’il reconnaisse plusieurs mérites à la conception économique de Marx, Schumpeter soulève de multiples limites à l’analyse des marxistes orthodoxes qui ne font que corroborer sa prise de position critique du marxisme. Une lecture des critiques et des réponses que Schumpeter a adressées au marxisme permet de révéler les points communs et les divergences entre les deux auteurs. Chez Schumpeter comme chez Marx, le capitalisme est un mode passager de la production sociale. Schumpeter se fixe comme objectif de combler la lacune des marxistes qui n’ont pas su identifier les vraies raisons du dépérissement du capitalisme. Il lui fallait relever le défi de critiquer certains adeptes de Marx sans pour autant s’en prendre trop au fondateur du marxisme auquel il vouait une admiration sincère.Juggling with the merits and flaws of Marx and his followers, Schumpeter seems to be acting as an impartial judge, especially since he eliminates the extreme arguments of both the Marxists and their opponents. His technique seeks to make his position unassailable from either side of the debate. Although he recognizes several merits to the economic conceptions of Marx, Schumpeter points out several limits of orthodox Marxists which only confirm his critical position towards Marxism. A careful reading of Schumpeter’s commentary on Marxism reveals many points in common between himself and Marx. For Schumpeter as for Marx, capitalism is a transitory and historically limited social mode of production. Unlike most Marxists, who merely repeated ideological slogans from the works of Marx, Schumpeter believed he had discovered the true reasons behind capitalism’s demise. With his critique of Marxism, Schumpeter did not wish to diminish the merit of its founder, but rather

  11. Canada-India Reactor (CIR)

    Energy Technology Data Exchange (ETDEWEB)

    None

    1960-12-15

    Design information on the Canada-India Reactor is presented. Data are given on reactor physics, the core, fuel elements, core heat transfer, control, reactor vessel, fluid flow, reflector and shielding, containment, cost estimates, and research facilities. Drawings of vertical and horizontal sections of the reactor and fluid flow are included. (M.C.G.)

  12. The effects of thermal aging on material behavior and strength of CF8M in nuclear reactor coolant system

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Jae Do; Lee, Yong Seon; Park, Jung Cheol; In, Jae Hyeon; Woo, Seung Wan; Pae, Yong Tak; Nam, Uk Hui; Park, Yun Won [Yeungnam Univ., Gyeongsan (Korea, Republic of)

    1999-03-15

    The following investigations are performed in order to estimate the mechanism of the structural integrity, and the life prediction. The CF8M is observed a brittle behavior in the range of 475 .deg. C. The five classes of the thermally aged CF8M specimen are prepared using an artificially accelerated aging method. Namely, after the specimen are held for 100, 300, 900, 1800 and 3600 hrs. at 430 .deg. C respectively, the specimen are water cooled to room temperature. In addition to the thermally aged specimens the specimens associated with {delta}-phase degradation are prepared. After the specimens are maintained for 20 min, 5, 15, 50 and 150 hrs. at 700 .deg. C, respectively. which is in the range of {delta}-phase degradation, all specimens are cooled in water. The impact energy variations are measured for both the aged and virgin specimen at -173, -70, -32, 27 and 100 .deg. C, respectively, through the Charpy impact tests in addition to the hardness tests. The characteristics of the fatigue crack growth and low cycle fatigue tests are investigated using both aged and virgin specimens. Also fractured surfaces of the specimen are observed using the scanning electronic microscopy. J-R curve and J{sub IC} of the aged and virgin specimens are found J{sub IC} in order to predict the critical flaw size and fatigue life.

  13. Photo-fermentative hydrogen production in a 4m3 baffled reactor: Effects of hydraulic retention time.

    Science.gov (United States)

    Zhang, Quanguo; Lu, Chaoyang; Lee, Duu-Jong; Lee, Yu-Jen; Zhang, Zhiping; Zhou, Xuehua; Hu, Jianjun; Wang, Yi; Jiang, Danping; He, Chao; Zhang, Tian

    2017-09-01

    A 4m 3 pilot-scale baffled continuous-flow photoreactor with four sequential chambers (#1-#4) was established and tested to evaluate its photo-fermentative hydrogen production from wastewater that contains (10g/L glucose using a functional consortium at 30°C, under light with an intensity of 3000±200lux with a hydraulic retention time (HRT) of 24-72h. The hydrogen production rate and the broth characteristics varied significantly in the flow direction. The hydrogen production rate was highest in chamber #1, and lower in chambers #2-#4 at an HRT of 72h, while the peak production rate shifted to the latter chambers as the HRT was shortened. The overall H 2 production rate increased as HRT decreased, but was not consistent with the predictions that were based on the complete-mixing assumption. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. Neutron Fluence Evaluation of Reactor Internal Structure Using 3D Transport Calculation Code, RAPTOR-M3G

    International Nuclear Information System (INIS)

    Maeng, YoungJae; Lim, MiJoung; Kim, KyungSik; Cho, YoungKi; Yoo, ChoonSung; Kim, ByoungChul

    2015-01-01

    Age-related degradation mechanisms are including the irradiation-assisted stress corrosion cracking(IASCC), void swelling, stress relaxation, fatigue, and etc. A lot of Baffle Former Bolts(BFBs) was installed at the former plate ends between baffle and barrel structure. These would undergo severe experiences, which are high temperature and pressure, bypass water flow and neutron exposure and have some radioactive limitation in inspecting their integrity. The objectives of this paper is to evaluate fast neutron fluence(n/cm 2 , E>1.0MeV) for PWR internals using 3D transport calculation code, RAPTOR-M3G, and to figure out a strategy to manage the effects of aging in PWR internals. One of age-related degradation mechanisms, IASCC, which is affected by fast neutron exposure rate, has been currently issued for PWR internals and has 2 x 10 21 (n/cm 2 ) of the threshold value by MRP-175. Because a lot of BFBs was installed around the internal components, closer inspections are required. As part of an aging management for Kori unit 2, 3D transport calculation code, RAPTOR-M3G, was applied for determining fast neutron fluence at baffle, barrel and former plates regions. As a result, the fast neutron fluence exceeds the screening or threshold values of IASCC in all of baffle, barrel and former plate region. And the most significant region is the baffle because it is located closest to the core. In addition, some regions including former plate tend to be more damaged because of less moderate ability than water. In conclusion, Ice's has been progressed for PWR internals of Kori unit 2. Several regions of internal components were damaged by fast neutron exposure and increase in size as time goes by

  15. Thai research reactor

    International Nuclear Information System (INIS)

    Aramrattana, M.

    1987-01-01

    The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

  16. A discussion of stock market speculation by Pierre-Joseph Proudhon

    OpenAIRE

    Jean-Claude Juhel; Dominique Dufour

    2010-01-01

    International audience; The object of this contribution is to present the ideas behind the thinking of the French economist Pierre-Joseph Proudhon (1809-1865) in relation to the causes and effects of Stock market speculation. It is based upon the works of this author but particularly on his “Manuel du spéculateur à la Bourse” (Stock Market Speculator Manual) edited in 1857 in Paris. Compared to the markets of today, however, the stock market described by Proudhon appears embryonic. Neverthele...

  17. Pierre-Joseph Proudhon, Du principe de l’art et de sa destination sociale, 1865

    OpenAIRE

    2017-01-01

    Introduction par Anne-Marie Bouchard Amalgamant le devenir historique des classes sociales (aristocratie et bourgeoisie) et le devenir social des formes de l’art (art pour l’art et art social), Pierre-Joseph Proudhon (1809-1865) propose dans Du principe de l’art et de sa destination socialeune lecture très personnelle de l’histoire de l’art des Égyptiens à Courbet, de laquelle il prétend extraire « la théorie la plus complète de l’art ». 1. Gustave Courbet, Les Casseurs de pierres, 1849 Œuvr...

  18. Keeper of the nuclear conscience the life and work of Joseph Rotblat

    CERN Document Server

    Brown, Andrew

    2012-01-01

    Joseph Rotblat was the Jewish nuclear scientist whose disillusionment with nuclear weapons encouraged him to become one of the prime architects of the anti-nuclear movement, and resulted in his lifelong efforts to promote social responsibility in science. His founding of Pugwash and his humanitarian work ultimately led to his being awarded the Nobel Peace Prize. Rotblat's life, from his boyhood in Warsaw under siege and occupation in World War I to an active old age that brought honours and public recognition, is a compelling human story in itself. What gave it significance is the single-minde

  19. Li-Fraumeni syndrome: Discovery and future challenges - Joseph Fraumeni Symposium

    Science.gov (United States)

    In May 2014, NCI’s Division of Cancer Epidemiology and Genetics (DCEG) hosted Cancer Epidemiology: From Pedigrees to Populations, a scientific symposium honoring 50 years of visionary leadership by Dr. Joseph F. Fraumeni, Jr., the founding Director of DCEG. In this video, Dr. Stephen Chanock of NCI provides opening remarks. Dr. David Schottenfeld of the University of Michigan moderates a session on the search for cancer susceptibility genes. Dr. Louise Strong of University of Texas MD Anderson Cancer Center speaks about the discovery and future challenges of Li-Fraumeni syndrome research. For more information on this symposium, visit http://dceg.cancer.gov/news-events/Fraumeni-symposium-speakers.

  20. Johann Joseph on Geometrical-Optical Illusions: A Translation and Commentary.

    Science.gov (United States)

    Wade, Nicholas J; Todorović, Dejan; Phillips, David; Lingelbach, Bernd

    2017-01-01

    The term geometrical-optical illusions was coined by Johann Joseph Oppel (1815-1894) in 1855 in order to distinguish spatial distortions of size and orientation from the broader illusions of the senses. We present a translation of Oppel's article and a commentary on the material described in it. Oppel did much more than give a name to a class of visual spatial distortions. He examined a variety of figures and phenomena that were precursors of later, named illusions, and attempted to quantify and interpret them.

  1. Johann Joseph Oppel (1855) on Geometrical–Optical Illusions: A Translation and Commentary

    Science.gov (United States)

    Todorović, Dejan; Phillips, David; Lingelbach, Bernd

    2017-01-01

    The term geometrical–optical illusions was coined by Johann Joseph Oppel (1815–1894) in 1855 in order to distinguish spatial distortions of size and orientation from the broader illusions of the senses. We present a translation of Oppel’s article and a commentary on the material described in it. Oppel did much more than give a name to a class of visual spatial distortions. He examined a variety of figures and phenomena that were precursors of later, named illusions, and attempted to quantify and interpret them. PMID:28694957

  2. Magnetohydrodynamic boundary layer flow past a porous substrate with Beavers-Joseph boundary condition

    International Nuclear Information System (INIS)

    Jat, R.N.; Chaudhary, Santosh

    2009-01-01

    The flow of an electrically conducting fluid past a porous substrate attached to the flat plate with Beavers-Joseph boundary condition under the influence of a uniform transverse magnetic field has been studied. Taking suitable similar variables, the momentum equation is transformed to ordinary differential equation and solved by standard techniques. The energy equation is solved by considering two boundary layers, one in the porous substrate and the other above the porous substrate. The velocity and temperature distributions along with Nusselt number are discussed numerically and presented through graphs. (author)

  3. ANTI-VISUAL EXPERIENCE AND ANTI-AESTHETIC PLEASURE IN LINGUISTIC CONCEPTUALISM: JOSEPH KOSUTH

    OpenAIRE

    Erhun Şengül

    2013-01-01

    1960s is a period that art was reshaped especially in Europe and in America and that is fed by its countercultural discourses. Duchamp’s conception of “art as idea” has pointed art’s anti-objective and idea dimension by coinciding with fields such as politics, philosophy, sociology and psychology. Conceptual artists such as Mel Bochner, Joseph Kosuth, Robert Barry, Lawrance Weiner, Terry Atkinson, played important role in foundation of the group “Art and Language” in England in 1968. As descr...

  4. Nuclear safety analyses and core design calculations to convert the Texas A & M University Nuclear Science Center reactor to low enrichment uranium fuel. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Parish, T.A.

    1995-03-02

    This project involved performing the nuclear design and safety analyses needed to modify the license issued by the Nuclear Regulatory Commission to allow operation of the Texas A& M University Nuclear Science Center Reactor (NSCR) with a core containing low enrichment uranium (LEU) fuel. The specific type of LEU fuel to be considered was the TRIGA 20-20 fuel produced by General Atomic. Computer codes for the neutronic analyses were provided by Argonne National Laboratory (ANL) and the assistance of William Woodruff of ANL in helping the NSCR staff to learn the proper use of the codes is gratefully acknowledged. The codes applied in the LEU analyses were WIMSd4/m, DIF3D, NCTRIGA and PARET. These codes allowed full three dimensional, temperature and burnup dependent calculations modelling the NSCR core to be performed for the first time. In addition, temperature coefficients of reactivity and pulsing calculations were carried out in-house, whereas in the past this modelling had been performed at General Atomic. In order to benchmark the newly acquired codes, modelling of the current NSCR core with highly enriched uranium fuel was also carried out. Calculated results were compared to both earlier licensing calculations and experimental data and the new methods were found to achieve excellent agreement with both. Therefore, even if an LEU core is never loaded at the NSCR, this project has resulted in a significant improvement in the nuclear safety analysis capabilities established and maintained at the NSCR.

  5. Reactor core and initially loaded reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Koyama, Jun-ichi; Aoyama, Motoo.

    1989-01-01

    In BWR type reactors, improvement for the reactor shutdown margin is an important characteristic condition togehter with power distribution flattening . However, in the reactor core at high burnup degree, the reactor shutdown margin is different depending on the radial position of the reactor core. That is , the reactor shutdown margin is smaller in the outer peripheral region than in the central region of the reactor core. In view of the above, the reactor core is divided radially into a central region and as outer region. The amount of fissionable material of first fuel assemblies newly loaded in the outer region is made less than the amount of the fissionable material of second fuel assemblies newly loaded in the central region, to thereby improve the reactor shutdown margin in the outer region. Further, the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower portion of the first fuel assemblies is made smaller than the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower region of the second fuel assemblies, to thereby obtain a sufficient thermal margin in the central region. (K.M.)

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sekine, Katsuhisa.

    1987-01-01

    Purpose: To decrease the thickness of a reactor container and reduce the height and the height and plate thickness of a roof slab without using mechanical vibration stoppers. Constitution: Earthquake proofness is improved by filling fluids such as liquid metal between a reactor container and a secondary container and connecting the outer surface of the reactor container with the inner surface of the secondary container by means of bellows. That is, for the horizontal seismic vibrations, horizontal loads can be supported by the secondary container without providing mechanical vibration stoppers to the reactor container and the wall thickness can be reduced thereby enabling to simplify thermal insulation structure for the reduction of thermal stresses. Further, for the vertical seismic vibrations, verical loads can be transmitted to the secondary container thereby enabling to reduce the wall thickness in the same manner as for the horizontal load. By the effect of transferring the point of action of the container load applied to the roof slab to the outer circumferential portion, the intended purpose can be attained and, in addition, the radiation dose rate at the upper surface of the roof slab can be decreased. (Kamimura, M.)

  7. The Vanadium Window with special reference to Joseph and James Flannery's contribution to the American steel and radium industries

    International Nuclear Information System (INIS)

    Lubenau, J. O.; Mould, R. F.

    2008-01-01

    The discovery of vanadium is described and the founding of the American Vanadium Company by Joseph Flannery (1867-1920) and its headquarters building in Pittsburgh in which was the stained glass window depicting the origin of the name Vanadium. Company orders for vanadium steel were obtained for the Panama canal and from Henry Ford. When his sister was diagnosed with cancer, Joseph Flannery withdrew from his vanadium interests and founded the Standard Chemical and Radium Chemical Companies which were the major suppliers of radium in the USA in the 1920s (before the Union Minicre du Haut Katanga commenced its commercial operations), processed from American mined carnotite in Colorado and Utah. Significant contributions to these enterprises involving vanadium and radium were also made by Joseph's elder brother, James Flannery (1848-1920). (author)

  8. Iterative CT reconstruction with small pixel size: distance-driven forward projector versus Joseph's

    Science.gov (United States)

    Hahn, K.; Rassner, U.; Davidson, H. C.; Schöndube, H.; Stierstorfer, K.; Hornegger, J.; Noo, F.

    2015-03-01

    Over the last few years, iterative reconstruction methods have become an important research topic in x-ray CT imaging. This effort is motivated by increasing evidence that such methods may enable significant savings in terms of dose imparted to the patient. Conceptually, iterative reconstruction methods involve two important ingredients: the statistical model, which includes the forward projector, and a priori information in the image domain, which is expressed using a regularizer. Most often, the image pixel size is chosen to be equal (or close) to the detector pixel size (at field-of-view center). However, there are applications for which a smaller pixel size is desired. In this investigation, we focus on reconstruction with a pixel size that is twice smaller than the detector pixel size. Using such a small pixel size implies a large increase in computational effort when using the distance-driven method for forward projection, which models the detector size. On the other hand, the more efficient method of Joseph will create imbalances in the reconstruction of each pixel, in the sense that there will be large differences in the way each projection contributes to the pixels. The purpose of this work is to evaluate the impact of these imbalances on image quality in comparison with utilization of the distance-driven method. The evaluation involves computational effort, bias and noise metrics, and LROC analysis using human observers. The results show that Joseph's method largely remains attractive.

  9. Presenting Digital Archives with Historical GIS: Mapping Joseph Needham's Trips in WWII China

    Science.gov (United States)

    Wu, H.

    2017-12-01

    Since 2016, select groups of students (aged 14-17) from the Independent School Foundation Academy (ISF), Hong Kong, have been constructing a Historical GIS system for the Needham Research Institute (NRI), Cambridge, UK, during their annual summer school in Cambridge. Students read the diaries and reports of Joseph Needham, the Cambridge scientist who worked in China from 1943 to 1946 as the head of the Sino-British Science Cooperation Office, and mapped out both Needham's itineraries and the location of Chinese scientific institutions he visited. By taking part in this project, students learnt two sets of skills: the historian's skills of reading and analyzing primary sources, and the geographer's skills of creating datasets and maps with a GIS software. This project will be carried on in future years, to gradually include other trips Joseph Needham undertook in China in the second half of the 20th century, thus making an essential contribution to the digitalization and the diffusion of the NRI's archives. As a historical researcher in NRI and an educator, the presenter will offer some reflections on the benefit of historical GIS projects as a venue par excellence for research institutions and schools to join force, enhancing both academic research and teaching with an enlarged social impact.

  10. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

    After some remarks on the nuclear fuel, on the chain reaction control, on fuel loading and unloading, this article proposes descriptions of the design, principles and operations of different types of nuclear reactors as well as comments on their presence and use in different countries: pressurized water reactors (design of the primary and secondary circuits, volume and chemistry control, backup injection circuits), boiling water reactors, heavy water reactors, graphite and boiling water reactors, graphite-gas reactors, fast breeder reactors, and fourth generation reactors (definition, fast breeding). For these last ones, six concepts are presented: sodium-cooled fast reactor, lead-cooled fast reactor, gas-cooled fast reactor, high temperature gas-cooled reactor, supercritical water-cooled reactor, and molten salt reactor

  11. Recreating Religion: The Response to Joseph Smith’s Innovations in the Second Prophetic Generation of Mormonism

    OpenAIRE

    Blythe, Christopher James

    2011-01-01

    On June 27, 1844, Joseph Smith, the founder of The Church of Jesus Christ ofLatter-day Saints, was assassinated. In the wake of his death, a number of would-besuccessors emerged. Each of these leaders - part of what I call the second propheticgeneration - established a unique vision of Mormonism. In 1844, Mormonism was in the middle of a major shift in its character. JosephSmith’s death left numerous theological and practical questions unresolved. This thesis argues that, rather than merel...

  12. Catholic Enlightenment for children. Teaching religion to children in the Habsburg Empire from Joseph II to the Restoration

    Directory of Open Access Journals (Sweden)

    Simonetta Polenghi

    2016-05-01

    Full Text Available During Joseph II’s reign a deep cultural shift took place within the intellectual and religious establishment, with the acceptance of philosophical and pedagogical ideas that bore a distinctive Enlightenment and Protestant stamp. This cultural shift was applied to the teaching of religion by some relevant figures of the episcopal and pedagogical elites (J. A. Gall, F.M. Vierthaler, F. de Paula Gaheis, J. M. Leonhard. New handbooks and textbooks of the catechism were written which introduced new dialogic methods, more narrative, and borrowed Rochow’s typology of moral short stories. The content of Bishop Gall’s books was heavily rationalistic, whereas subsequent texts tried to balance reason and faith. Vierthaler, Gaheis, and Leonhard used a language that was more suitable for children and closer to the New Testament, with the use of parables and short stories. The so-called Socratic method was used in different ways by these authors.In the age of the Restoration, in spite of the process of school confessionalization, the heritage of the spirit of Enlightenment was still present, since by law the pedagogy taught in the Empire’s academic chairs and teacher training courses was the one defined by Milde, which bore a Kantian imprint, and stressed the importance of developing inner moral law in pupils. Leonhard was a follower of Milde, and his catechism, eventually approved for elementary schools for decades, bore this stamp.So at the end of the eighteenth and the beginning of the nineteenth centuries a new way of teaching religion was introduced, debated and contested in Habsburg Catholic territories. Rousseau’s and Salzmann’s theories were discussed; rationalism and faith, natural religion and revelation were confronted. In the end more attention was devoted to child psychology and language. The cultural fracture caused by Josephinism became less severe: orthodoxy was restored, but new pedagogical ideas actually entered the teaching of

  13. Aspects sociaux et religieux dans l’anthropologie pédagogique de Joseph Wresinski (Social and religious aspects in Joseph Wresinski’s pedagogical anthropology

    Directory of Open Access Journals (Sweden)

    Gabriella Kiss

    2016-12-01

    Full Text Available Joseph Wresinski founded the ATD-Fourth World Movement in France in 1957 with the aim of eradicating poverty, as well as the exclusion and the lack of rights that go with it, in order to be able to model the structure of a society that has the most disadvantaged people in its centre. As an ordained priest of the Catholic Church, he created a secular organisation whose practice and ensuing principles are shaped by this peculiar duality. In order to demonstrate this facet, the first part of the present study gives a brief overview of Wresinski’s career, highlighting how the personal aspects of his life had influenced his views concerning the poorest, and more specifically, the principles and objectives of the Movement he founded. Thereafter, I address the particularities of the Movement, emphasizing its religious and social dimensions, in relation to the secular nature of French society. The two subchapters of the third part describe the two factors of the primordial relationship that constitutes the two, interdependent pillars of the Movement, emphasizing the relevant features of Wresinski’s vision concerning the poorest and also the volunteers engaged in the Movement. Finally, I intend to show how the pedagogical anthropology of Wresinski, with his radical interpretation of the Gospel, positions in its centre the man who, disfigured by poverty, is still the most authentic bearer of universal humanity, as he inseparably incorporates human rights and the divine filiation.

  14. Reactor core for LMFBR type reactors

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Azekura, Kazuo; Kurihara, Kunitoshi; Bando, Masaru; Watari, Yoshio.

    1987-01-01

    Purpose: To reduce the power distribution fluctuations and obtain flat and stable power distribution throughout the operation period in an LMFBR type reactor. Constitution: In the inner reactor core region and the outer reactor core region surrounding the same, the thickness of the inner region is made smaller than the axial height of the reactor core region and the radial width thereof is made smaller than that of the reactor core region and the volume thereof is made to 30 - 50 % for the reactor core region. Further, the amount of the fuel material per unit volume in the inner region is made to 70 - 90 % of that in the outer region. The difference in the neutron infinite multiplication factor between the inner region and the outer region is substantially constant irrespective of the burnup degree and the power distribution fluctuation can be reduced to about 2/3, by which the effect of thermal striping to the reactor core upper mechanisms can be moderated. Further, the maximum linear power during operation can be reduced by 3 %, by which the thermal margin in the reactor core is increased and the reactor core fuels can be saved by 3 %. (Kamimura, M.)

  15. De orgelmakers Joseph en Adam Binvignat : Maastrichtse orgelbouw in de nadagen van het Ancien Regime en in het begin van de moderne tijd

    NARCIS (Netherlands)

    Syrier, R.G.J.B.

    2014-01-01

    Joseph Binvignat was born in Attigny on 26 June 1755 and had been apprenticed to the Reims organ maker Louis Péronard. The first record of his presence in Maastricht is a document dated 7 September 1774, which mentions a tender submitted by Joseph Binvignat and Lambert Houtappel for repairs to the

  16. Chief Joseph Kokanee Enhancement Project; Strobe Light Deterrent Efficacy Test and Fish Behavior Determination at the Grand Coulee Dam Third Powerplant Forebay, 2002-2003 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, R.; McKinstry, C.; Simmons, C. (Pacific Northwest National Laboratory)

    2003-01-01

    Since 1995, the Confederated Tribes of the Colville Reservation (Colville Confederated Tribes) have managed the Chief Joseph Kokanee Enhancement Project as part of the Northwest Power Planning Council (NWPPC) Fish and Wildlife Program. Project objectives have focused on understanding natural production of kokanee (a land-locked sockeye salmon) and other fish stocks in the area above Grand Coulee and Chief Joseph Dams on the Columbia River. A 42-month investigation concluded that entrainment at Grand Coulee Dam ranged from 211,685 to 576,676 fish annually. Further analysis revealed that 85% of the total entrainment occurred at the dam's third powerplant. These numbers represent a significant loss to the tribal fisheries upstream of the dam. In response to a suggestion by the NWPPC Independent Scientific Review Panel, the scope of work for the Chief Joseph Kokanee Enhancement Project was expanded to include a multiyear pilot test of a strobe light system to help mitigate fish entrainment. This report details the work conducted during the second year of the study by researchers of the Colville Confederated Tribes in collaboration with the Pacific Northwest National Laboratory. The 2002 study period extended from May 18 through July 30. The objective of the study was to determine the efficacy of a prototype strobe light system to elicit a negative phototactic response in kokanee and rainbow trout. The prototype system consisted of six strobe lights affixed to an aluminum frame suspended vertically underwater from a barge secured in the center of the entrance to the third powerplant forebay. The lights, controlled by a computer, were aimed to illuminate a specific region directly upstream of the barge. Three light level treatments were used: 6 of 6 lights on, 3 of 6 lights on, and all lights off. These three treatment conditions were applied for an entire 24-hr day and were randomly assigned within a 3-day block throughout the study period. A seven

  17. A multi-purpose reactor

    International Nuclear Information System (INIS)

    Changwen Ma

    2000-01-01

    An integrated natural circulation self pressurized reactor can be used for sea water desalination, electrogeneration, ship propulsion and district or process heating. The reactor can be used for ship propulsion because it has following advantages: it is a integrated reactor. Whole primary loop is included in a size limited pressure vessel. For a 200 MW reactor the diameter of the pressure vessel is about 5 m. It is convenient to arranged on a ship. Hydraulic driving facility of control rods is used on the reactor. It notably decreases the height of the reactor. For ship propulsion, smaller diameter and smaller height are important. Besides these, the operation reliability of the reactor is high enough, because there is no rotational machine (for example, circulating pump) in safety systems. Reactor systems are simple. There are no emergency water injection system and boron concentration regulating system. These features for ship propulsion reactor are valuable. Design of the reactor is based on existing demonstration district heating reactor design. The mechanic design principles are the same. But boiling is introduced in the reactor core. Several variants to use the reactor as a movable seawater desalination plant are presented in the paper. When the sea water desalination plant is working to produce fresh water, the reactor can supply electricity at the same time to the local electricity network. Some analyses for comprehensive application of the reactor have been done. Main features and parameters of the small (Thermopower 200 MW) reactor are given in the paper. (author)

  18. M and c'99 : Mathematics and computation, reactor physics and environmental analysis in nuclear applications, Madrid, September 27-30, 1999

    International Nuclear Information System (INIS)

    Aragones, J. M.; Ahnert, C.; Cabellos, O.

    1999-01-01

    The international conference on mathematics and computation, reactor physics and environmental analysis in nuclear applications in the biennial topical meeting of the mathematics and computation division of the American Nuclear Society. (Author)

  19. M and c'99 : Mathematics and computation, reactor physics and environmental analysis in nuclear applications, Madrid, September 27-30, 1999

    Energy Technology Data Exchange (ETDEWEB)

    Aragones, J. M.; Ahnert, C.; Cabellos, O.

    1999-07-01

    The international conference on mathematics and computation, reactor physics and environmental analysis in nuclear applications in the biennial topical meeting of the mathematics and computation division of the American Nuclear Society. (Author)

  20. H Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The H Reactor was the first reactor to be built at Hanford after World War II.It became operational in October of 1949, and represented the fourth nuclear reactor on...

  1. Post irradiation examination of RAF/M steels after fast reactor irradiation up to 33 dpa and < 340 C (ARBOR1). RAFM steels. Metallurgical and mechanical characterisation. Final report for TW2-TTMS-001b, D9

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, C. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). EURATOM, Inst. fuer Materialforschung, Programm Kernfusion

    2010-07-01

    In an energy generating fusion reactor structural materials will be exposed to very high dpa-levels of about 100 dpa. Due to this fact and because fast reactor irradiation facilities in Europe are not available anymore, a reactor irradiation at the State Scientific Center of the Russian Federation with its Research Institute of Atomic Reactors (SSC RIAR), Dimitrovgrad, had been performed in the fast reactor BOR 60 with an instrumented test rig. This test rig contained tensile, impact and Low Cycle Fatigue type specimens used at FZK since many years. Samples of actual Reduced Activation Ferritic/Martensitic (RAF/M) -steels (e.g. EUROFER 97) had been irradiated in this reactor at a lower temperature (< 340 C) up to a damage of 33 dpa. This irradiation campaign was called ARBOR 1. Starting in 2003 one half of these irradiated samples were post irradiation examined (PIE) by tensile testing, low cycle fatigue testing and impact testing under the ISTC Partner Contract 2781p in the hot cells of SSC RIAR. In the post irradiation instrumented impact tests a significant increase in the Ductile to Brittle Transition Temperature as an effect of irradiation has been detected. During tensile testing the strength values are increasing and the strain values reduced due to substantial irradiation hardening. The hardening rate is decreasing with increasing damage level, but it does not show saturation. The low cycle fatigue behaviour of all examined RAF/M - steels show at total strain amplitudes below 1 % an increase of number of cycles to failure, due to irradiation hardening. From these post irradiation experiments, like tensile, low cycle fatigue and impact tests, radiation induced design data, e.g. for verification of design codes, can be generated.

  2. Compact torsatron reactors

    International Nuclear Information System (INIS)

    Lyon, J.F.; Carreras, B.A.; Lynch, V.E.; Tolliver, J.S.; Sviatoslavsky, I.N.

    1988-05-01

    Low-aspect-ratio torsatron configurations could lead to compact stellarator reactors with R 0 = 8--11m, roughly one-half to one-third the size of more conventional stellarator reactor designs. Minimum-size torsatron reactors are found using various assumptions. Their size is relatively insensitive to the choice of the conductor parameters and depends mostly on geometrical constraints. The smallest size is obtained by eliminating the tritium breeding blanket under the helical winding on the inboard side and by reducing the radial depth of the superconducting coil. Engineering design issues and reactor performance are examined for three examples to illustrate the feasibility of this approach for compact reactors and for a medium-size (R 0 ≅ 4 m,/bar a/ /approx lt/ 1 m) copper-coil ignition experiment. 26 refs., 11 figs., 7 tabs

  3. Defining American Heroes: Analyzing the Metamorphosis of the War Hero in Twentieth Century War Films Using Joseph Campbell's, "Hero's Journey."

    Science.gov (United States)

    Frith, Luci A.

    In "The Hero's Journey" Joseph Campbell identifies the patterns that inform the myths of the "hero" throughout recorded history. By using Campbell's template, this paper examines how the American war hero is portrayed and has been portrayed in film. The paper states that Americans not only define their war heroes in films but…

  4. Joseph V. Denney, the Land-Grant Mission, and Rhetorical Education at Ohio State: An Institutional History

    Science.gov (United States)

    Mendenhall, Annie S.

    2011-01-01

    This essay provides an account of The Ohio State University's (OSU) rhetoric department during the tenure of Joseph Villiers Denney, arguing that he appropriated and repurposed national trends in education and rhetoric in ways that complicate the narrative of rhetoric and composition's decline in the late nineteenth century. In this essay, the…

  5. Diagnosis of Joseph disease by means of N-isopropyl-p-[123I]iodoamphetamine (IMP) SPECT

    International Nuclear Information System (INIS)

    Takahashi, Naoya; Nishihara, Mamiko; Odano, Ikuo; Sakai, Kunio; Yuasa, Tatsuhiko.

    1993-01-01

    Using N-isopropyl-p-[ 123 I]iodoamphetamine (IMP) and single-photon-emission computed tomography (SPECT), we studied the regional cerebral blood flow (rCBF) in 4 Japanese patients who had been clinically diagnosed as having Joseph disease. This is the first report of rCBF measurement by means of [ 123 I]-IMP SPECT in patients with Joseph disease. Cerebellar atrophy was evaluated by means of a 5-rating scale as defined by X-ray computed tomography (X-CT). As compared with 10 normal controls (mean cerebellar CBF±SD: 66.9±6.6 ml/100 g/min), the regional CBF of the patients with Joseph disease was found to decrease significantly in the cerebellum (mean±SD: 52.8±5.3 ml/100 g/min). However, no significant relationship was found between the decrease in rCBF in the cerebellum and the degree of cerebellar atrophy as shown by X-CT. The regional CBF in the cerebellum decreased little in one patient who had severe cerebellar atrophy or in two who showed moderate atrophy. [ 123 I]-IMP SPECT demonstrates the pathological and metabolic changes in the cerebellum that do not appear on X-CT or MRI. IMP SPECT is thus shown to be useful for the diagnosis of patients with Joseph disease. (author)

  6. Operatic films: a comparative study of Don Giovanni by Joseph Losey and Juan by Kasper Holten

    Directory of Open Access Journals (Sweden)

    Isabel VILLANUEVA BENITO

    2017-12-01

    Full Text Available From an artistic point of view, the adaptation of an opera to the cinema, traditionally has been considered a complex and controversial process. Don Giovanni, of W.A. Mozart is one of the operas that more audiovisual versions has generated during the centuries XX and XXI, although very few films have finally been taken to the screen. This paper is focused on comparing the audiovisual versions Don Giovanni, by Joseph Losey (1979, and Juan by Kasper Holten (2010. Through a quantitative and qualitative methodology based on content analysis, this research reflects on the degree of intervention exercised by the language and audiovisual format used in the process of reinterpretation of the pre-existing operatic text.

  7. Sympathetic science: Charles Darwin, Joseph Hooker, and the passions of Victorian naturalists.

    Science.gov (United States)

    Endersby, Jim

    2009-01-01

    This essay examines the complex tangle of emotional and scientific attachments that linked Darwin and botanist Joseph Dalton Hooker. Analyzing their roles as husbands, fathers, and novel readers demonstrates that possessing and expressing sympathy was as important for Victorian naturalists as it was for Victorian husbands. Sympathy was a scientific skill that Victorian naturalists regarded as necessary to fully understand the living world; although sympathy became increasingly gendered as feminine over the course of the century, its importance to male naturalists requires us to rethink the ways gender roles were negotiated in Victorian Britain. Botany was, for men like Darwin and Hooker, an acceptably masculine pursuit that nevertheless allowed--and even required--them to be sensitive and sympathetic.

  8. Joseph Jastrow, the psychology of deception, and the racial economy of observation.

    Science.gov (United States)

    Pettit, Michael

    2007-01-01

    This article reconstructs the recurring themes in the career of Joseph Jastrow, both inside and outside the laboratory. His psychology of deception provides the bridge between his experimental and popular pursuits. Furthermore, Jastrow's career illustrates the complex ways in which scientific psychology and pragmatist philosophy operated within the constraints of a moral economy deeply marked by notions of "race." Psychological investigations of deception were grafted onto two of the human sciences' leading tools: the evolutionary narrative and the statistical analysis of populations. Such associations abetted the racialization of the acts of deceiving and being deceived. These connections also were used to craft moral lessons about how individuals ought to behave in relationship to the aggregate population and natural selection's endowment.

  9. Joseph McCabe: A Forgotten Early Populariser of Science and Defender of Evolution

    Science.gov (United States)

    Cooke, Bill

    2010-05-01

    Joseph McCabe (1867-1955) was one of the most prolific and gifted polymaths of the twentieth century. Long before such a thing was thought respectable, and almost a century before any university established a chair in the public understanding of science, McCabe made a living as a populariser of science and a critic of philosophical and religious obscurantism. Through the first half of the twentieth century he wrote countless cheap and widely distributed books and pamphlets for those whose thirst for knowledge exceeded the money or time they could devote to such pursuits. This article will detail, and give some assessment of, McCabe’s career as a populariser of science and expositor of evolutionary theory and its philosophical, religious and cultural ramifications.

  10. Joseph Swan (1791-1874): pioneer of research on peripheral nerves.

    Science.gov (United States)

    Barton, N J; Smith, B D

    2008-06-01

    Joseph Swan was born in 1791 and appointed surgeon to Lincoln County Hospital in 1814. In addition to his clinical work, he carried out what were probably the first animal experiments on nerve injuries. These were mostly on rabbits, in which the sciatic nerves were partly or wholly divided, had a section excised, or were ligated. He found that regeneration could occur, even after neurectomy. He reported these results, together with his experience in human patients and the effects of neurectomy in a horse, in an essay of 1819, which won the Jacksonian Prize of the Royal College of Surgeons of England and is still preserved there. In 1827 he moved to London, where he devoted himself mainly to dissections of the nervous system and was active in the College. He retired to Filey in Yorkshire, where he died in 1874.

  11. [Dr. Joseph Chazanowicz (1844-1919) and the National Library in Jerusalem].

    Science.gov (United States)

    Ohry, Avi

    2014-01-01

    Dr. Joseph Chazanowicz (1844-1919), was a Russian physician, and founder of the Jewish National Library in JerusaLem. After completing his studies at the Jewish school and at the gymnasium of Grodno, Chazanowicz went to Königsberg, Germany to study medicine and finished his studies in 1872. Returning to Russia, he began to practice at Byelostok's Jewish hospital. Chazanowicz founded the Hovevei Ziyyon ["Lovers of Zion"] society and also the Linat Ha-Zedek ("Hospice for the Poor")--caring for the poor. In 1890 he visited Palestine and conceived the idea of founding a library in Jerusalem, together with the B'nai B'rith organization. In 1896 he sent his large collection of books, amounting to nearly 10,000 volumes, to Jerusalem as the beginning of the Abarbanel library. The enlargement of this library and the collection of funds to erect a special building for it became the life-work of Chazanowicz.

  12. Acquisition of wood fuel at the Joseph C. McNeil Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Kropelin, W. [Burlington Electric Dept., VT (United States)

    1993-12-31

    The Joseph C. McNeil Generating Station is the world`s largest single boiler, municipally-owned, wood-fired electrical generating plant. The 50 megawatt McNeil Station is located in Burlington, Vermont and is owned by several Vermont public and private electric utilities. The operator and majority owner is the City of Burlington Electric Department (BED). Wood fuel procurement for the McNeil Station has been conducted in an environmentally sensitive way. Harvesting is carried out in conformance with a comprehensive wood chip harvesting policy and monitored by professional foresters. Unpredictable levels of Station operation require rigid adherence to a wood storage plan that minimizes the risk of over heating and spontaneous combustion of stockpiled fuel.

  13. Laparoscopic Scar: a mimicker of Sister Mary Joseph's nodule on positron emission tomography/CT

    International Nuclear Information System (INIS)

    Setty, B.; Blake, M.A.; Holalkere, N.S.; Blaszkowsky, L.S.; Fischman, A.

    2006-01-01

    Positron emission tomography/CT is an established imaging method in the diagnosis and staging of cancers. 18 F -fluoro-2-deoxy-D-glucose (FDG) is the most commonly used radiotracer in positron emission tomography/CT. It is a tumour viability agent and usually its uptake within a lesion reflects the presence of a viable tumour tissue. However, false-positive FDG uptake is known to occur in benign processes of either inflammatory or infectious aetiology. We describe FDG uptake at the site of laparoscopic scar that mimicked Sister Mary Joseph's nodule in a patient with gastric adenocarcinoma. Here, the knowledge of the patient's history and subtle imaging findings helped in accurate staging of the patient. In this case report, we emphasize the value of the knowledge of the patient history and awareness of different pitfalls of FDG to achieve a correct diagnosis on positron emission tomography/CT

  14. Catherine the Great in the writings of Charles-Joseph Lamoral, 7th Prince de Ligne

    Directory of Open Access Journals (Sweden)

    Joanna Pychowska

    2012-01-01

    Full Text Available Charles-Joseph de Ligne (1735-1814, a Wallon and European Prince, subject of the Austro-Hungary Empire, a heartbreaker of the French Europe, is considered the most famous representative of literary cosmopolitanism. War, love and writing were inseparable in his life. He took part in numerous military campaigns, serving both Austria and Russia, as a Russian colonel, a commander of the order of Maria Theresa, and an Austrian fi eld marshal. He authored various texts related to war; he admired heroism of Charles II, Conde, the tactics of Frederick II, the strategies of Napoleon, Catherine II. The latter was immportalized in de Ligne’s various texts representing different literary genres. The Prince was clearly fascinated by the Empress, and he depicted her in a positive light as an educated person, both agreable and determined. Can we, however, talk about the documentary character of his work ? Instead, the Prince seems to be a documentalist-interpreter.

  15. [Advances in Neurological Therapeutics for Friedreich Ataxia and Machado-Joseph Disease].

    Science.gov (United States)

    Yabe, Ichiro; Sasaki, Hidenao

    2017-08-01

    We reviewed advances in therapeutics for both Friedreich ataxia and Machado-Joseph disease. Various clinical trials have been carried out, mainly for Friedreich ataxia; however, the therapeutic reports from these trials have not provided much evidence for success. Some interesting clinical trials have been reported, and further developments are expected. Regenerative therapy using umbilical cord mesenchymal stem cells and a therapeutic study investigating a new pathomechanism in animal and/or cell culture studies were reported. We expect that these results will translate to therapeutic strategies for patients with these disorders. In addition, biomarkers play an important role when novel treatments are discovered and clinical trials are performed: hence at present, a number of biomarkers such as gait analysis by triaxial accelerometers and prism adaptation of hand-reaching movements, are being examined.

  16. Joseph Henry’s role in the discovery of electromagnetic induction

    International Nuclear Information System (INIS)

    Smith, Glenn S

    2017-01-01

    The discovery of electromagnetic induction in the early part of the 19th century is one of the greatest scientific achievements of all time, and it has had tremendous technological consequences. The credit for this discovery rightfully goes to the great English experimental physicist Michael Faraday. However, the American physicist Joseph Henry made some observations comparable to Faraday’s at nearly the same time, and for that reason, Faraday and Henry are often considered to be co-discoverers of some aspects of electromagnetic induction. We examine Henry’s early research on electromagnetism, starting from his efforts to improve the electromagnet, which led directly to his investigations of induction. We describe his earliest experiments on both mutual and self-induction, and pay particular attention to the relationship of Henry’s research to that of Faraday. The approach is one in which the experiments are described and then analysed using modern theory and terminology. (paper)

  17. The possibility of creating a new low power nuclear facility with slightly enriched nuclear fuel on the basis of the decommissioned IRT-M reactor intended for applied purposes

    International Nuclear Information System (INIS)

    Abramidze, Sh.P.; Katamadze, N.M.; Kiknadze, G.G.; Rostomashvili, Z.I.; Saralidze, Z.K.

    2002-01-01

    Nearly 50 years have passed since the appearance of the first nuclear research reactors. Most of them have completed their operating life and must be dismantled. But it is known that the dismantling of permanently shut down nuclear reactors is a very complex process, full realization that it generates a lot of radioactive waste (both solid and liquid), it is connected with high financial expenditures, and its solution is apparently beyond the possibilities of many countries, including Georgia In the given paper we consider a radiologically safe, ecologically clean and economically beneficial version of the decommissioning of the IRT-M nuclear research reactor and the stages of its implementation that are not connected with the dismantling of its highly radioactive technological components. We justify the possibility of creating a new Low Power Nuclear Facility on the basis of the decommissioned IRT-M reactor to solve the problems of applied nature in different fields of science and technology being very important for Georgia. (author)

  18. Ortodoxia y heterodoxia en la filosofía de Joseph de Maistre. Sus antecedentes y sus huellas en el pensamiento contrarrevolucionario español (1833-1936)

    OpenAIRE

    Fornés Murciano, Antonio

    2015-01-01

    Joseph de Maistre va ser un pensador original, d'una profunditat major de la que freqüentment se li concedeix i posseïdor, a més, d'una prosa excepcional. Aquest estudi pretén mostrar d'una banda que la seva filosofia i la seva lluita a favor de l'ortodòxia polític-religiosa neix, paradoxalment, de fonts obertament heterodoxes, i d'un altre costat que el seu discurs ideològic i antirevolucionari, nodrit per la força d'aquest ascendent, va influir de forma determinant en els apriorismes foname...

  19. Design and fabrication report on capsule (11M 19K for out of pile test) for irradiation testing of research reactor materials at HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Kim, B.G.; Yang, S.W.; Park, S.J.; Shim, K.T.; Choo, K.N.; Oh, J.M.; Lee, B.C.; Choi, M.H.; Kim, D.J.; Kim, J.M.; Kang, S.H.; Chun, Y.B.; Kim, T.K.; Jeong, Y.H.

    2012-05-15

    As a part of the research reactor development project with a plate type fuel, the irradiation tests of graphite (Gr), beryllium (Be), and zircaloy 4 materials using the capsule have been investigating to obtain the mechanical characteristics such as an irradiation growth, hardness, swelling and tensile strength at the temperature below 100 .deg. C and the 30 MW reactor power. Then, A capsule to be able to irradiate materials(graphite, Be, zircaloy 4) under 100 .deg. C at the HANARO was designed and fabricated. After performing out of pile testing in single channel test loop by using the capsule, the final design of the capsules to be irradiated in CT and IR2 test hole of HANARO was approved, and 2 sets of capsule were fabricated. These capsules will be loaded in CT and IR2 test hole of HANARO, and be started the irradiation from the end of June, 2012. After performing the irradiation testing of 2 sets of capsule, PIE (Post Irradiation Examination) on irradiated specimens (Gr, Be, and zircaloy 4) will be carry out in IMEF (Irradiated Material Examination Facility). So, the irradiation testing will be contributed to obtain the characteristic data induced neutron irradiation on Gr, Be, and zircaloy 4. And then, it is convinced that these data will be also contributed to obtain the license for JRTR (Jordan Research and Training Reactor) and new research reactor in Korea, and export research reactors.

  20. Minimization of the external heating power by long fusion power rise-up time for self-ignition access in the helical reactor FFHR2m

    International Nuclear Information System (INIS)

    Mitarai, O.; Sagara, A.; Chikaraishi, H.; Imagawa, S.; Shishkin, A.A.; Motojima, O.

    2006-10-01

    Minimization of the external heating power to access self-ignition is advantageous to increase the reactor design flexibility and to reduce the capital and operating costs of the plasma heating device in a helical reactor. In this work we have discovered that a larger density limit leads to a smaller value of the required confinement enhancement factor, lower density limit margin reduces the external heating power, and over 300 s of the fusion power rise-up time makes it possible to reach a minimized heating power. While the fusion power rise-up time in a tokamak is limited by the OH transformer flux or the current drive capability, any fusion power rise-up time can be employed in a helical reactor for reducing the thermal stresses of the blanket and shields, because the confinement field is generated by the external helical coils. (author)

  1. Determination of oxygen potentials and O/M ratios of oxide nuclear reactor fuels by means of an automated solid state galvanic cell

    International Nuclear Information System (INIS)

    Toci, F.; Cambini, M.

    1987-01-01

    An automated version of the electromotive force (emf) cell for the determination of oxygen activities and oxygen to metal ratios of oxide nuclear reactor fuel, irradiated or not, is reported together with some measurements. 9 figs., 17 refs. In appendix a method is described for preparing suitable electrolyte crucibles

  2. Resident fish stock status above Chief Joseph and Grand Coulee dams : 2000 annual report; ANNUAL

    International Nuclear Information System (INIS)

    Lockwood, N.; McLellan, J.; Crossley, B.

    2001-01-01

    The Resident Fish Stock Status above Chief Joseph and Grand Coulee Dams Project, commonly known as the Joint Stock Assessment Project (JSAP) is a management tool using ecosystem principles to manage artificial fish assemblages and native fish in altered environments existing in the Columbia River System above Chief Joseph and Grand Coulee Dams (blocked area). The three-phase approach of this project will enhance the fisheries resources of the blocked area by identifying data gaps, filling data gaps with research, and implementing management recommendations based on research results. The Blocked Area fisheries information housed in a central location will allow managers to view the entire system while making decisions, rather than basing management decisions on isolated portions of the system. The JSAP (NWPPC program measure 10.8B.26) is designed and guided jointly by fisheries managers in the blocked area and the Columbia Basin blocked area management plan (1998). The initial year of the project (1997) identified the need for a central data storage and analysis facility, coordination with the StreamNet project, compilation of blocked area fisheries information, and a report on the ecological condition of the Spokane River System. These needs were addressed in 1998 by acquiring a central location with a data storage and analysis system, coordinating a pilot project with StreamNet, compiling fisheries distribution data throughout the blocked area, identifying data gaps based on compiled information, and researching the ecological condition of the Spokane River. In order to ensure that any additional information collected throughout the life of this project will be easily stored and manipulated by the central storage facility, it was necessary to develop standardized methodologies between the JSAP fisheries managers. The use of common collection and analytical tools is essential to the process of streamlining joint management decisions. In 1999 and 2000 the project

  3. Resident Fish Stock Status above Chief Joseph and Grand Coulee Dams; 2000 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Lockwood, Jr., Neil [Kalispel Tribe of Indians, Usk, WA (United States); McLellan, Jason G [Washington Department of Fish and Wildlife, Spokane, WA (United States); Crossley, Brian [Spokane Tribe of Indians, Department of Natural Resources, Wellpinit, WA (United States); O' Connor, Dick

    2001-01-01

    The Resident Fish Stock Status above Chief Joseph and Grand Coulee Dams Project, commonly known as the Joint Stock Assessment Project (JSAP) is a management tool using ecosystem principles to manage artificial fish assemblages and native fish in altered environments existing in the Columbia River System above Chief Joseph and Grand Coulee Dams (blocked area). The three-phase approach of this project will enhance the fisheries resources of the blocked area by identifying data gaps, filling data gaps with research, and implementing management recommendations based on research results. The Blocked Area fisheries information housed in a central location will allow managers to view the entire system while making decisions, rather than basing management decisions on isolated portions of the system. The JSAP (NWPPC program measure 10.8B.26) is designed and guided jointly by fisheries managers in the blocked area and the Columbia Basin blocked area management plan (1998). The initial year of the project (1997) identified the need for a central data storage and analysis facility, coordination with the StreamNet project, compilation of blocked area fisheries information, and a report on the ecological condition of the Spokane River System. These needs were addressed in 1998 by acquiring a central location with a data storage and analysis system, coordinating a pilot project with StreamNet, compiling fisheries distribution data throughout the blocked area, identifying data gaps based on compiled information, and researching the ecological condition of the Spokane River. In order to ensure that any additional information collected throughout the life of this project will be easily stored and manipulated by the central storage facility, it was necessary to develop standardized methodologies between the JSAP fisheries managers. The use of common collection and analytical tools is essential to the process of streamlining joint management decisions. In 1999 and 2000 the project

  4. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2002-01-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

  5. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  6. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

  7. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  8. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

    Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

  9. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  10. Colonel Joseph J. Reynolds and the Saint Patrick's Day Celebration on Powder River Battle of Powder River (Montana, 17 March 1876)

    National Research Council Canada - National Science Library

    Hedegaard, Michael

    2001-01-01

    The Battle of Powder River occurred on 17 March 1876 in southeastern Montana. Historians and researchers have consistently overlooked the importance of this battle on the outcome of the Great Sioux War of 1876. Colonel Joseph J...

  11. Atrazine Concentrations in Stream Water and Streambed Sediment Pore Water in the St. Joseph and Galien River Basins, Michigan and Indiana, May 2001 - September 2003

    National Research Council Canada - National Science Library

    Duris, Joseph W; Reeves, Howard W; Kiesler, James L

    2004-01-01

    The U.S. Geological Survey (USGS) sampled multiple stream sites across the St. Joseph and Galien River Basins to detect and quantify the herbicide atrazine using a field enzyme-linked immunosorbent assay (ELISA) triazine test...

  12. Review: Joseph Patrick Ganahl, Corruption, Good Governance, and the African State: A Critical Analysis of the Political-Economic Foundations of Corruption in Sub-Saharan Africa (2013)

    OpenAIRE

    Reinhart Kößler

    2015-01-01

    Review of the monograph:Joseph Patrick Ganahl, Corruption, Good Governance, and the African State: A Critical Analysis of the Political-Economic Foundations of Corruption in Sub-Saharan Africa, Potsdam: Potsdam University Press, 2013, ISBN 9783869562483, 300 pp.

  13. The works of Joseph and Michael Haydn in Ondřej Horník's collection

    Czech Academy of Sciences Publication Activity Database

    Freemanová, Michaela

    2017-01-01

    Roč. 9, 1-2 (2017), s. 14-23 ISSN 1803-7828 Institutional support: RVO:68378076 Keywords : music manuscripts * Joseph Haydn * Michael Haydn * Ondřej Horník's collection * church music Subject RIV: AL - Art, Architecture, Cultural Heritage OBOR OECD: Performing arts studies ( Music ology, Theater science, Dramaturgy) http://www.nm.cz/publikace/archiv.php?id=16

  14. Euroopal jätkub väljakutseid ka peale laienemist / Joseph Daul ; interv. Kaja Sõrg

    Index Scriptorium Estoniae

    Daul, Joseph

    2008-01-01

    Euroopa Parlamendi Euroopa Rahvapartei ja Euroopa Demokraatide fraktsiooni esimees Joseph Daul vastab küsimustele, mis puudutavad fraktsiooni järgnevate aastate prioriteete, fraktsiooni peamisi saavutusi käesoleva koosseisu ajal, Euroopa ühise põllumajanduspoliitika tulevikku, fraktsioonikaaslase Tunne Kelami osalust fraktsiooni töös ning Euroopa Parlamendi ametliku asukoha võimalikku viimist Strasbourg'ist Brüsselisse

  15. War, sanity, and the Nazi mind: the last passion of Joseph Jastrow.

    Science.gov (United States)

    Behrens, Peter J

    2009-11-01

    The career of Joseph Jastrow (1863-1944) spanned more than 50 years in service to psychology. For 40 years he represented academic psychology at the University of Wisconsin as chair of the psychology department (1886 to 1927), but also was never far from popularizing psychology through books, articles, public lectures, newspaper columns, and finally radio lectures (e.g., Jastrow, 1900, 1935b). Providing a scientific and progressive psychology for the general public was always a strong penchant for Jastrow on several subjects, such as spiritualism (Jastrow, 1911) and effective living (Jastrow, 1935b). About 1939, while he was well into his 70s, his efforts focused on exposing the menace that Adolf Hitler and Nazism posed, so he undertook to enlist prominent editors to publish his work, Hitler: Mask and Myth, as articles or a book. He was not successful in gaining support for the project. His failing can be understood from the perspectives of the American market for Hitler material, the shortcomings of the manuscript, and how he represented psychology to the American public.

  16. Joseph John Thomson's models of matter and radiation in the early 1890s.

    Science.gov (United States)

    Bordoni, Stefano

    In the late nineteenth century, Joseph John Thomson moved away from Maxwell's specific theoretical models of matter and energy, even though he continued to rely on the general framework of Maxwell's electromagnetic theory. In his 1893 book, he accomplished the conceptual drift towards a discrete model for matter, electricity, and fields. In Thomson's model, energy was linked to tubes of force, in particular to the aether contained in them and surrounding them: the energy was the kinetic energy of aether, of both a rotational and translational kind. Starting from Maxwell's electromagnetic fields, namely stresses propagating through a continuous solid medium, Thomson arrived at a representation of fields as a sea of discrete units carrying energy and momentum. He tried to transform Maxwell's theory into a unified picture in which atomic models of matter stood beside atomic models of fields. In 1904 his interpretation of X-rays was based on the integration between two complementary features of electromagnetic radiation, the continuity and the discreteness, and on some kind of fibrous aether. In recent secondary literature, the problematic conceptual link between J. J. Thomson's theory and contemporary theories on electromagnetic radiation has been underestimated. On the contrary, in the first half of the twentieth century, some physicists inquired into that link, and a widespread debate emerged, misunderstandings included.

  17. Joseph Carpue's file drawer experiment – A murder mystery from 1801

    Directory of Open Access Journals (Sweden)

    M. Felix Freshwater

    2015-12-01

    Full Text Available Today unpublished or “file drawer” experiments are the impetus for trial registration and reporting of all results. In 1801, Joseph Carpue, the father of modern plastic surgery, did a file drawer experiment for Benjamin West, who was President of the Royal Academy of Arts. George III had commissioned West to create the largest stained glass window ever created whose theme, the Crucifixion, was based upon Michelangelo's drawing. Subsequently, West suffered a series of political, professional and economic setbacks. In the summer of 1801, West's project was delayed. By the fall, West hoped that independent scientific confirmation of his design could salvage the project. West approached Carpue who obtained a murderer's fresh corpse that he crucified and documented the results with plaster casts created by sculptor Thomas Banks. Carpue's experiment showed that West's window design wrongly depicted the Crucifixion because West had posed the hands and shoulders incorrectly. West died in 1820 without ever being associated with Carpue's experiment. Carpue's obituary in The Lancet in 1846 contained Carpue's handwritten note that described the experiment but not West's Royal commission. As no records or publications associate the cast with West project, this can be considered to be a file drawer experiment. After 1801, West made further drawings of the Crucifixion that showed the figures in the same position as the cast. Nineteenth century auction catalogues suggest that West made a corrected Crucifixion painting, but its current location remains a mystery.

  18. Inpatient management of borderline personality disorder at Helen Joseph Hospital, Johannesburg

    Directory of Open Access Journals (Sweden)

    Laila Paruk

    2016-06-01

    Full Text Available Objective: The aim of this report was to establish a profile of patients with borderline personality disorder (BPD admitted to the acute inpatient psychiatric assessment unit at the Helen Joseph Hospital, in Johannesburg, over the course of 1 year. Methods: A retrospective record review was conducted to investigate the prevalence, demographics, reasons for admission, treatment, length of stay and follow-up of a group of inpatients during 2010 with a diagnosis of BPD, based on DSM-IV-TR diagnostic criteria, allocated on discharge. Results: Considering evidence retrospectively, the quality of the BPD diagnosis allocated appeared adequate. Statistical analysis revealed findings mainly in keeping with other reports, for example, that patients with BPD are above-average users of resources who make significantly more use of emergency services and that they generally do not adhere well to their scheduled outpatient follow-up arrangements. The longer average length of inpatient stay of this group with BPD, however, exceeded the typically brief period generally recommended for acute inpatient containment and emergency intervention. Conclusion: Implementation of targeted prevention and early intervention strategies, based on systematised programmes such as dialectical behavioural therapy and mentalisation based therapy, may be useful in addressing these problems experienced with integrating the in- and outpatient management of BPD. Keywords: Borderline personality; inpatient; acute

  19. The institution of science and the science of institutions the legacy of Joseph Ben-David

    CERN Document Server

    2014-01-01

    The present anthology, edited by Marcel Herbst, is partially based on a conference, held in 2009, to reflect on the legacy of Ben-David, and contains a selection of substantially revised papers, plus four contributions specifically written for this volume. The book focuses on three major lines of Ben-David’s research, namely “Center and Periphery” (Part I), “Role and Ethos” (Part II), and “Organization and Growth” (Part III). In addition, comprehensive introductory (“Prologue”) and concluding chapters (“Epilogue”, Part IV) by Marcel Herbst are provided. The volume addresses the following disciplines: higher education, history and sociology of science, philosophy of science, history of medicine, public administration, policy studies, Jewish studies, and economics. The anthology is one of two new publications on Joseph Ben-David after the special Minerva edition Vol. 25, Numbers 1–2, March 1987, and Gad Freudenthal’s collection of Ben-David’s writings [1991]. The text can be used i...

  20. (123I)-IMP SPECT findings in Machado-Joseph disease

    International Nuclear Information System (INIS)

    Suzuki, Masahiko

    1997-01-01

    Single photon emission computed tomography (SPECT) with N-isopropyl-p-( 123 I)iodoamphetamine (IMP) was used to study the dynamics of cerebellar and brainstem metabolic function in patients with Mochado-Joseph disease (MJD), the diagnosis of which was confirmed with genetic analysis. The SPECT data obtained was analyzed semiquantitatively. In patients with MJD, ( 123 I)-IMP accumulation in the cerebellum and brainstem was decreased, and the degree of decrease reflected the clinical severity of MJD. When MJD was mild, the decrease in ( 123 I)-IMP accumulation was much greater in the brainstem than in the cerebellum. However, the decrease in ( 123 I)-IMP accumulation in the cerebellum and brainstem was not correlated with the severity of atrophy or with the number of CAG repeats. ( 123 I)-IMP SPECT was useful for evaluating the decrease in cerebellum and brainstem function in patients with MJD. Results of this study suggest that the functional decrease in MJD may begin in the brainstem. (author)

  1. Theoretical requirements to tolerances to be imposed on fuel rod design parameters for RBEC-M lead-bismuth fast reactor

    International Nuclear Information System (INIS)

    Vasiliev, A.; Alekseev, P.; Mikityuk, K.; Fomichenko, P.; Shestopalov, A.

    2002-01-01

    Development of advanced reactors with innovative materials requires comprehensive analysis of fuel rod design parameters as well as tolerances to be imposed on these parameters. Currently, it is considered traditional to estimate uncertainties in core neutronics parameters on the basis of known tolerances imposed on fuel rod design parameters. However, requirements to some core neutronics parameters of advanced reactors can be first formulated and then taken into account, while developing the technologies for innovative fuel rod manufacturing, i.e. an 'inverse' problem can be solved. The aim of this problem is to find combinations of fuel rod design tolerances which provide that selected core neutronics parameters remain within specified deviations during base irradiation. (authors)

  2. Review: Joseph Patrick Ganahl, Corruption, Good Governance, and the African State: A Critical Analysis of the Political-Economic Foundations of Corruption in Sub-Saharan Africa (2013)

    OpenAIRE

    Reinhart Kößler; Arnold-Bergstraesser-Institut

    2015-01-01

    Review of the monograph:Joseph Patrick Ganahl, Corruption, Good Governance, and the African State: A Critical Analysis of the Political-Economic Foundations of Corruption in Sub-Saharan Africa, Potsdam: Potsdam University Press, 2013, ISBN 9783869562483, 300 pp. Besprechung der Monographie:Joseph Patrick Ganahl, Corruption, Good Governance, and the African State: A Critical Analysis of the Political-Economic Foundations of Corruption in Sub-Saharan Africa, Potsdam: Potsdam University Press...

  3. Fusion-fission hybrid reactors

    International Nuclear Information System (INIS)

    Greenspan, E.

    1984-01-01

    This chapter discusses the range of characteristics attainable from hybrid reactor blankets; blanket design considerations; hybrid reactor designs; alternative fuel hybrid reactors; multi-purpose hybrid reactors; and hybrid reactors and the energy economy. Hybrid reactors are driven by a fusion neutron source and include fertile and/or fissile material. The fusion component provides a copious source of fusion neutrons which interact with a subcritical fission component located adjacent to the plasma or pellet chamber. Fissile fuel and/or energy are the main products of hybrid reactors. Topics include high F/M blankets, the fissile (and tritium) breeding ratio, effects of composition on blanket properties, geometrical considerations, power density and first wall loading, variations of blanket properties with irradiation, thermal-hydraulic and mechanical design considerations, safety considerations, tokamak hybrid reactors, tandem-mirror hybrid reactors, inertial confinement hybrid reactors, fusion neutron sources, fissile-fuel and energy production ability, simultaneous production of combustible and fissile fuels, fusion reactors for waste transmutation and fissile breeding, nuclear pumped laser hybrid reactors, Hybrid Fuel Factories (HFFs), and scenarios for hybrid contribution. The appendix offers hybrid reactor fundamentals. Numerous references are provided

  4. Mirror reactor studies

    International Nuclear Information System (INIS)

    Moir, R.W.; Barr, W.L.; Bender, D.J.

    1977-01-01

    Design studies of a fusion mirror reactor, a fusion-fission mirror reactor, and two small mirror reactors are summarized. The fusion reactor uses 150-keV neutral-beam injectors based on the acceleration of negative ions. The injectors provide over 1 GW of continuous power at an efficiency greater than 80%. The fusion reactor has three-stage, modularized, Venetian blind, plasma direct converter with a predicted efficiency of 59% and a new concept for removal of the lune-shaped blanket: a crane is brought between the two halves of the Yin-Yang magnet, which are separated by a float. The design has desirable features such as steady-state operation, minimal impurity problems, and low first-wall thermal stress. The major disadvantage is low Q resulting in high re-circulating power and hence high cost of electrical power. However, the direct capital cost per unit of gross electrical power is reasonable [$1000/kW(e)]. By contrast, the fusion-fission reactor design is not penalized by re-circulating power and uses relatively near-term fusion technology being developed for the fusion power program. New results are presented on the Th- 233 U and the U- 239 Pu fuel cycles. The purpose of this hybrid is fuel production, with projected costs at $55/g of Pu or $127/g of 233 U. Blanket and cooling system designs, including an emergency cooling system, by General Atomic Company, lead us to the opinion that the reactor can meet expected safety standards for licensing. The smallest mirror reactor having only a shield between the plasma and the coil is the 4.2-m long fusion engineering research facility (FERF) designed for material irradiation. The smallest mirror reactor having both a blanket and shield is the 7.5-m long experimental power reactor (EPR), which has both a fusion and a fusion-fission version. (author)

  5. Nuclear reactors

    International Nuclear Information System (INIS)

    Middleton, J.E.

    1977-01-01

    Reference is made to water cooled reactors and in particular to the cooling system of steam generating heavy water reactors (SGHWR). A two-coolant circuit is described for the latter. Full constructural details are given. (U.K.)

  6. Reactor decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1984-01-01

    A pioneering project on the decommissioning of the Windscale Advanced Gas-cooled Reactor, by the UKAEA, is described. Reactor data; policy; waste management; remote handling equipment; development; and recording and timescales, are all briefly discussed. (U.K.)

  7. 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

  8. Multiregion reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The study of reflected reactors can be done employing the multigroup diffusion method. The neutron conservation equations, inside the intervals, can be written by fluxes and group constants. A reflected reactor (one and two groups) for a slab geometry is studied, aplying the continuity of flux and current in the interface. At the end, the appropriated solutions for a infinite cylindrical reactor and for a spherical reactor are presented. (Author) [pt

  9. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sato, Morihiko.

    1994-01-01

    Liquid metals such as liquid metal sodium are filled in a reactor container as primary coolants. A plurality of reactor core containers are disposed in a row in the circumferential direction along with the inner circumferential wall of the reactor container. One or a plurality of intermediate coolers are disposed at the inside of an annular row of the reactor core containers. A reactor core constituted with fuel rods and control rods (module reactor core) is contained at the inside of each of the reactor core containers. Each of the intermediate coolers comprises a cylindrical intermediate cooling vessels. The intermediate cooling vessel comprises an intermediate heat exchanger for heat exchange of primary coolants and secondary coolants and recycling pumps for compulsorily recycling primary coolants at the inside thereof. Since a plurality of reactor core containers are thus assembled, a great reactor power can be attained. Further, the module reactor core contained in one reactor core vessel may be small sized, to facilitate the control for the reactor core operation. (I.N.)

  10. Chief Joseph Kokanee Enhancement Project; Strobe Light Deterrent Efficacy Test and Fish Behavior Determination at the Grand Coulee Dam Third Powerplant Forebay, 2003-2004 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Simmons, M.; McKinstry, C.; Cook, C.

    2004-01-01

    Since 1995, the Confederated Tribes of the Colville Reservation (Colville Confederated Tribes) have managed the Chief Joseph Kokanee Enhancement Project as part of the Northwest Power Planning Council (NWPPC) Fish and Wildlife Program. Project objectives have focused on understanding natural production of kokanee (a land-locked sockeye salmon) and other fish stocks in the area above Grand Coulee and Chief Joseph Dams on the Columbia River. A 42-month investigation from 1996 to 1999 determined that from 211,685 to 576,676 fish were entrained annually at Grand Coulee Dam. Analysis of the entrainment data found that 85% of the total entrainment occurred at the dam's third powerplant. These numbers represent a significant loss to the tribal fisheries upstream of the dam. In response to a suggestion by the NWPPC Independent Scientific Review Panel, the scope of work for the Chief Joseph Kokanee Enhancement Project was expanded to include a multiyear pilot test of a strobe light system to help mitigate fish entrainment. This report details the work conducted during the third year of the strobe light study by researchers of the Colville Confederated Tribes in collaboration with the Pacific Northwest National Laboratory. The objective of the study is to determine the efficacy of a prototype strobe light system to elicit a negative phototactic response in kokanee and rainbow trout under field conditions. The prototype system consists of six strobe lights affixed to an aluminum frame suspended 15 m vertically underwater from a barge secured in the center of the entrance to the third powerplant forebay. The lights, controlled by a computer, illuminate a region directly upstream of the barge. The 2003 study period extended from June 16 through August 1. Three light treatments were used: all six lights on for 24 hours, all lights off for 24 hours, and three of six lights cycled on and off every hour for 24 hours. These three treatment conditions were assigned randomly

  11. Studies of the effect of irradiation in a nuclear reactor, of targets containing Mo used for the preparation of 99Mo gel, material that constitutes the 99Mo - 99mTc generators

    International Nuclear Information System (INIS)

    Nieto, Renata Correa

    2004-01-01

    The most used radioisotope in Nuclear Medicine is 99m Tc, obtained in the 99 Mo - 99m Tc generator form. 99 Mo can be produced by several nuclear reactions in Cyclotron and Reactor. The production in Cyclotron is not technically and commercially feasible. The production in Nuclear Reactor can be made in two ways: 235 U fission and 99 Mo (n,γ) 99 Mo reaction. A project aiming the production of 99 Mo by activation of Mo is under way at IPEN, producing a gel type MoZr generator. There are two ways of preparing the gel and the generators: by irradiating MoO 3 and preparing the gel or by the preparation of the gel and further irradiation. This work consists in the study of the irradiation effects in several targets containing Mo for the production of 99 Mo by the 98 Mo (n,γ) 99 Mo reaction and further preparation of the gel for use as a gel type 99 Mo - 99m Tc generator. Three rinds of gel were studied: zirconium, titanium and cerium molybdate, and their morphology, infrared structure and elution yield of 99m Tc were analysed. The best results were achieved with the generators prepared with MoZr post formed gel, with amorphous structure and better elution yields. The pre formed gel induced crystallinity and worst performance of the generators. (author)

  12. Fast breeder reactor

    International Nuclear Information System (INIS)

    Ito, Shin-ichi; Maki, Koichi.

    1975-01-01

    Object: To conserve loaded fuel, aquire controllable surplus reaction degree, increase the breeding index, flatten output and improve sealing of neutrons by inserting a decelerating substance in a blanket section. Structure: A decelerating substance such as beryllium or beryllium oxide is inserted in a blanket section between an outer reactor core and reflector. With this arrangement, neutrons are decelerated to increase the low energy components, which are partly subjected to reflection by the outer reactor core to thereby reduce leakage of neutrons from the reactor core. (Kamimura, M.)

  13. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

    After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

  14. 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)

  15. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

    Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

  16. Resident Fish Stock Status above Chief Joseph and Grand Coulee Dams; 2001 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Connor, Jason M. (Kalispell Department of Natural Resources, Usk, WA); McLellan, Jason G. (Washington Department of Fish and Wildlife, Spokane, WA); O' Connor, Dick (Washington Department of Fish and Wildlife, Olympia, WA)

    2003-01-01

    In 1980, the United States Congress enacted the Northwest Power Planning and Conservation Act (PL 96-501, 1980), which established the Northwest Power Planning Council (NPPC). The NPPC was directed by Congress to develop a regional Power Plan and also the Columbia River Basin Fish and Wildlife Program (FWP) to restore or replace losses of fish caused by construction and operation of hydroelectric dams in the Columbia River Basin. In developing the FWP, Congress specifically directed NPPC to solicit recommendations for measures to be included in the Program from the region's fish and wildlife agencies and Indian tribes. All measures adopted by the Council were also required to be consistent with the management objectives of the agencies and tribes [Section 4.(h)(6)(A)], the legal rights of Indian tribes in the region [Section 4.(h)(6)(D)] and be based upon and supported by the best available scientific knowledge [Section 4.(h)(6)(B)]. The Resident Fish Stock Status above Chief Joseph and Grand Coulee Dams Project, also known as the Joint Stock Assessment Project (JSAP) specifically addresses NPPC Council measure 10.8B.26 of the 1994 program. The Joint Stock Assessment Project is a management tool using ecosystem principles to manage artificial fish assemblages and native fish in altered environments existing in the Columbia River System above Chief Joseph and Grand Coulee Dams (Blocked Area). A three-phase approach of this project will enhance the fisheries resources of the Blocked Area by identifying data gaps, filling data gaps with research, and implementing management recommendations based on research results. The Blocked Area fisheries information is housed in a central location, allowing managers to view the entire system while making decisions, rather than basing management decisions on isolated portions of the system. The JSAP is designed and guided jointly by fisheries managers in the Blocked Area and the Columbia Basin Blocked Area Management Plan

  17. Resident Fish Stock above Chief Joseph and Grand Coulee Dams; 2002 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Connor, Jason M. (Kalispel Department of Natural Resources, Usk, WA); McLellan, Jason G. (Washington Department of Fish and Wildlife, Spokane, WA); Butler, Chris (Spokane Tribe of Indians, Department of Natural Resources, Wellpinit, WA)

    2003-09-01

    In 1980, the United States Congress enacted the Northwest Power Planning and Conservation Act (PL 96-501, 1980), which established the Northwest Power and Conservation Council (NPCC), formerly the Northwest Power Planning Council. The NPCC was directed by Congress to develop a regional Power Plan and also the Columbia River Basin Fish and Wildlife Program (FWP) to restore or replace losses of fish caused by construction and operation of hydroelectric dams in the Columbia River Basin. In developing the FWP, Congress specifically directed NPCC to solicit recommendations for measures to be included in the Program from the region's fish and wildlife agencies and Indian tribes. All measures adopted by the Council were also required to be consistent with the management objectives of the agencies and tribes [Section 4.(h)(6)(A)], the legal rights of Indian tribes in the region [Section 4.(h)(6)(D)] and be based upon and supported by the best available scientific knowledge [Section 4.(h)(6)(B)]. The Resident Fish Stock Status above Chief Joseph and Grand Coulee Dams Project, also known as the Joint Stock Assessment Project (JSAP) specifically addresses NPPC Council measure 10.8B.26 of the 1994 program. The Joint Stock Assessment Project is a management tool using ecosystem principles to manage artificial fish assemblages and native fish in altered environments existing in the Columbia River System above Chief Joseph and Grand Coulee Dams (Blocked Area). A three-phase approach of this project will enhance the fisheries resources of the Blocked Area by identifying data gaps, filling data gaps with research, and implementing management recommendations based on research results. The Blocked Area fisheries information is housed in a central location, allowing managers to view the entire system while making decisions, rather than basing management decisions on isolated portions of the system. The JSAP is designed and guided jointly by fisheries managers in the Blocked Area

  18. Resident Fish Stock above Chief Joseph and Grand Coulee Dams; 2003-2004 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Connor, Jason M. (Kalispel Tribe of Indians, Usk, WA); McLellan, Jason G. (Washington Department of Fish and Wildlife, Olympia, WA); Butler, Chris (Spokane Tribe of Indians, Wellpinit, WA)

    2005-11-01

    In 1980, the United States Congress enacted the Northwest Power Planning and Conservation Act (PL 96-501, 1980), which established the Northwest Power and Conservation Council (NPCC), formerly the Northwest Power Planning Council. The NPCC was directed by Congress to develop a regional Power Plan and also the Columbia River Basin Fish and Wildlife Program (FWP) to restore or replace losses of fish caused by construction and operation of hydroelectric dams in the Columbia River Basin. In developing the FWP, Congress specifically directed NPCC to solicit recommendations for measures to be included in the Program from the region's fish and wildlife agencies and Indian tribes. All measures adopted by the Council were also required to be consistent with the management objectives of the agencies and tribes [Section 4.(h)(6)(A)], the legal rights of Indian tribes in the region [Section 4.(h)(6)(D)] and be based upon and supported by the best available scientific knowledge [Section 4.(h)(6)(B)]. The Resident Fish Stock Status above Chief Joseph and Grand Coulee Dams Project, also known as the Joint Stock Assessment Project (JSAP) specifically addresses NPPC Council measure 10.8B.26 of the 1994 program. The Joint Stock Assessment Project is a management tool using ecosystem principles to manage artificial and native fish assemblages in altered environments existing in the Columbia River System above Chief Joseph and Grand Coulee Dams (Blocked Area). A three-phase approach of this project will enhance the fisheries resources of the Blocked Area by identifying data gaps, filling data gaps with research, and implementing management recommendations based on research results. The Blocked Area fisheries information is housed in a central location, allowing managers to view the entire system while making decisions, rather than basing management decisions on isolated portions of the system. The JSAP is designed and guided jointly by fisheries managers in the Blocked Area. The

  19. Resident Fish Stock Status above Chief Joseph and Grand Coulee Dams; 2002-2003 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Connor, Jason M. (Kalispel Tribe of Indians, Usk, WA); McLellan, Jason G. (Washington Department of Fish and Wildlife); Butler, Chris (Spokane Tribe of Indians, Wellpinit, WA)

    2006-02-01

    In 1980, the United States Congress enacted the Northwest Power Planning and Conservation Act (PL 96-501, 1980), which established the Northwest Power and Conservation Council (NPCC), formerly the Northwest Power Planning Council. The NPCC was directed by Congress to develop a regional Power Plan and also the Columbia River Basin Fish and Wildlife Program (FWP) to restore or replace losses of fish caused by construction and operation of hydroelectric dams in the Columbia River Basin. In developing the FWP, Congress specifically directed NPCC to solicit recommendations for measures to be included in the Program from the region's fish and wildlife agencies and Indian tribes. All measures adopted by the Council were also required to be consistent with the management objectives of the agencies and tribes [Section 4.(h)(6)(A)], the legal rights of Indian tribes in the region [Section 4.(h)(6)(D)] and be based upon and supported by the best available scientific knowledge [Section 4.(h)(6)(B)]. The Resident Fish Stock Status above Chief Joseph and Grand Coulee Dams Project, also known as the Joint Stock Assessment Project (JSAP) specifically addresses NPPC Council measure 10.8B.26 of the 1994 program. The Joint Stock Assessment Project is a management tool using ecosystem principles to manage artificial and native fish assemblages in altered environments existing in the Columbia River System above Chief Joseph and Grand Coulee Dams (Blocked Area). A three-phase approach of this project will enhance the fisheries resources of the Blocked Area by identifying data gaps, filling data gaps with research, and implementing management recommendations based on research results. The Blocked Area fisheries information is housed in a central location, allowing managers to view the entire system while making decisions, rather than basing management decisions on isolated portions of the system. The JSAP is designed and guided jointly by fisheries managers in the Blocked Area. The

  20. La robe et les mortiers. Joseph-Marie de Villespassans, magistrat faux-monnayeur (1713

    Directory of Open Access Journals (Sweden)

    Mathieu Soula

    2011-12-01

    Full Text Available Au début du XVIIIe siècle, un magistrat toulousain, le conseiller de Villepassans, est soupçonné d’être à la tête d’un réseau de faux-monnayeurs. L’affaire est sensible pour le parlement, qui instruit directement l’affaire, car il s’agit de poursuivre l’un de ses membres. Un magistrat faux-monnayeur est en effet une « figure » criminelle qui trouble et pose question. Par contagion, la mauvaise renommée de Villepassans peut atteindre les autres conseillers et porter le discrédit sur une institution qui se définit comme « le vrai vengeur des crimes ». Dans ces conditions, comment le parlement traite-t-il l’affaire, et quelle figure criminelle appose-t-il à Villespassans ? L’étude de ce cas atypique peut ainsi aider à mieux comprendre l’enjeu de la construction d’une identité criminelle.In early 18th century, a magistrate of the parliament of Toulouse, Joseph-Marie de Villespassans, is suspected of being the leader of forgers of money. This case is highly dangerous for the parliament, who’s in charge. The culpability of the magistrate-forger can also touch the others magistrates, and the prestige of the institution to. So, in these conditions, how can the parliament manage this case? I this research, we’re trying to study this atypical case in the way the parliament built the culpability.

  1. Joseph Black, carbon dioxide, latent heat, and the beginnings of the discovery of the respiratory gases.

    Science.gov (United States)

    West, John B

    2014-06-15

    The discovery of carbon dioxide by Joseph Black (1728-1799) marked a new era of research on the respiratory gases. His initial interest was in alkalis such as limewater that were thought to be useful in the treatment of renal stone. When he studied magnesium carbonate, he found that when this was heated or exposed to acid, a gas was evolved that he called "fixed air" because it had been combined with a solid material. He showed that the new gas extinguished a flame, that it could not support life, and that it was present in gas exhaled from the lung. Within a few years of his discovery, hydrogen, nitrogen, and oxygen were also isolated. Thus arguably Black's work started the avalanche of research on the respiratory gases carried out by Priestley, Scheele, Lavoisier, and Cavendish. Black then turned his attention to heat and he was the first person to describe latent heat, that is the heat added or lost when a liquid changes its state, for example when water changes to ice or steam. Latent heat is a key concept in thermal physiology because of the heat lost when sweat evaporates. Black was a friend of the young James Watt (1736-1819) who was responsible for the development of early steam engines. Watt was puzzled why so much cooling was necessary to condense steam into water, and Black realized that the answer was the latent heat. The resulting improvements in steam engines ushered in the Industrial Revolution. Copyright © 2014 the American Physiological Society.

  2. Identità, attraversamenti e ibridismi nell'opera di Joseph O'Connor

    Directory of Open Access Journals (Sweden)

    Manfredi Bernardini

    2011-05-01

    Full Text Available This paper looks into the works of Irish writer Joseph O’Connor and his perspective in the process of redefining the spacial, temporal and cultural links between Ireland and the Unites States. In fact, a number of interesting points can be found throughout O’Connor works: the imagology (the image of the Irishman in the American culture; the investigation on prejudices and stereotypes (True Believers, 1991; border studies, although considered in a broader sense, one where the physical and geographical borders (the Atlantic Ocean appear to be symbolic and imaginary. Referring to the concept of Black Atlantic, as it was first proposed by Paul Gilroy, we can similarly imagine - acording to scholars such as David Lloyd and Peter O’Neill - a Green Atlantic, where the Ocean, after ceasing to represent a frontier, a border meant to separate, acquires a new meaning and becomes a place for bidirectional crossing: on the one hand as a means to cross over borders and synthesis between two cultures; in the other as a movement towards and beyond the limits of a Third Space, “a space of enunciation” and cultural negotiation, as Homi Bhabha would say. Other fundamental and recurring themes in the novels of O’Connor are identity and memory (Sweet Liberty Travels in Irish America, 1996, the “look” of the Others (Inishowen, 2000 and towards the Other (Redemption Falls, 2007 and, more importantly, the Irish diaspora towards the United States, spanning from the final years of the 19th century until the first half of the 20th, when, in some respect, the United States were looked upon as a “promised land” (this is mostly evident in the novel Star of the sea, 2002.

  3. Parkinsonian phenotype in Machado-Joseph disease (MJD/SCA3: a two-case report

    Directory of Open Access Journals (Sweden)

    Vasconcelos João

    2011-10-01

    Full Text Available Abstract Background Machado-Joseph disease (MJD, or spinocerebellar ataxia type 3 (SCA3, is an autosomal dominant neurodegenerative disorder of late onset, which is caused by a CAG repeat expansion in the coding region of the ATXN3 gene. This disease presents clinical heterogeneity, which cannot be completely explained by the size of the repeat tract. MJD presents extrapyramidal motor signs, namely Parkinsonism, more frequently than the other subtypes of autosomal dominant cerebellar ataxias. Although Parkinsonism seems to segregate within MJD families, only a few MJD patients develop parkinsonian features and, therefore, the clinical and genetic aspects of these rare presentations remain poorly investigated. The main goal of this work was to describe two MJD patients displaying the parkinsonian triad (tremor, bradykinesia and rigidity, namely on what concerns genetic variation in Parkinson's disease (PD associated loci (PARK2, LRRK2, PINK1, DJ-1, SNCA, MAPT, APOE, and mtDNA tRNAGln T4336C. Case presentation Patient 1 is a 40 year-old female (onset at 30 years of age, initially with a pure parkinsonian phenotype (similar to the phenotype previously reported for her mother. Patient 2 is a 38 year-old male (onset at 33 years of age, presenting an ataxic phenotype with parkinsonian features (not seen either in other affected siblings or in his father. Both patients presented an expanded ATXN3 allele with 72 CAG repeats. No PD mutations were found in the analyzed loci. However, allelic variants previously associated with PD were observed in DJ-1 and APOE genes, for both patients. Conclusions The present report adds clinical and genetic information on this particular and rare MJD presentation, and raises the hypothesis that DJ-1 and APOE polymorphisms may confer susceptibility to the parkinsonian phenotype in MJD.

  4. Post-Colonial Analysis of Joseph Conrad’s Heart of Darkness

    Directory of Open Access Journals (Sweden)

    Samet Güven

    2013-07-01

    Full Text Available Joseph Conrad’s Heart of Darkness tells the journey of Marlow through the African jungle and his search for the European Kurtz who exploits the natives by imposing violence. It is mainly based upon Conrad’s own experience in Congo. Conrad learned how Europeans exploited and traded the natives for their own benefits during his own journey. The book is regarded as an attack on imperialism and criticizes immoral treatments of the European colonizers in Africa in the 19th century. Keith Booker states that “the book deals with issues such as imperialism, capitalism, race, and gender that were very much at the forefront of the turn-of-the century European mind. Conrad’s ambivalent treatment of these issues is extremely representative of the way they were treated in any number of European discourses of the time” (217. Besides, Chinua Achebe in his An “Image of Africa: Racism in Conrad’s Heart of Darkness” comments that “Heart of Darkness projects the image of Africa as ‘the other world’, the antithesis of Europe and therefore of civilization, a place where man’s vaunted intelligence and refinement are finally mocked by triumphant bestiality” (338. Although Achebe puts forward that the novel is in favor of colonialism, I consider that Conrad does not intend to write it to appreciate colonialism and therefore the purpose of this study is to approach Conrad’s Heart of Darkness from post-colonial perspective by taking European imperialism and colonialism over Africa into consideration in order to clarify how Conrad has deconstructed binary oppositions of colonialism by subverting the general idea of the Europeans towards Africa in the 19th century.

  5. Post-Colonial Analysis of Joseph Conrad’s Heart of Darkness

    Directory of Open Access Journals (Sweden)

    Samet Güven

    2013-06-01

    Full Text Available Joseph Conrad’s Heart of Darkness tells the journey of Marlow through the African jungle and his search for the European Kurtz who exploits the natives by imposing violence. It is mainly based upon Conrad’s own experience in Congo. Conrad learned how Europeans exploited and traded the natives for their own benefits during his own journey. The book is regarded as an attack on imperialism and criticizes immoral treatments of the European colonizers in Africa in the 19th century. Keith Booker states that “the book deals with issues such as imperialism, capitalism, race, and gender that were very much at the forefront of the turn-of-the century European mind. Conrad’s ambivalent treatment of these issues is extremely representative of the way they were treated in any number of European discourses of the time” (217. Besides, Chinua Achebe in his An “Image of Africa: Racism in Conrad’s Heart of Darkness” comments that “Heart of Darkness projects the image of Africa as ‘the other world’, the antithesis of Europe and therefore of civilization, a place where man’s vaunted intelligence and refinement are finally mocked by triumphant bestiality” (338. Although Achebe puts forward that the novel is in favor of colonialism, I consider that Conrad does not intend to write it to appreciate colonialism and therefore the purpose of this study is to approach Conrad’s Heart of Darkness from post-colonial perspective by taking European imperialism and colonialism over Africa into consideration in order to clarify how Conrad has deconstructed binary oppositions of colonialism by subverting the general idea of the Europeans towards Africa in the 19th century.

  6. Chief Joseph Kokanee Enhancement Project : Strobe Light Deterrent Efficacy Test and Fish Behavior Determination at Grond Coulee Dam Third Powerplant Forebay.

    Energy Technology Data Exchange (ETDEWEB)

    Simmons, M.A.; McKinstry, C.A.; Simmons, C.S.

    2002-01-01

    Since 1995, the Colville Confederated Tribes have managed the Chief Joseph Kokanee Enhancement Project as part of the Northwest Power Planning Council's (NWPPC) Fish and Wildlife Program. Project objectives have focused on understanding natural production of kokanee (a land-locked sockeye salmon) and other fish stocks in the area above Grand Coulee and Chief Joseph Dams on the Columbia River. A 42-month investigation concluded that entrainment at Grand Coulee Dam ranged from 211,685 to 576,676 fish annually. Further analysis revealed that 85% of the total entrainment occurred at the dam's third powerplant. These numbers represent a significant loss to the tribal fisheries upstream of the dam. In response to a suggestion by the NWPPC's Independent Scientific Review Panel, the scope of work for the Chief Joseph Kokanee Enhancement Project was expanded to include a multiyear pilot test of a strobe light system to help mitigate fish entrainment. This report details the work conducted during the first year of the study by researchers of the Colville Confederated Tribes in collaboration with the Pacific Northwest National Laboratory (PNNL). The objective of the study was to determine the efficacy of a prototype strobe light system to elicit a negative phototactic response in kokanee and rainbow trout. Analysis of the effect of strobe lights on the distribution (numbers) and behavior of kokanee and rainbow trout was based on 51, 683 fish targets detected during the study period (June 30 through August 1, 2001). Study findings include the following: (1) Analysis of the count data indicated that significantly more fish were present when the lights were on compared to off. This was true for both the 24-hr tests as well as the 1-hr tests. Powerplant discharge, distance from lights, and date were significant factors in the analysis. (2) Behavioral results indicated that fish within 14 m of the lights were trying to avoid the lights by swimming across the lighted

  7. First results of U3Si2 production and its relevance in the power scale-up of IPEN research reactor IEA-R1m

    International Nuclear Information System (INIS)

    Saliba-Silva, A.M.; Souza, J.A.B.; Frajndlich, E.U.C.; Durazzo, M.; Perrotta, J.A.

    1997-01-01

    The own supply of LEU U 3 Si 2 is crucial for IPEN, since the whole scale-up of IPEN MTR IEA-Rlm reactor will rely on it. The Brazilian request for radioisotopes production is fully linked with the already made power scale-up from 2 to 5 MW for this reactor. IPEN now depends on fuel element material upgrading from U 3 O 8 towards LEU U 3 Si 2 . The fuel plate productive technology from the powdered material is already well established, only needing simple making of minor adjustments, but to reach the stage of producing U 3 Si 2 we need a fully settled chemical pilot plant in order to reach a LEU UF 4 productive routine. Complementing this process, it was also needed to scale down the previous practice of uranium magnesiothermic reduction to around a sub-critical safe uranium mass of approximately 3000g. To complete the metallurgical processing, it is being developed the production of U 3 Si 2 in a vacuum induction furnace. Some experiments to get this intermetallic, using natural uranium, have already been carried out in order to build up a general idea of the future process of LEU U 3 Si 2 . These experiments are described in this paper and also some of the initial characterization results, such as the qualification pattern of the ingot. It is also discussed some new features of inhomogeneity of solidified phases that may be deleterious to future production routine. (author)

  8. L’intérêt historiographique des manuscrits de travail de linguistes : l’exemple de la linguistique générale de Joseph Vendryes

    Directory of Open Access Journals (Sweden)

    Testenoire Pierre-Yves

    2016-01-01

    Full Text Available Dans quelle mesure les manuscrits de travail des linguistes présentent-ils un intérêt pour les historiens de la linguistique ? Ce type de documents suscite, depuis quelques années, un regain indéniable de curiosité. L’exploration d’un nombre croissant de fonds d’archives de savants permet, au-delà d’un élargissement de l’horizon documentaire, d’envisager des approches comparatives entre différentes pratiques savantes. Elle ouvre aussi de nouvelles interrogations. Cet article réfléchit à l’intérêt historiographique de ce type de documents à partir d’un cas inédit : les papiers de travail consacrés à la linguistique générale du linguiste français, Joseph Vendryes (1875-1960. On met en évidence le double intérêt des archives privées de savants : documentaire et processuel. On aborde, dans un premier temps, les manuscrits d’un point de vue documentaire de façon à dégager ce que leur prise en compte modifie de notre connaissance de la linguistique générale de Joseph Vendryes. Le deuxième temps, consacré à la perspective processuelle, fait des manuscrits le lieu de l’observation de la méthode. Il s’agit d’analyser, à partir des manuscrits préparatoires à l’écriture d’un article, comment s’élabore un discours scientifique à caractère général sur le langage et les langues. Ces archives privées sont au carrefour de questionnements de recherche qui relèvent aussi bien d’une histoire conceptuelle que d’une histoire sociale des sciences du langage.

  9. Small propulsion reactor design based on particle bed reactor concept

    International Nuclear Information System (INIS)

    Ludewig, H.; Lazareth, O.; Mughabghab, S.; Perkins, K.; Powell, J.R.

    1989-01-01

    In this paper Particle Bed Reactor (PBR) designs are discussed which use 233 U and /sup 242m/Am as fissile materials. A constant total power of 100MW is assumed for all reactors in this study. Three broad aspects of these reactors is discussed. First, possible reactor designs are developed, second physics calculations are outlined and discussed and third mass estimates of the various candidates reactors are made. It is concluded that reactors with a specific mass of 1 kg/MW can be envisioned of 233 U is used and approximately a quarter of this value can be achieved if /sup 242m/Am is used. If this power level is increased by increasing the power density lower specific mass values are achievable. The limit will be determined by uncertainties in the thermal-hydraulic analysis. 5 refs., 5 figs., 6 tabs

  10. Test reactors in the world

    International Nuclear Information System (INIS)

    Corella, M.R.; Gomez Alonso, M.

    1983-01-01

    INFCE work on research reactor core conversion from HEU to LEU, attracted a raising interest on this type of nuclear reactors. In this context, the present work shows a compilation of worldwide research and test nuclear reactors, now in operation, under construction, or planned, as well as decommissioned reactors (tables A to F). Brief descriptions of these reactors are included in tables G to L. In table M a summary view of reactors with power level between 10 and 30 MWt is shown. Attention is focused on that power range, as it has been considered in very preliminar studies for a new research reactor. Almost all data have been obtained from current available bibliography. (author)

  11. Reactor safety device

    International Nuclear Information System (INIS)

    Okada, Yasumasa.

    1987-01-01

    Purpose: To scram control rods by processing signals from a plurality of temperature detectors and generating abnormal temperature warning upon occurrence of abnormal temperature in a nuclear reactor. Constitution: A temperature sensor comprising a plurality of reactors each having a magnetic body as the magnetic core having a curie point different from each other and corresponding to the abnormal temperature against which reactor core fuels have to be protected is disposed in an identical instrumentation well near the reactor core fuel outlet/inlet of a reactor. A temperature detection device actuated upon detection of an abnormal temperature by the abrupt reduction of the reactance of each of the reactors is disposed. An OR circuit and an AND circuit for conducting OR and AND operations for each of the abnormal temperature detection signals from the temperature detection device are disposed. The output from the OR circuit is used as the abnormal temperature warning signal, while the output from the AND circuit is utilized as a signal for actuating the scram operation of control rod drive mechanisms. Accordingly, it is possible to improve the reliability of the reactor scram system, particularly, improve the reliability under a high temperature atmosphere. (Kamimura, M.)

  12. Health requirements for nuclear reactor operators

    International Nuclear Information System (INIS)

    1980-05-01

    The health prerequisites established for the qualification of nuclear reactor operators according to CNEN-NE-1.01 Guidelines Licensing of nuclear reactor operators, CNEN-12/79 Resolution, are described. (M.A.) [pt

  13. Reactor container

    International Nuclear Information System (INIS)

    Naruse, Yoshihiro.

    1990-01-01

    The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    Garabedian, G.

    1988-01-01

    A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

  15. Compact stellarators as reactors

    International Nuclear Information System (INIS)

    Lyon, J.F.; Valanju, P.; Zarnstorff, M.C.; Hirshman, S.; Spong, D.A.; Strickler, D.; Williamson, D.E.; Ware, A.

    2001-01-01

    Two types of compact stellarators are examined as reactors: two- and three-field-period (M=2 and 3) quasi-axisymmetric devices with volume-average =4-5% and M=2 and 3 quasi-poloidal devices with =10-15%. These low-aspect-ratio stellarator-tokamak hybrids differ from conventional stellarators in their use of the plasma-generated bootstrap current to supplement the poloidal field from external coils. Using the ARIES-AT model with B max =12T on the coils gives Compact Stellarator reactors with R=7.3-8.2m, a factor of 2-3 smaller R than other stellarator reactors for the same assumptions, and neutron wall loadings up to 3.7MWm -2 . (author)

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Batheja, P.; Huber, R.; Rau, P.

    1985-01-01

    Particularly for nuclear reactors of small output, the reactor pressure vessel contains at least two heat exchangers, which have coolant flowing through them in a circuit through the reactor core. The circuit of at least one heat exchanger is controlled by a slide valve, so that even for low drive forces, particularly in natural circulation, the required even loading of the heat exchanger is possible. (orig./HP) [de

  17. Reactor power control device

    International Nuclear Information System (INIS)

    Doi, Kazuyori.

    1981-01-01

    Purpose: To automatically control the BWR type reactor power by simple and short-time searching the load pattern nearest to the required pattern at a nuclear power plant side. Constitution: The reactor power is automatically regulated by periodical modifying of coefficients fitting to a reactor core model, according as a required load pattern. When a load requirement pattern is given, a simulator estimates the total power change and the axial power distribution change from a xenon density change output calculated by a xenon dynamic characteristic estimating device, and a load pattern capable of being realized is searched. The amount to be recirculated is controlled on the basis of the load patteren thus searched, and the operation of the BWR type reactor is automatically controlled at the side of the nuclear power plant. (Kamimura, M.)

  18. Heterogeneous reactors

    International Nuclear Information System (INIS)

    Moura Neto, C. de; Nair, R.P.K.

    1979-08-01

    The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author) [pt

  19. Evaluation of in-situ methanotrophic bioremediation for contaminated groundwater, St. Joseph, Michigan. Final report, January 1989-December 1989

    International Nuclear Information System (INIS)

    McCarty, P.L.; Semprini, L.; Dolan, M.E.; Harmon, T.C.; Just, S.

    1990-09-01

    A feasibility study of utilizing indigenous bacteria that use methane as a source of cell carbon and energy (methanotrophs) for in-situ bioremediation of groundwater contaminants at the St. Joseph site is summarized. The contaminants, compounds, can be biotransformed by methanotrophic bacteria, which are found in some locations of the site in adequate populations. The process involves stimulating the growth of native populations of methanotrophs by injecting water containing dissolved methane and oxygen into the aquifer. The stimulated population of methanotrophs in turn has the capability to degrade trichloroethylene, 1,2-cis-dichloroethylene, 1,2-trans-dichloroethylene, and vinyl chloride

  20. The fantastic in Thomas Mann's Der Tod in Venedig and Joseph und seine Brüder

    OpenAIRE

    Nolan, Tom

    2011-01-01

    The thesis includes an introductory survey of recent relevant secondary literature and a coda dealing with the fantastic as a manifestation of Schiller’s ‘Spieltrieb’. Its main body, however, is comprised of three substantial chapters prosecuting two interlinked arguments: (1) that Der Tod in Venedig and Joseph und seine Brüder are fantastic narratives and (2) that the fantastic in these narratives works hand in glove with Mann’s philosophical concerns. In order to demonstrate that the fir...

  1. "Four Ways of Writing the City" : St. Petersburg-Leningrad as a Metaphor in the Poetry of Joseph Brodsky

    OpenAIRE

    Könönen, Maija

    2003-01-01

    The present study discusses the theme of St. Petersburg-Leningrad in Joseph Brodsky's verse works. The chosen approach to the evolving im-age of the city in Brodsky's poetry is through four metaphors: St. Petersburg as "the common place" of the Petersburg Text, St. Petersburg as "Paradise and/or Hell", St. Petersburg as "a Utopian City" and St. Petersburg as "a Void". This examination of the city-image focusses on the aspects of space and time as basic categories underlying the poet's po...

  2. Regional cerebral blood flow measured with N-isopropyl-p-[123I]iodoamphetamine single-photon emission tomography in patients with Joseph disease

    International Nuclear Information System (INIS)

    Takahashi, Naoya; Odano, Ikuo; Nishihara, Mamiko; Yuasa, Tatsuhiko; Sakai, Kunio

    1994-01-01

    Regional cerebral blood flow (rCBF) was measured in five Japanese patients who were clinically diagnosed as having Joseph disease, also called Machado-Joseph disease or Azorean disease, using N-isopropyl-p-[ 123 I]iodoamphetamine (IMP) and single-photon emission tomography (SPET). Cerebellar atrophy was evaluated by a five-step rating scale as defined on X-ray computed tomography (X-CT). Compared with ten age-matched normal controls (mean cerebellar CBF ± SD: 66.9 ± 6.6 ml/100 g/min), rCBF in patients with Joseph disease was significantly decreased in the cerebellum (mean ± SD: 50.2 ± 7.3 ml/100 g/min). No significant relationship, however, was found between the decrease in rCBF in the cerebellum and the degree of cerebellar atrophy on X-CT. rCBF in the cerebellum was minimally decreased in one patient who had severe cerebellar atrophy and in two patients with moderate atrophy. These data may support the findings that Purkinje cells in the cerebellum are almost normal in Joseph disease, and that the granular and molecular layers remain intact in spite of cortical atrophy of the cerebellum. It is concluded that [ 123 I]-IMP SPET is able to identify pathological and metabolic changes in the cerebellum that do not appear on X-CT or magnetic resonance imaging, and thus is useful for the diagnosis of Joseph disease. (orig.)

  3. Summary Describing Integration of ERM Methodology into Supervisory Control Framework with Software Package Documentation; Advanced Reactor Technology Milestone: M4AT-16PN2301052

    Energy Technology Data Exchange (ETDEWEB)

    Ramuhalli, Pradeep [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hirt, Evelyn H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Dib, Gerges [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Veeramany, Arun [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bonebrake, Christopher A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Roy, Surajit [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-20

    This project involved the development of enhanced risk monitors (ERMs) for active components in Advanced Reactor (AdvRx) designs by integrating real-time information about equipment condition with risk monitors. Health monitoring techniques in combination with predictive estimates of component failure based on condition and risk monitors can serve to indicate the risk posed by continued operation in the presence of detected degradation. This combination of predictive health monitoring based on equipment condition assessment and risk monitors can also enable optimization of maintenance scheduling with respect to the economics of plant operation. This report summarizes PNNL’s multi-year project on the development and evaluation of an ERM concept for active components while highlighting FY2016 accomplishments. Specifically, this report provides a status summary of the integration and demonstration of the prototypic ERM framework with the plant supervisory control algorithms being developed at Oak Ridge National Laboratory (ORNL), and describes additional case studies conducted to assess sensitivity of the technology to different quantities. Supporting documentation on the software package to be provided to ONRL is incorporated in this report.

  4. Slurry reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kuerten, H; Zehner, P [BASF A.G., Ludwigshafen am Rhein (Germany, F.R.)

    1979-08-01

    Slurry reactors are designed on the basis of empirical data and model investigations. It is as yet not possible to calculate the flow behavior of such reactors. The swarm of gas bubbles and cluster formations of solid particles and their interaction in industrial reactors are not known. These effects control to a large extent the gas hold-up, the gas-liquid interface and, similarly as in bubble columns, the back-mixing of liquids and solids. These hydrodynamic problems are illustrated in slurry reactors which constructionally may be bubble columns, stirred tanks or jet loop reactors. The expected effects are predicted by means of tests with model systems modified to represent the conditions in industrial hydrogenation reactors. In his book 'Mass Transfer in Heterogeneous Catalysis' (1970) Satterfield complained of the lack of knowledge about the design of slurry reactors and hence of the impossible task of the engineer who has to design a plant according to accepted rules. There have been no fundamental changes since then. This paper presents the problems facing the engineer in designing slurry reactors, and shows new development trends.

  5. Reactor safety

    International Nuclear Information System (INIS)

    Butz, H.P.; Heuser, F.W.; May, H.

    1985-01-01

    The paper comprises an introduction into nuclear physics bases, the safety concept generally speaking, safety devices of pwr type reactors, accident analysis, external influences, probabilistic safety assessment and risk studies. It further describes operational experience, licensing procedures under the Atomic Energy Law, research in reactor safety and the nuclear fuel cycle. (DG) [de

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Mysels, K.J.; Shenoy, A.S.

    1976-01-01

    A nuclear reactor is described in which the core consists of a number of fuel regions through each of which regulated coolant flows. The coolant from neighbouring fuel regions is combined in a manner which results in an averaging of the coolant temperature at the outlet of the core. By this method the presence of hot streaks in the reactor is reduced. (UK)

  7. Reactor container

    International Nuclear Information System (INIS)

    Kato, Masami; Nishio, Masahide.

    1987-01-01

    Purpose: To prevent the rupture of the dry well even when the melted reactor core drops into a reactor pedestal cavity. Constitution: In a reactor container in which a dry well disposed above the reactor pedestal cavity for containing the reactor pressure vessel and a torus type suppression chamber for containing pressure suppression water are connected with each other, the pedestal cavity and the suppression chamber are disposed such that the flow level of the pedestal cavity is lower than the level of the pressure suppression water. Further, a pressure suppression water introduction pipeway for introducing the pressure suppression water into the reactor pedestal cavity is disposed by way of an ON-OFF valve. In case if the melted reactor core should fall into the pedestal cavity, the ON-OFF valve for the pressure suppression water introduction pipeway is opened to introduce the pressure suppression water in the suppression chamber into the pedestal cavity to cool the melted reactor core. (Ikeda, J.)

  8. RA Reactor

    International Nuclear Information System (INIS)

    1989-01-01

    This chapter includes the following: General description of the RA reactor, organization of work, responsibilities of leadership and operators team, regulations concerning operation and behaviour in the reactor building, regulations for performing experiments, regulations and instructions for inserting samples into experimental channels [sr

  9. Reactor physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    1998-01-01

    Progress in research on reactor physics in 1997 at the Belgian Nuclear Research Centre SCK/CEN is described. Activities in the following four domains are discussed: core physics, ex-core neutron transport, experiments in Materials Testing Reactors, international benchmarks

  10. Reactor core

    International Nuclear Information System (INIS)

    Azekura, Kazuo; Kurihara, Kunitoshi.

    1992-01-01

    In a BWR type reactor, a great number of pipes (spectral shift pipes) are disposed in the reactor core. Moderators having a small moderating cross section (heavy water) are circulated in the spectral shift pipes to suppress the excess reactivity while increasing the conversion ratio at an initial stage of the operation cycle. After the intermediate stage of the operation cycle in which the reactor core reactivity is lowered, reactivity is increased by circulating moderators having a great moderating cross section (light water) to extend the taken up burnup degree. Further, neutron absorbers such as boron are mixed to the moderator in the spectral shift pipe to control the concentration thereof. With such a constitution, control rods and driving mechanisms are no more necessary, to simplify the structure of the reactor core. This can increase the fuel conversion ratio and control great excess reactivity. Accordingly, a nuclear reactor core of high conversion and high burnup degree can be attained. (I.N.)

  11. Reactor container

    International Nuclear Information System (INIS)

    Kojima, Yoshihiro; Hosomi, Kenji; Otonari, Jun-ichiro.

    1997-01-01

    In the present invention, a catalyst for oxidizing hydrogen to be disposed in a reactor container upon rupture of pipelines of a reactor primary coolant system is prevented from deposition of water droplets formed from a reactor container spray to suppress elevation of hydrogen concentration in the reactor container. Namely, a catalytic combustion gas concentration control system comprises a catalyst for oxidizing hydrogen and a support thereof. In addition, there is also disposed a water droplet deposition-preventing means for preventing deposition of water droplets in a reactor pressure vessel on the catalyst. Then, the effect of the catalyst upon catalytic oxidation reaction of hydrogen can be kept high. The local elevation of hydrogen concentration can be prevented even upon occurrence of such a phenomenon that various kinds of mobile forces in the container such as dry well cooling system are lost. (I.S.)

  12. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

    A description is given of a nuclear reactor and especially a high-temperature reactor in which provision is made within a pressure vessel for a main cavity containing the reactor core and a series of vertical cylindrical pods arranged in spaced relation around the main cavity and each adapted to communicate with the cavity through two collector ducts or headers for the primary fluid which flows downwards through the reactor core. Each pod contains two superposed steam-generator and circulator sets disposed in substantially symmetrical relation on each side of the hot primary-fluid header which conveys the primary fluid from the reactor cavity to the pod, the circulators of both sets being mounted respectively at the bottom and top ends of the pod

  13. Joseph Clover and the cobra: a tale of snake envenomation and attempted resuscitation with bellows in London, 1852.

    Science.gov (United States)

    Ball, C

    2010-07-01

    The Industrial Revolution saw the creation of many new jobs, but probably none more curious than that of zookeeper. The London Zoological Gardens, established for members in 1828, was opened to the general public in 1847. In 1852 the "Head Keeper in the Serpent Room", Edward Horatio Girling, spent a night farewelling a friend departing for Australia. He arrived at work in an inebriated state and was bitten on the face by a cobra that he was handling in a less than sensible manner. He was taken by cab to University College Hospital where he was resuscitated by a number of doctors, including Joseph Clover then the resident medical officer to the hospital and later to become the leading anaesthetist in London. Clover recorded this event in his diary along with the resuscitation method used. The patient eventually died but his treatment created a flurry of correspondence in the medical and lay press. Interestingly, the attempted resuscitation was with bellows, which had been abandoned by the Royal Humane Society twenty years earlier Clover records other cases of resuscitation with bellows at University College Hospital during his time as a resident medical officer there (1848 to 1853). There is a casebook belonging to Joseph Clover in the Geoffrey Kaye Museum, in Melbourne. This story is one of the many interesting stories uncovered during a study of this book and Clover's other personal papers.

  14. Plasma core reactor applications

    International Nuclear Information System (INIS)

    Latham, T.S.; Rodgers, R.J.

    1976-01-01

    Analytical and experimental investigations are being conducted to demonstrate the feasibility of fissioning uranium plasma core reactors and to characterize space and terrestrial applications for such reactors. Uranium hexafluoride (UF 6 ) fuel is injected into core cavities and confined away from the surface by argon buffer gas injected tangentially from the peripheral walls. Power, in the form of thermal radiation emitted from the high-temperature nuclear fuel, is transmitted through fused-silica transparent walls to working fluids which flow in axial channels embedded in segments of the cavity walls. Radiant heat transfer calculations were performed for a six-cavity reactor configuration; each cavity is approximately 1 m in diameter by 4.35 m in length. Axial working fluid channels are located along a fraction of each cavity peripheral wall

  15. Nuclear reactor buildings

    International Nuclear Information System (INIS)

    Nagashima, Shoji; Kato, Ryoichi.

    1985-01-01

    Purpose: To reduce the cost of reactor buildings and satisfy the severe seismic demands in tank type FBR type reactors. Constitution: In usual nuclear reactor buildings of a flat bottom embedding structure, the flat bottom is entirely embedded into the rock below the soils down to the deck level of the nuclear reactor. As a result, although the weight of the seismic structure can be decreased, the amount of excavating the cavity is significantly increased to inevitably increase the plant construction cost. Cross-like intersecting foundation mats are embedded to the building rock into a thickness capable withstanding to earthquakes while maintaining the arrangement of equipments around the reactor core in the nuclear buildings required by the system design, such as vertical relationship between the equipments, fuel exchange systems and sponteneous drainings. Since the rock is hard and less deformable, the rigidity of the walls and the support structures of the reactor buildings can be increased by the embedding into the rock substrate and floor responsivity can be reduced. This enables to reduce the cost and increasing the seismic proofness. (Kamimura, M.)

  16. LMFBR type reactor

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

    1988-01-01

    Purpose: To flatten the power distribution while maintaining the flattening in the axial power distribution in LMFBR type reactors. Constitution: Main system control rods are divided into control rods used for the operation and starting rods used for the starting of the reactor, and the starting rods are disposed in the radial periphery of the reactor core, while the control rods are disposed to the inside of the starting rods. With such a constitution, adjusting rods can be disposed in the region where the radial power peaking is generated to facilitate the flattening of the power distribution even in such a design that the ratio of the number of control rods to that of fuel assemblies is relatively large. That is, in this reactor, the radial power peaking is reduced by about 10% as compared with the conventional reactor core. As a result, the maximum linear power density during operation is reduced by about 10% to increase the thermal margin of the reactor core. If the maximum linear power density is set identical, the number of the fuel assemblies can be decreased by about 10%, to thereby reduce the fuel production cost. (K.M.)

  17. BWR type reactor

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1988-01-01

    Purpose: To inhibit the lowering of the neutron moderation effect due to voids in the upper portion of the reactor core, thereby flatten the axial power distribution. Constitution: Although it has been proposed to enlarge the diameter at the upper portion of a water rod thereby increasing the moderator in the upper portion, since the water rod situates within the channel box, the increase in the capacity thereof is has certain limit. In the present invention, it is designed such that the volume of the region at the outside of the channel box for the fuel assembly to which non-boiling water in the non-boiling water region can enter is made greater in the upper portion than in the lower portion of the reactor core. Thus, if the moderator density in the upper portion of the reactor core should be decreased due to the generation of the voids, the neutron moderating effect in the upper portion of the reactor core is not lowered as compared with the lower portion of the reactor core and, accordingly, the axial power distribution can be flattening more as compared with that in the conventional nuclear reactors. (Takahashi, M.)

  18. Reactor core structure

    International Nuclear Information System (INIS)

    Higashinakagawa, Emiko; Sato, Kanemitsu.

    1992-01-01

    Taking notice on the fact that Fe based alloys and Ni based alloys are corrosion resistant in a special atmosphere of a nuclear reactor, Fe or Ni based alloys are applied to reactor core structural components such as fuel cladding tubes, fuel channels, spacers, etc. On the other hand, the neutron absorption cross section of zirconium is 0.18 barn while that of iron is 2.52 barn and that of nickel is 4.6 barn, which amounts to 14 to 25 times compared with that of zirconium. Accordingly, if the reactor core structural components are constituted by the Fe or Ni based alloys, neutron economy is lowered. Since it is desirable that neutrons contribute to uranium fission with least absorption to the reactor core structural components, the reactor core structural components are constituted with the Fe or Ni based alloys of good corrosion resistance only at a portion in contact with reactor water, that is, at a surface portion, while the main body is constituted with zircalloy in the present invention. Accordingly, corrosion resistnace can be kept while keeping small neutron absorption cross section. (T.M.)

  19. Reactor building

    International Nuclear Information System (INIS)

    Maruyama, Toru; Murata, Ritsuko.

    1996-01-01

    In the present invention, a spent fuel storage pool of a BWR type reactor is formed at an upper portion and enlarged in the size to effectively utilize the space of the building. Namely, a reactor chamber enhouses reactor facilities including a reactor pressure vessel and a reactor container, and further, a spent fuel storage pool is formed thereabove. A second spent fuel storage pool is formed above the auxiliary reactor chamber at the periphery of the reactor chamber. The spent fuel storage pool and the second spent fuel storage pool are disposed in adjacent with each other. A wall between both of them is formed vertically movable. With such a constitution, the storage amount for spent fuels is increased thereby enabling to store the entire spent fuels generated during operation period of the plant. Further, since requirement of the storage for the spent fuels is increased stepwisely during periodical exchange operation, it can be used for other usage during the period when the enlarged portion is not used. (I.S.)

  20. Reactor container

    International Nuclear Information System (INIS)

    Shibata, Satoru; Kawashima, Hiroaki

    1984-01-01

    Purpose: To optimize the temperature distribution of the reactor container so as to moderate the thermal stress distribution on the reactor wall of LMFBR type reactor. Constitution: A good heat conductor (made of Al or Cu) is appended on the outer side of the reactor container wall from below the liquid level to the lower face of a deck plate. Further, heat insulators are disposed to the outside of the good heat conductor. Furthermore, a gas-cooling duct is circumferentially disposed at the contact portion between the good heat conductor and the deck plate around the reactor container. This enables to flow the cold heat from the liquid metal rapidly through the good heat conductor to the cooling duct and allows to maintain the temperature distribution on the reactor wall substantially linear even with the abrupt temperature change in the liquid metal. Further, by appending the good heat conductor covered with inactive metals not only on the outer side but also on the inside of the reactor wall to introduce the heat near the liquid level to the upper portion and escape the same to the cooling layer below the roof slab, the effect can be improved further. (Ikeda, J.)

  1. Skin Inqjuries Reduce Survival and Modulate Corticosterone, C-Reactive Protein, Complement Component 3, IgM, and Prostaglandin E2 after Whole-Body Reactor-Produced Mixed Field (n + γ-Photons Irradiation

    Directory of Open Access Journals (Sweden)

    Juliann G. Kiang

    2013-01-01

    Full Text Available Skin injuries such as wounds or burns following whole-body γ-irradiation (radiation combined injury (RCI increase mortality more than whole-body γ-irradiation alone. Wound-induced decreases in survival after irradiation are triggered by sustained activation of inducible nitric oxide synthase pathways, persistent alteration of cytokine homeostasis, and increased susceptibility to systemic bacterial infection. Among these factors, radiation-induced increases in interleukin-6 (IL-6 concentrations in serum were amplified by skin wound trauma. Herein, the IL-6-induced stress proteins including C-reactive protein (CRP, complement 3 (C3, immunoglobulin M (IgM, and prostaglandin E2 (PGE2 were evaluated after skin injuries given following a mixed radiation environment that might be found after a nuclear incident. In this report, mice received 3 Gy of reactor-produced mixed field (n+γ-photons radiations at 0.38 Gy/min followed by nonlethal skin wounding or burning. Both wounds and burns reduced survival and increased CRP, C3, and PGE2 in serum after radiation. Decreased IgM production along with an early rise in corticosterone followed by a subsequent decrease was noted for each RCI situation. These results suggest that RCI-induced alterations of corticosterone, CRP, C3, IgM, and PGE2 cause homeostatic imbalance and may contribute to reduced survival. Agents inhibiting these responses may prove to be therapeutic for RCI and improve related survival.

  2. Nuclear reactor

    International Nuclear Information System (INIS)

    Rau, P.

    1980-01-01

    The reactor core of nuclear reactors usually is composed of individual elongated fuel elements that may be vertically arranged and through which coolant flows in axial direction, preferably from bottom to top. With their lower end the fuel elements gear in an opening of a lower support grid forming part of the core structure. According to the invention a locking is provided there, part of which is a control element that is movable along the fuel element axis. The corresponding locking element is engaged behind a lateral projection in the opening of the support grid. The invention is particularly suitable for breeder or converter reactors. (orig.) [de

  3. Compilation of the ``Atlas of Gamma-rays from the Inelastic Scattering of Reactor Fast Neutrons'' (1978DE41) by A.M. Demidov, L.I. Govor, Yu. K. Cherepantsev, M.R. Ahmed, S. Al-Najjar, M.A. Al-Amili, N. Al-Assafi, and N. Rammo

    Energy Technology Data Exchange (ETDEWEB)

    Hurst, Aaron M. [Univ. of California, Berkeley, CA (United States); Bernstein, Lee A. [Univ. of California, Berkeley, CA (United States); Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Chong, Su-Ann [Univ. of California, Berkeley, CA (United States)

    2017-07-26

    A Structured Query Language (SQL) relational database has been developed based on the original (n,n'gamma) work carried out by A.M. Demidov et al., at the Nuclear Research Institute in Baghdad, Iraq [``Atlas of Gamma-Ray Spectra from the Inelastic Scattering of Reactor Fast Neutrons'', Nuclear Research Institute, Baghdad, Iraq (Moscow, Atomizdat 1978)] for 105 independent measurements comprising 76 elemental samples of natural composition and 29 isotopically-enriched samples. The information from this ATLAS includes: gamma-ray energies and intensities; nuclide and level data corresponding to where the gamma-ray originated from; target (sample) experimental-measurement data. Taken together, this information allows for the extraction of the flux-weighted (n,n'gamma) cross sections for a given transition relative to a defined value. Currently, we are using the fast-neutron flux-weighted partial gamma-ray cross section from ENDF/B-VII.1 for the production of the 847-keV transition from the first excited 2+ state to the 0+ ground state in 56Fe, 468 mb. This value also takes into account contributions to the 847-keV transition following beta(-) decay of 56Mn formed in the 56Fe(n,p) reaction. However, this value can easily be adjusted to accommodate the user preference. The (n,n'gamma) data has been compiled into a series of ASCII comma separated value tables and a suite of Python scripts and C modules are provided to build the database. Upon building, the database can then be interacted with directly via the SQLite engine or accessed via the Jupyter Notebook Python-browser interface. Several examples exploiting these utilities are also provided with the complete software package.

  4. Uit de donkere dagen van voor linguistic turn oftewel wat J. M. ...

    African Journals Online (AJOL)

    Hugo Claus, poet. In Hugo Claus, Greetings: Selected Poems. Vert. John Iron, New York: Harcourt; overdruk in J. M. Coetzee, Inner Workings. Literary Essay 2000-2005. New York: Viking,. 2007. _____. 2007. Wat is een klassieke roman. Vert. P. Bergsma. Amsterdam: Cossee. Conrad, Joseph. 1899. The Heart of Darkness.

  5. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    A nuclear reactor containment vessel faced internally with a metal liner is provided with thermal insulation for the liner, comprising one or more layers of compressible material such as ceramic fiber, such as would be conventional in an advanced gas-cooled reactor and also a superposed layer of ceramic bricks or tiles in combination with retention means therefor, the retention means (comprising studs projecting from the liner, and bolts or nuts in threaded engagement with the studs) being themselves insulated from the vessel interior so that the coolant temperatures achieved in a High-Temperature Reactor or a Fast Reactor can be tolerated with the vessel. The layer(s) of compressible material is held under a degree of compression either by the ceramic bricks or tiles themselves or by cover plates held on the studs, in which case the bricks or tiles are preferably bedded on a yielding layer (for example of carbon fibers) rather than directly on the cover plates

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Miyashita, Akio.

    1981-01-01

    Purpose: To facilitate and accelerate a leakage test of valves of a main steam pipe by adding a leakage test partition valve thereto. Constitution: A leakage testing partition valve is provided between a pressure vessel for a nuclear reactor and the most upstream side valve of a plurality of valves to be tested for leakage, a testing branch pipe is communicated with the downstream side of the partition valve, and the testing water for preventing leakage is introduced thereto through the branch pipe. Since main steam pipe can be simply isolated by closing the partition valve in the leakage test, the leakage test can be conducted without raising or lowering the water level in the pressure vessel, and since interference with other work in the reactor can be eliminated, the leakage test can be readily conducted parallel with other work in the reactor in a short time. Clean water can be used without using reactor water as the test water. (Yoshihara, H.)

  7. REACTOR SHIELD

    Science.gov (United States)

    Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.

    1959-02-17

    Radiation shield construction is described for a nuclear reactor. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. Reactor coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the reactor container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the reactor container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.

  8. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  9. Breeder reactors

    International Nuclear Information System (INIS)

    Gollion, H.

    1977-01-01

    The reasons for the development of fast reactors are briefly reviewed (a propitious neutron balance oriented towards a maximum uranium burnup) and its special requirements (cooling, fissile material density and reprocessing) discussed. The three stages in the French program of fast reactor development are outlined with Rapsodie at Cadarache, Phenix at Marcoule, and Super Phenix at Creys-Malville. The more specific features of the program of research and development are emphasized: kinetics and the core, the fuel and the components [fr

  10. Nuclear reactor

    International Nuclear Information System (INIS)

    Schulze, I.; Gutscher, E.

    1980-01-01

    The core contains a critical mass of UN or U 2 N 3 in the form of a noncritical solution with melted Sn being kept below a N atmosphere. The lining of the reactor core consists of graphite. If fission progresses part of the melted metal solution is removed and cleaned from fission products. The reactor temperatures lie in the range of 300 to 2000 0 C. (Examples and tables). (RW) [de

  11. Nuclear Reactor RA Safety Report, Vol. 4, Reactor

    International Nuclear Information System (INIS)

    1986-11-01

    RA research reactor is thermal heavy water moderated and cooled reactor. Metal uranium 2% enriched fuel elements were used at the beginning of its operation. Since 1976, 80% enriched uranium oxide dispersed in aluminium fuel elements were gradually introduced into the core and are the only ones presently used. Reactor core is cylindrical, having diameter 40 cm and 123 cm high. Reaktor core is made up of 82 fuel elements in aluminium channels, lattice is square, lattice pitch 13 cm. Reactor vessel is cylindrical made of 8 mm thick aluminium, inside diameter 140 cm and 5.5 m high surrounded with neutron reflector and biological shield. There is no containment, the reactor building is playing the shielding role. Three pumps enable circulation of heavy water in the primary cooling circuit. Degradation of heavy water is prevented by helium cover gas. Control rods with cadmium regulate the reactor operation. There are eleven absorption rods, seven are used for long term reactivity compensation, two for automatic power regulation and two for safety shutdown. Total anti reactivity of the rods amounts to 24%. RA reactor is equipped with a number of experimental channels, 45 vertical (9 in the core), 34 in the graphite reflector and two in the water biological shield; and six horizontal channels regularly distributed in the core. This volume include detailed description of systems and components of the RA reactor, reactor core parameters, thermal hydraulics of the core, fuel elements, fuel elements handling equipment, fuel management, and experimental devices [sr

  12. Space nuclear reactor safety

    International Nuclear Information System (INIS)

    Damon, D.; Temme, M.; Brown, N.

    1990-01-01

    Definition of safety requirements and design features of the SP-100 space reactor power system has been guided by a mission risk analysis. The analysis quantifies risk from accidental radiological consequences for a reference mission. Results show that the radiological risk from a space reactor can be made very low. The total mission risk from radiological consequences for a shuttle-launched, earth orbit SP-100 mission is estimated to be 0.05 Person-REM (expected values) based on a 1 mREM/yr de Minimus dose. Results are given for each mission phase. The safety benefits of specific design features are evaluated through risk sensitivity analyses

  13. Fast reactors

    International Nuclear Information System (INIS)

    Vasile, A.

    2001-01-01

    Fast reactors have capacities to spare uranium natural resources by their breeding property and to propose solutions to the management of radioactive wastes by limiting the inventory of heavy nuclei. This article highlights the role that fast reactors could play for reducing the radiotoxicity of wastes. The conversion of 238 U into 239 Pu by neutron capture is more efficient in fast reactors than in light water reactors. In fast reactors multi-recycling of U + Pu leads to fissioning up to 95% of the initial fuel ( 238 U + 235 U). 2 strategies have been studied to burn actinides: - the multi-recycling of heavy nuclei is made inside the fuel element (homogeneous option); - the unique recycling is made in special irradiation targets placed inside the core or at its surroundings (heterogeneous option). Simulations have shown that, for the same amount of energy produced (400 TWhe), the mass of transuranium elements (Pu + Np + Am + Cm) sent to waste disposal is 60,9 Kg in the homogeneous option and 204.4 Kg in the heterogeneous option. Experimental programs are carried out in Phenix and BOR60 reactors in order to study the feasibility of such strategies. (A.C.)

  14. The art of Joseph Beuys and Vision Andreas Huyssen in Postmodernity A arte de Joseph Beuys e a visão de Andreas Huyssen na pós-modernidade

    Directory of Open Access Journals (Sweden)

    Lívia Garcez de Oliveira Padilha

    2012-04-01

    Full Text Available This article aims do present reflections on art in post-modernity, which encourages a reading of the ambivalence between the technique and aesthetics. We focus the environmentalist work of artist Joseph Beuys and the critical German essayist Andreas Huyssen and the paradoxical thinking of vanguard and mass culture. Is it possible to think like that in a dualist way? Or we can see a shift in sensitivity towards what touches us by affection? We believe, nevertheless, that exists a permanent state of artistic tension which stimulates a more relativistic than categorical culture in the XXI century.Este artigo tem como objetivo apresentar reflexões sobre a arte na pós-modernidade - que estimula uma leitura da ambivalência entre técnica e estética - por meio de duas obras “ambientalistas” do artista plástico Joseph Beuys e do olhar crítico, mas de cunho compreensivo, do ensaísta alemão Andreas Huyssen. O enfoque é o paradoxo entre a arte dita culta ou de vanguarda (? e a sua possível massificação (?. Estas duas expressões – vanguarda e massificação - ainda se sustentam na paisagem pós-moderna? Ou percebe-se um redirecionamento da sensibilidade em direção àquilo que nos toca pela afetividade? Consideramos, por meio da fenomenologia, que se enfrenta, em tempos pós-modernos, um permanente estado de tensionamento artístico, o que estimula uma visão mais relativista do que categórica da cultura no século XXI.

  15. Baron von Zach's business relations with the Munich entrepreneur Joseph von Utzschneider (German Title: Geschäftsbeziehungen des Barons von Zach zu dem Münchner Unternehmer Joseph von Utzschneider)

    Science.gov (United States)

    Schneider, Ivo

    The relationship between the astronomer von Zach on the one side and the entrepreneur Joseph von Utzschneider and his partner Georg von Reichenbach on the other dates presumably from the year 1807 when Zach spent two months in Munich. Already in the same year Zach had ordered an instrument for himself and began to solicit business for the institute of Reichenbach, Utzschneider, and Liebherr, which was founded in 1804. One of the clients canvassed by Zach was the director of the observatory in Naples Zuccari. Zuccari had ordered the whole equipment for the new observatory from this institute in 1813. The instruments for Naples, which were completed in 1814, were sent accompanied by Reichenbach by land and sea to their destination where Reichenbach supervised their setup. At that time Reichenbach had separated from Utzschneider who kept the optical institute in Benediktbeuern with his new partner Joseph von Fraunhofer whereas Reichenbach became owner of the mathematical-mechanical institute in Munich. For personal and economical reasons Utzschneider began soon after to produce not only optical glass but also optical devices similar to those offered by Reichenbach. As soon as two institutes in Munich competed against each other on the market for sophisticated geodetical and astronomical instruments Zach sided with Utzschneider. Zach's main professional argument for this decision was that both competitors got the optical glass for their instruments from Utzschneider's optical institute in Benediktbeuern. This meant that Utzschneider had first choice and so the optical part of his instruments could be considered as better than that of Reichenbach`s instruments. Zach's role as an agent in Italy and France for the sale of products coming from Utzschneider's manufactories is highlighted by three of Zach's letters to Utzschneider from 1817 and 1818, two of which are reproduced here for the first time.

  16. L’influence de l’eugénisme galtonien dans la pensée de Joseph Alois Schumpeter The Influence of Eugenics in Joseph Alois Schumpeter’s theory

    Directory of Open Access Journals (Sweden)

    Fabrice Dannequin

    2012-11-01

    Full Text Available Dans sa théorie du capitalisme, Joseph Alois Schumpeter mobilise l’eugénique, notamment les travaux de Francis Galton. Ce dernier a élaboré une vision hiérarchisée et héréditariste des hommes. Il l’a notamment appliquée à la question de la pauvreté en reprenant les données empiriques de Charles Booth. Schumpeter reprend ces éléments comme socle de l’explication de l’inégalité sociale et dans la construction de sa théorie de l’entrepreneuriat. Les entrepreneurs constituent une élite se démarquant de la masse, en engendrant l’évolution de la société du fait de leurs talents innés. Le capitalisme ne peut déboucher sur la disparition totale de la pauvreté. En effet, les individus biologiquement moins « dotés » sont condamnés à rester au bas de l’échelle sociale.In his theory about capitalism, Joseph Alois Schumpeter uses eugenics, and especially Francis Galton’s work. The former has conceived a hierarchized vision of society, and a hereditary vision of the transmission of talents. He notably applied it to the question of poverty by using Charles Booth’s empirical data. Schumpeter uses these elements both as an explanation of social inequality and as a basis of his theory of entrepreneurship. To him, the entrepreneurs are an elite standing out against the masses since they have the innate talents to generate evolution. Capitalism cannot totally eradicate poverty. Indeed, the least biologically gifted are bound to remain at the bottom of the social ladder.

  17. Machado-Joseph disease versus hereditary spastic paraplegia: case report Doença de Machado-Joseph versus paraplegia espástica hereditária: relato de caso

    Directory of Open Access Journals (Sweden)

    Hélio A. Ghizoni Teive

    2001-09-01

    Full Text Available Machado-Joseph disease (MJD is the most common autosomal dominant spinocerebellar ataxia and presents great phenotypic variability. MJD presenting with spastic paraparesis was recently described in Japanese patients. We report the case of 41-year-old woman with the phenotype of complicated hereditary spastic paraplegia. Her father died at the age of 56 years due to an undiagnosed progressive neurological disease that presented parkinsonism. She had an expanded allele with 66 CAG repeats and a normal allele with 22 repeats in the gene of MJD. MJD should be considered in the differential diagnosis of autosomal dominant complicated HSP. A patient with the phenotype of complicated HSP and relatives with other clinical features of a neurodegenerative disease should raise the suspicion of MJD.A doença de Machado-Joseph (DMJ é a ataxia espinocerebelar autossômica dominante mais prevalente e apresenta grande variabilidade fenotípica. DMJ apresentando-se com o fenótipo de paraparesia espástica foi recentemente descrita em pacientes japoneses. Relatamos o caso de uma paciente com fenótipo de paraplegia espástica hereditária (PEH "complicada". Seu pai faleceu com 56 anos de uma doença neurológica progressiva que cursava com parkinsonismo. Estudo genético pela técnica de reação em cadeia da polimerase mostrou um alelo de tamanho normal com 22 repetições e um alelo de tamanho expandido com 66 repetições para o tripleto CAG no gene da DMJ. A DMJ deve ser considerada no diagnóstico diferencial das PEH complicadas autossômicas dominantes. Em um paciente com quadro de PEH e outros familiares com fenótipos diferentes de doenças degenerativas deve-se suspeitar de DMJ.

  18. Fusion reactor problems

    International Nuclear Information System (INIS)

    Carruthers, R.

    It is pointed out that plasma parameters for a fusion reactor have been fairly accurately defined for many years, and the real plasma physics objective must be to find the means of achieving and maintaining these specifiable parameters. There is good understanding of the generic technological problems: breading blankets and shields, radiation damage, heat transfer and methods of magnet design. The required plasma parameters for fusion self-heated reactors are established at ntausub(E) approximately 2.10 14 cm -3 sec, plasma radius 1.5 to 3 m, wall loading 5 to 10 MW cm -2 , temperature 15 keV. Within this model plasma control by quasi-steady burn as a key problem is studied. It is emphasized that the future programme must interact more closely with engineering studies and should concentrate upon research which is relevant to reactor plasmas. (V.P.)

  19. Reactor control device

    International Nuclear Information System (INIS)

    Araki, Takao; Inoue, Toyokazu.

    1981-01-01

    Purpose: To protect the reactor floor by alleviating the shock imparted to the reactor floor by a dropped control rod when a wire rope accidentally breaks. Constitution: A control rod is hung by wire rope from a control rod drive, and shock absorbers are mounted at the upper and lower portions of the control rod. The outer diameter of the upper shock absorber is made larger than the inner diameter of a control rod inserting hole formed in the reactor core. If the control rod drops, the upper absorber is stopped at the upper tapered portion of the inserting hole. Thus, the dropping energy of the control rod can be sufficiently absorbed by the upper and lower shock absorbers. (Kamimura, M.)

  20. Reactor container facility

    International Nuclear Information System (INIS)

    Saito, Takashi; Nagasaka, Hideo.

    1990-01-01

    A dry-well pool for spontaneously circulating stored pool water and a suppression pool for flooding a pressure vessel by feeding water, when required, to a flooding gap by means of spontaneous falling upto the flooding position, thereby flooding the pressure vessel are contained at the inside of a reactor container. Thus, when loss of coolant accidents such as caused by main pipe rupture accidents should happen, pool water in the suppression pool is supplied to the flooding gap by spontaneously falling. Further, if the flooding water uprises exceeding a predetermined level, the flooding gap is in communication with the dry-well pool at the upper and the lower portions respectively. Accordingly, flooding water at high temperature heated by the after-heat of the reactor core is returned again into the flooding gap to cool the reactor core repeatedly. (T.M.)

  1. BWR type reactor system

    International Nuclear Information System (INIS)

    Morooka, Shin-ichi.

    1980-01-01

    Purpose: To reduce the internal structure in a reactor by rapidly and efficiently transferring heat generated in a reactor core out of the reactor and eliminating the danger of radiation exposure. Constitution: Steam generated in a pressure vessel is introduced into heat pipe group by inserting the heat pipe group into the steam dome of the pressure vessel. The introduced steam is condensed in the heat pipes to transfer the heat of the steam to the heat pipe group. The transferred heat is transmitted to a heat exchanger provided out of a containment vessel to generate steam to operate a turbine. Thus, it is not necessary to introduce the steam including radioactive substance externally and can remove only the heat so as to carry out the desired purpose. (Kamimura, M.)

  2. Natural convection type reactor

    International Nuclear Information System (INIS)

    Nakayama, Takafumi; Horiuchi, Tetsuo; Moriya, Kimiaki; Matsumoto, Masayoshi; Akita, Minoru.

    1988-01-01

    Purpose: To improve the reliability by decreasing the number of dynamic equipments and safely shutdown the reactor core upon occurrence of accidents. Constitution: A pressure relief valve and a pressurizing tank or gravitational water falling tank disposed to the main steam pipe of a reactor are installed in combination. Upon loss-of-coolant accident, the pressure relief valve is opened to reduce the pressure in the reactor pressure vessel to the operation pressure for each of the tanks, thereby enabling to inject water in the pressurizing tank at first and, thereafter, water in the gravitational water falling tank successively to the inside of the pressure vessel. By utilizing the natural force in this way, the reliability can be improved as compared with the case of pumped water injection. Further, by injecting an aqueous boric acid to a portion of a plurality of tanks, if the control rod insertion becomes impossible, aqueous boric acid can be injected. (Takahashi, M.)

  3. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Hoizumi, Atsushi.

    1986-01-01

    Purpose: To grasp the margin for the limit value of the power distribution peaking factor inside the reactor under operation by using the reactor power distribution monitor. Constitution: The monitor is composed of the 'constant' file, (to store in-reactor power distributions obtained from analysis), TIP and thermocouple, lateral output distribution calibrating apparatus, axial output distribution synthesizer and peaking factor synthesizer. The lateral output distribution calibrating apparatus is used to make calibration by comparing the power distribution obtained from the thermocouples to the power distribution obtained from the TIP, and then to provide the power distribution lateral peaking factors. The axial output distribution synthesizer provides the power distribution axial peaking factors in accordance with the signals from the out-pile neutron flux detector. These axial and lateral power peaking factors are synthesized with high precision in the three-dimensional format and can be monitored at any time. (Kamimura, M.)

  4. Joseph Roth in den Niederlanden und Flandern: Vermittlung, Vernetzung und Orchestierung eines vielseitigen Autors im niederländischsprachigen Kontext 1924-1940

    NARCIS (Netherlands)

    Snick, E.S.

    2011-01-01

    This dissertation investigates the contemporary mediators and networks that played an important role in the canonization of Joseph Roth’s (original and translated) work in Flanders and the Netherlands. These mediators and networks made a substantial contributionto Roth’s intellectual and literary

  5. Review: Joseph Patrick Ganahl, Corruption, Good Governance, and the African State: A Critical Analysis of the Political-Economic Foundations of Corruption in Sub-Saharan Africa (2013

    Directory of Open Access Journals (Sweden)

    Reinhart Kößler

    2015-01-01

    Full Text Available Review of the monograph:Joseph Patrick Ganahl, Corruption, Good Governance, and the African State: A Critical Analysis of the Political-Economic Foundations of Corruption in Sub-Saharan Africa, Potsdam: Potsdam University Press, 2013, ISBN 9783869562483, 300 pp.

  6. A delicate balance global perspectives on innovation and tradition in the history of mathematics a festschrift in honor of Joseph W. Dauben

    CERN Document Server

    Horng, Wann-Sheng

    2015-01-01

    Joseph W. Dauben, a leading authority on the history of mathematics in Europe, China, and North America, has played a pivotal role in promoting international scholarship over the last forty years. This Festschrift volume, showcasing recent historical research by leading experts on three continents, offers a global perspective on important themes in this field.

  7. 33 CFR 334.670 - Gulf of Mexico south and west of Apalachicola, San Blas, and St. Joseph bays; air-to-air firing...

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 3 2010-07-01 2010-07-01 false Gulf of Mexico south and west of Apalachicola, San Blas, and St. Joseph bays; air-to-air firing practice range, Tyndall Air Force Base, Fla. 334..., DEPARTMENT OF DEFENSE DANGER ZONE AND RESTRICTED AREA REGULATIONS § 334.670 Gulf of Mexico south and west of...

  8. Being a Stranger and the Strangeness of Being: Joseph Conrad's "The Secret Sharer" as an Allegory of Being in Education

    Science.gov (United States)

    Schwieler, Elias

    2013-01-01

    Joseph Conrad's "The Secret Sharer" has often been associated with what can be called initiation stories. However, in this article I argue that Conrad's text is more than that. It can, I suggest, be read as an allegory of the inaccessibility to reveal the essence of being in command, being in education, and also the…

  9. Romantic Joseph Lenné Landscape Park in Zatonie Near Zielona Góra as a Relic of Garden Art - Modern-Day Transformations and Threats

    Directory of Open Access Journals (Sweden)

    Kochańska Agnieszka

    2016-09-01

    Full Text Available The romantic landscape park was established in 1824 by order of one of the best-known aristocrats at the time, Princess Dorothea Talleyrand Perigold, Dutchess of Dino. The park is an example of amenity horticulture of artistic value that has survived to this day. The creator of the park was the talented landscape architect Peter Joseph Lenné.

  10. Three pioneers of comparative psychology in America, 1843-1890: Lewis H. Morgan, John Bascom, and Joseph LeConte.

    Science.gov (United States)

    Johnston, Timothy D

    2003-02-01

    Scientific comparative psychology in America dates from the mid-1890s, but there is a body of earlier literature on the topic, written during a period of theistic debates over Darwinian evolution. The anthropologist Lewis H. Morgan rejected instinct as an explanation of animal behavior in 1843 and defended the mental similarities between animals and humans, although he was not an evolutionist. John Bascom's textbook Comparative Psychology (1878) is the earliest American work to use that title, and its theistic approach anticipates some arguments found in much later evolutionary works. Beginning in 1860, the geologist Joseph LeConte, who is well known for defending the compatibility of evolution and religion, wrote several articles in which he outlined a comparative evolutionary approach to psychological problems. However, these writers did not establish a coherent research tradition and were ignored by the "New Psychologists" of the 1880s.

  11. José Ignacio Moreno. Un teólogo peruano. Entre Montesquieu y Joseph de Maistre

    Directory of Open Access Journals (Sweden)

    Victor Samuel Rivera

    2013-01-01

    Full Text Available José Ignacio Moreno es uno de los fundadores de la independencia del Perú. En calidad de tal acompañó el proyecto del General rioplatense José de San Martín de transformar en 1822 la monarquía peruana en un reino independiente. Pero, a diferencia de la multitud de sus contemporáneos, la historiografía apenas lo presenta como un circunstante en la epopeya de la emancipación, de quien no se conserva ni un retrato. El motivo es la extraña adherencia de este personaje a las ideas del ultramontanismo y su temprana cercanía con la obra del contrarrevolucionario francés Joseph de Maistre. Un discurso monárquico extremista en 1822 lo colocaría como el fundador involuntario del Perú como República.

  12. A comparative study of blood flow in the cerebellum and brainstem between Machado-Joseph disease and olivopontocerebellar atrophy

    International Nuclear Information System (INIS)

    Fukumitsu, Nobuyoshi; Suzuki, Masahiko; Ito Yasuhiko; Iguchi, Yasuyuki; Mori, Yutaka

    2002-01-01

    In recent years, the neurogenic and pathological differences between Machado-Joseph disease (MJD) and sporadic olivopontocerebellar atrophy (OPCA) have been clarified. We performed N-isopropyl-p-[I-123] iodoamphetamine (IMP) SPECT on 9 patients with MJD and 12 patients with OPCA. The blood flow of the cerebellum in the MJD group was significantly decreased than that of the control group (p<0.0001). That of OPCA group was significantly decreased than those of the control and MJD groups (p<0.0001, respectively). The blood flow of the brainstem in the MJD group was significantly decreased than that of the control group (p<0.001). That of OPCA group was significantly decreased than those of the control and MJD groups (p<0.0001, respectively). The blood flow of cerebellum and brainstem in the OPCA group were much decreased than those of MJD group. IMP distribution pattern in MJD patients obviously differed from that of OPCA patients. (author)

  13. A "next generation" ethics committee. St. Joseph Health system has integrated performance-improvement features into its ethics work.

    Science.gov (United States)

    Murphy, Kevin

    2006-01-01

    Understanding the limitations that accompany the traditional model of ethics committees, St. Joseph Health System (SJHS), Orange, CA, has been working to integrate ethics expertise and quality-improvement methodology into its "Next Generation Model" (NG Model) for such committees. However, moving from a traditional structure to the NG Model (introduced to SJHS facilities in 1999) brought some challenges, not the least of which was a deep-rooted culture of resistance to change. Following a 2004 audit of how the NG model was working, some common challenges were identified. To deal with those challenges, SJHS developed some tools and techniques that have helped ease the ongoing transition. These tools have helped the system's ethics committees address such issues as collaboration for the sake of organizational integration, setting goals, and measuring performance of various ethics roles.

  14. Handwerklicher Hintergrund und Perspektiven akademischer Studien. Zum Frühwerk Joseph Führichs in Böhmen

    Directory of Open Access Journals (Sweden)

    Machalíková, Pavla

    2013-11-01

    Full Text Available The study of the early works by Joseph Führich helps to elucidate his role in the formation of the national schools of painting as understood by the early 19th century. It also reveals the links between the academic schooling and paintings of the artist (regarded as one of the leading representatives of Romanticism in the early 1820s in Prague and his commissioned works of the period intended for more traditional clients and public – altar paintings for Northern Bohemian churches. An analysis of his most important paintings from around the mid-1820s indicates, that he managed to integrate various elements into highly specific personal style: craftsmanship acquired in his father's workshop, elements inspired by old art, academic schooling, and inspiration provided by contemporary Romantic art and iconography.

  15. A question of merit: John Hutton Balfour, Joseph Hooker and the 'concussion' over the Edinburgh chair of botany.

    Science.gov (United States)

    Bellon, Richard

    2005-03-01

    In 1845, Robert Graham's death created a vacancy for the traditionally dual appointment to the University of Edinburgh's chair of botany and the Regius Keepership of the Edinburgh Royal Botanic Garden. John Hutton Balfour and Joseph Hooker emerged as the leading candidates. The contest quickly became embroiled in long running controversies over the nature and control of Scottish university education at a time of particular social and political tension after a recent schism in Church of Scotland. The politics of the appointment were complicated by the fact that the Edinburgh Town Council (which preferred Balfour) chose the chair while the keepership was under the patronage of the Westminster government (which preferred Hooker). Balfour eventually emerged triumphant after a bitter campaign marked on all sides by intense politicking. The struggle to replace Graham provides a case study in how Victorian men of science adapted their aspirations to the practical realities of life in industrial, reforming, imperial, multinational Britain.

  16. Generation IV reactors: reactor concepts

    International Nuclear Information System (INIS)

    Cardonnier, J.L.; Dumaz, P.; Antoni, O.; Arnoux, P.; Bergeron, A.; Renault, C.; Rimpault, G.; Delpech, M.; Garnier, J.C.; Anzieu, P.; Francois, G.; Lecomte, M.

    2003-01-01

    Liquid metal reactor concept looks promising because of its hard neutron spectrum. Sodium reactors benefit a large feedback experience in Japan and in France. Lead reactors have serious assets concerning safety but they require a great effort in technological research to overcome the corrosion issue and they lack a leader country to develop this innovative technology. In molten salt reactor concept, salt is both the nuclear fuel and the coolant fluid. The high exit temperature of the primary salt (700 Celsius degrees) allows a high energy efficiency (44%). Furthermore molten salts have interesting specificities concerning the transmutation of actinides: they are almost insensitive to irradiation damage, some salts can dissolve large quantities of actinides and they are compatible with most reprocessing processes based on pyro-chemistry. Supercritical water reactor concept is based on operating temperature and pressure conditions that infers water to be beyond its critical point. In this range water gets some useful characteristics: - boiling crisis is no more possible because liquid and vapour phase can not coexist, - a high heat transfer coefficient due to the low thermal conductivity of supercritical water, and - a high global energy efficiency due to the high temperature of water. Gas-cooled fast reactors combining hard neutron spectrum and closed fuel cycle open the way to a high valorization of natural uranium while minimizing ultimate radioactive wastes and proliferation risks. Very high temperature gas-cooled reactor concept is developed in the prospect of producing hydrogen from no-fossil fuels in large scale. This use implies a reactor producing helium over 1000 Celsius degrees. (A.C.)

  17. Research reactors - an overview

    International Nuclear Information System (INIS)

    West, C.D.

    1997-01-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs

  18. Comparative Aesthetics of the Manly Face in the Parties of the Prophet Joseph and Zuleika from Safavid Era to the Contemporary Era

    Directory of Open Access Journals (Sweden)

    Maryam Shahbazi

    2017-02-01

    Full Text Available One of the noteworthy stories for the Iranian writers and painters is the story of Joseph and Zuleika. This story has elegantly been described many times in the poetry of Iranian famous poets and many painters have sought to illustrate this story. One of the themes of this story which has been considered in the present research is the party of Joseph and Zuleika in confronting with Egyptian women. Because the subject matter of this party has been Joseph’s beauty and it has been confirmed by a large number of people. Therefore, the painters have tried to picture the most beautiful human being by using all visual techniques. This research studies the aesthetics of the Joseph’s figure from Safavid School to the art of the contemporary era. With this assumption that in the Iranian painting, there has been a certain principle for painting the body and face of the most beautiful people; the present paper with the aim of finding the principles of men’s body and facial aesthetic has done the comparative study by concentration on the painting and designing of the body and face of Joseph in the figures. Some questions have been presented in this regard including whether it is possible to find an aesthetic approach common to all Iranian painting schools to show the most beautiful manly face and body? Whether exemplary beauty of Joseph is expressible by an indicator? What relation has the exemplary of Joseph had with the schools of Safavid art and the following schools? The method of this research is comparative and content analysis. The paper refers to the written and illustrated sources. The statistical society, including six ceremonies of painting and drawing, has been analyzed from Safavid school till the contemporary art; also, painter artists of this circle have been introduced. Matching the theoretical findings with the men’s most beautiful appearance manifested in the statue of majesty Joseph causes the acquisition of the embodied beauty

  19. Pressure tube reactor

    International Nuclear Information System (INIS)

    Seki, Osamu; Kumasaka, Katsuyuki.

    1988-01-01

    Purpose: To remove the heat of reactor core using a great amount of moderators at the periphery of the reactor core as coolants. Constitution: Heat of a reactor core is removed by disposing a spontaneous recycling cooling device for cooling moderators in a moderator tank, without using additional power driven equipments. That is, a spontaneous recycling cooling device for cooling the moderators in the moderator tank is disposed. Further, the gap between the inner wall of a pressure tube guide pipe disposed through the vertical direction of a moderator tank and the outer wall of a pressure tube inserted through the guide pipe is made smaller than the rupture distortion caused by the thermal expansion upon overheating of the pressure tube and greater than the minimum gap required for heat shiels between the pressure tube and the pressure tube guide pipe during usual operation. In this way, even if such an accident as can not using a coolant cooling device comprising power driven equipment should occur in the pressure tube type reactor, the rise in the temperature of the reactor core can be retarded to obtain a margin with time. (Kamimura, M.)

  20. BWR type nuclear reactors

    International Nuclear Information System (INIS)

    Yamamoto, Toru.

    1987-01-01

    Purpose: To obtain reactor core characteristics with less changes in the excess reactivity due to fuel burnup even when the operation period varies. Constitution: In a BWR type reactor where fuel assemblies containing fuel rods incorporated with burnable poisons are arranged, the fuel assemblies are grouped into first fuel assemblies and second fuel assemblies. Then, the number of fuel rods incorporated with burnable poisons within the first fuel assemblies is made greater than that of the second fuel rods, while the concentration of the burnable poisons in the fuel rods incorporated with the burnable poisons in the first fuel assemblies is made lower than that of the fuel rods incorporated with the burnable poisons in the second fuel assemblies. In the BWR type reactor constituted in this way, the reactor core characteristics can be improved by changing the ratio between the first fuel assemblies and the second fuel assemblies charged to the reactor core, thereby decreasing the changes in the burnup of the excess reactivity. (Kamimura, M.)

  1. The reactor Cabri

    International Nuclear Information System (INIS)

    Ailloud, J.; Millot, J.P.

    1964-01-01

    It has become necessary to construct in France a reactor which would permit the investigation of the conditions of functioning of future installations, the choice, the testing and the development of safety devices to be adopted. A water reactor of a type corresponding to the latest CEA constructions in the field of laboratory or university reactors was decided upon: it appeared important to be able to evaluate the risks entailed and to study the possibilities of increasing the power, always demanded by the users; on the other hand, it is particularly interesting to clarify the phenomena of power oscillation and the risks of burn out. The work programme for CABRI will be associated with the work carried out on the American Sperts of the same type, during its construction, very useful contacts were made with the American specialists who designed the se reactors. A brief description of the reactor is given in the communication as well as the work programme for the first years with respect to the objectives up to now envisaged. Rough description of the reactor. CABRI is an open core swimming-pool reactor without any lateral protection, housed in a reinforced building with controlled leakage, in the Centre d'Etudes Nucleaires de Cadarache. It lies alone in the middle of an area whose radius is 300 meters long. Control and measurements equipment stand out on the edge of that zone. It consumes MTR fuel elements. The control-safety rods are propelled by compressed air. The maximum flow rate of cooling circuit is 1500 m 3 /h. Transient measurements are recorded in a RW330 unit. Aims and work programme. CABRI is meant for: - studies on the safety of water reactors - for the definition of the safety margins under working conditions: research of maximum power at which a swimming-pool reactor may operate with respect to a cooling accident, of local boiling effect on the nuclear behaviour of the reactor, performances of the control and safety instruments under exceptional

  2. m m m contreras turrubiartes

    Indian Academy of Sciences (India)

    Home; Journals; Bulletin of Materials Science. M M M CONTRERAS TURRUBIARTES. Articles written in Bulletin of Materials Science. Volume 40 Issue 6 October 2017 pp 1225-1230. Thickness and photocatalytic activity relation in TiO 2 :N films grown by atomic layer deposition with methylene-blue and E. coli bacteria.

  3. Nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Prescott, R F; George, B V; Baglin, C J

    1978-05-10

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given.

  4. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1978-01-01

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given. (UK)

  5. Bioconversion reactor

    Science.gov (United States)

    McCarty, Perry L.; Bachmann, Andre

    1992-01-01

    A bioconversion reactor for the anaerobic fermentation of organic material. The bioconversion reactor comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the reactor but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Scholz, M.

    1976-01-01

    An improvement of the accessibility of that part of a nuclear reactor serving for biological shield is proposed. It is intended to provide within the biological shield, distributed around the circumference of the reactor pressure vessel, several shielding chambers filled with shielding material, which are isolated gastight from the outside by means of glass panes with a given bursting strength. It is advantageous that, on the one hand, inspection and maintenance will be possible without great effort and, on the other, a large relief cross section will be at desposal if required. (UWI) [de

  7. NEUTRONIC REACTOR

    Science.gov (United States)

    Wigner, E.P.; Weinberg, A.W.; Young, G.J.

    1958-04-15

    A nuclear reactor which uses uranium in the form of elongated tubes as fuel elements and liquid as a coolant is described. Elongated tubular uranium bodies are vertically disposed in an efficient neutron slowing agent, such as graphite, for example, to form a lattice structure which is disposed between upper and lower coolant tanks. Fluid coolant tubes extend through the uranium bodies and communicate with the upper and lower tanks and serve to convey the coolant through the uranium body. The reactor is also provided with means for circulating the cooling fluid through the coolant tanks and coolant tubes, suitable neutron and gnmma ray shields, and control means.

  8. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    The method of operating a water-cooled neutronic reactor having a graphite moderator is described which comprises flowing a gaseous mixture of carbon dioxide and helium, in which the helium comprises 40--60 volume percent of the mixture, in contact with the graphite moderator. 2 claims, 4 figures

  9. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield

  10. Reactor facility

    International Nuclear Information System (INIS)

    Suzuki, Hiroaki; Murase, Michio; Yokomizo, Osamu.

    1997-01-01

    The present invention provides a BWR type reactor facility capable of suppressing the amount of steams generated by the mutual effect of a failed reactor core and coolants upon occurrence of an imaginal accident, and not requiring spacial countermeasures for enhancing the pressure resistance of the container vessel. Namely, a means for supplying cooling water at a temperature not lower by 30degC than the saturated temperature corresponding to the inner pressure of the containing vessel upon occurrence of an accident is disposed to a lower dry well below the pressure vessel. As a result, upon occurrence of such an accident that the reactor core should be melted and flown downward of the pressure vessel, when cooling water at a temperature not lower than the saturated temperature, for example, cooling water at 100degC or higher is supplied to the lower dry well, abrupt generation of steams by the mutual effect of the failed reactor core and cooling water is scarcely caused compared with a case of supplying cooling water at a temperature lower than the saturation temperature by 30degC or more. Accordingly, the amount of steams to be generated can be suppressed, and special countermeasure is no more necessary for enhancing the pressure resistance of the container vessel is no more necessary. (I.S.)

  11. Nuclear reactor

    International Nuclear Information System (INIS)

    Gilroy, J.E.

    1980-01-01

    An improved cover structure for liquid metal cooled fast breeder type reactors is described which it is claimed reduces the temperature differential across the intermediate grid plate of the core cover structure and thereby reduces its subjection to thermal stresses. (UK)

  12. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

    This presentation discusses reactor licensing and includes the legislative basis for licensing, other relevant legislation , the purpose of the Nuclear Safety and Control Act, important regulations, regulatory document, policies, and standards. It also discusses the role of the CNSC, its mandate and safety philosophy

  13. Reactor system

    International Nuclear Information System (INIS)

    Miyano, Hiroshi; Narabayashi, Naoshi.

    1990-01-01

    The represent invention concerns a reactor system with improved water injection means to a pressure vessel of a BWR type reactor. A steam pump is connected to a heat removing system pipeline, a high pressure water injection system pipeline and a low pressure water injection system pipeline for injecting water into the pressure vessel. A pump actuation pipeline is disposed being branched from a main steam pump or a steam relieaf pipeline system, through which steams are supplied to actuate the steam pump and supply cooling water into the pressure vessel thereby cooling the reactor core. The steam pump converts the heat energy into the kinetic energy and elevates the pressure of water to a level higher than the pressure of the steams supplied by way of a pressure-elevating diffuser. Cooling water can be supplied to the pressure vessel by the pressure elevation. This can surely inject cooling water into the pressure vessel upon loss of coolant accident or in a case if reactor scram is necessary, without using an additional power source. (I.N.)

  14. Reactor core

    International Nuclear Information System (INIS)

    Matsuura, Tetsuaki; Nomura, Teiji; Tokunaga, Kensuke; Okuda, Shin-ichi

    1990-01-01

    Fuel assemblies in the portions where the gradient of fast neutron fluxes between two opposing faces of a channel box is great are kept loaded at the outermost peripheral position of the reactor core also in the second operation cycle in the order to prevent interference between a control rod and the channel box due to bending deformation of the channel box. Further, the fuel assemblies in the second row from the outer most periphery in the first operation cycle are also kept loaded at the second row in the second operation cycle. Since the gradient of the fast neutrons in the reactor core is especially great at the outer circumference of the reactor core, the channel box at the outer circumference is bent such that the surface facing to the center of the reactor core is convexed and the channel box in the second row is also bent to the identical direction, the insertion of the control rod is not interfered. Further, if the positions for the fuels at the outermost periphery and the fuels in the second row are not altered in the second operation cycle, the gaps are not reduced to prevent the interference between the control rod and the channel box. (N.H.)

  15. New about research reactors

    International Nuclear Information System (INIS)

    Egorenkov, P.M.

    2001-01-01

    The multi-purpose research reactor MAPLE (Canada) and concept of new reactor MAPLE-CNF as will substitute the known Canadian research reactor NRU are described. New reactor will be used as contributor for investigations into materials, neutron beams and further developments for the CANDU type reactor. The Budapest research reactor (BRR) and its application after the last reconstruction are considered also [ru

  16. Radioactive nuclides in nuclear reactors

    International Nuclear Information System (INIS)

    Akatsu, Eiko

    1982-12-01

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around nuclear reactors. The curricula of the courses contain also chemical subject materials. With reference to the foreign curricula, a plan of educational subject material of chemistry was considered for students of the school in the previous report (JAERI-M 9827), where the first part of the plan, ''Fundamentals of Reactor Chemistry'', was reviewed. This report is a review of the second part of the plan containing fission products chemistry, actinoids elements chemistry and activated reactor materials chemistry. (author)

  17. Oscillating liquid flow ICF Reactor

    International Nuclear Information System (INIS)

    Petzoldt, R.W.

    1990-01-01

    Oscillating liquid flow in a falling molten salt inertial confinement fusion reactor is predicted to rapidly clear driver beam paths of residual liquid droplets. Oscillating flow will also provide adequate neutron and x-ray protection for the reactor structure with a short (2-m) fall distance permitting an 8 Hz repetition rate. A reactor chamber configuration is presented with specific features to clear the entire heavy-ion beam path of splashed molten salt. The structural components, including the structure between beam ports, are shielded. 3 refs., 12 figs

  18. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

    1994-01-01

    In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

  19. "If I only touch her cloak": the Sisters of Charity of St. Joseph in New Orleans hospital, 1834-1860.

    Science.gov (United States)

    Kong, Hyejung Grace; Kim, Ock-Joo

    2015-04-01

    This study is about the Sisters of Charity of St. Joseph in New Orleans' Charity Hospital during the years between 1834 and 1860. The Sisters of Charity of St. Joseph was founded in 1809 by Saint Elizabeth Ann Bailey Seton (first native-born North American canonized in 1975) in Emmitsburg, Maryland. Seton's Sisters of Charity was the first community for religious women to be established in the United States and was later incorporated with the French Daughters of Charity of St. Vincent de Paul in 1850. A call to work in New Orleans' Charity Hospital in the 1830s meant a significant achievement for the Sisters of Charity, since it was the second oldest continuously operating public hospitals in the United States until 2005, bearing the same name over the decades. In 1834, Sister Regina Smith and other sisters were officially called to Charity Hospital, in order to supersede the existing "nurses, attendants, and servants," and take a complete charge of the internal management of Charity Hospital. The existing scholarship on the history of hospitals and Catholic nursing has not integrated the concrete stories of the Sisters of Charity into the broader histories of institutionalized medicine, gender, and religion. Along with a variety of primary sources, this study primarily relies on the Charity Hospital History Folder stored at the Daughters of Charity West Center Province Archives. Located in the "Queen city of the South," Charity Hospital was the center of the southern medical profession and the world's fair of people and diseases. Charity Hospital provided the sisters with a unique situation that religion and medicine became intertwined. The Sisters, as nurses, constructed a new atmosphere of caring for patients and even their families inside and outside the hospital, and built their own separate space within the hospital walls. As hospital managers, the Sisters of Charity were put in complete charge of the hospital, which was never seen in other hospitals. By

  20. Method of reactor operation

    International Nuclear Information System (INIS)

    Nakajima, Takeshi

    1988-01-01

    Purpose: To minimize the power change due to the increase in xenone and power distribution after reaching the rated power in the case of using fresh fuels no requiring conditioning operation thereby starting the nuclear reactor in a short period of time and stably. Method: When control rods are entirely inserted only with a purpose for the compensation of the reactivity in a xenon-unsaturated state such as upon starting of the nuclear reactor, peaking is generated in the lower portion of the reactor core. Therefore, it is necessary to insert control rods for additionally suppressing the peaking in the lower portion of the reactor core to a relatively shallow level. In view of the above, a plurality of control rods are divided into a first control rod group finally inserted in the rated power state and a second control rod group other than the above. Then, the power is once elevated to the rated power level by means of such an intermediate control rod pattern that the ratio of the total extraction amount between the first control rod group and the second control rod group is made constant. Then, the control rods are extracted stepwise while setting the ratio of the total extraction amount constant in accordance with the change of the accumulating amount of xenone, to thereby obtain the purpose. (kamimura, M.)

  1. Lapiku maailma haprus / Joseph S. Nye ; tõlk. Liis Auväärt

    Index Scriptorium Estoniae

    Nye, Joseph S.

    2006-01-01

    Ilmunud ka: Molodjozh Estonii 28. aug. lk. 6-7. Käsitledes globaliseerumist ja Thomas Friedmani lapiku maa metafoori, ütleb autor, et ka 1914. oli maailmamajandus äärmiselt integreeritud, kuid vastastikune majanduslik sõltuvus vähenes järgmise 30 aasta jooksul, muutudes ühtseks alles 70-ndatel. Mõnede arvates mängib Hiina tänapäeval sama rolli, mida mängis Saksamaa XX sajandil. Oht lapikule maale tuleb mitteriiklikelt jõududelt

  2. Usmirenije Severnoi Korei / Joseph S. Nye ; tõlk. Nikolai Zhdanovitsh

    Index Scriptorium Estoniae

    Nye, Joseph S.

    2006-01-01

    USA president George Bush lootis, et tal õnnestub Põhja-Korea tuumaprobleemi lahendada režiimi vahetamisega. Arvestati, et isolatsioon ja sanktsioonid viivad Kim Jong Il'i diktatuuri kukutamiseni. Kuna režiim osutus vastupidavaks, nõustuti kuuepoolsete läbirääkimistega Hiina, Venemaa, Jaapani ja mõlema Koreaga

  3. Väikesed suured mehed / Joseph Nye ; tõlk. Priit Simson

    Index Scriptorium Estoniae

    Nye, Joseph

    2008-01-01

    Autor väljendab mõtet, et ühiskonnad, mis tuginevad nn, kangelasjuhtidele, arendavad kodanikuühiskonda ja sotsiaalset kapitali liiga aeglaselt, et olla võimelised juhtima tänapäeva võrgustunud maailma ning ei tule toime infoühiskonna väljakutsetega

  4. 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

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    Gibbons, J.F.; McLaughlin, D.J.

    1978-01-01

    In the pressure vessel of the water-cooled nuclear reactor there is provided an internal flange on which the one- or two-part core barrel is hanging by means of an external flange. A cylinder is extending from the reactor vessel closure downwards to a seat on the core cupport structure and serves as compression element for the transmission of the clamping load from the closure head to the core barrel (upper guide structure). With the core barrel, subject to tensile stress, between the vessel internal flange and its seat on one hand and the compression of the cylinder resp. hold-down element between the closure head and the seat on the other a very strong, elastic sprung structure is obtained. (DG) [de

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Sasaki, Tomozo.

    1987-01-01

    Purpose: To improve the nuclear reactor availability by enabling to continuously exchange fuels in the natural-slightly enriched uranium region during operation. Constitution: A control rod is withdrawn to the midway of a highly enriched uranium region by means of control rod drives and the highly enriched uranium region is burnt to maintain the nuclear reactor always at a critical state. At the same time, fresh uranium-slightly enriched uranium is continuously supplied gravitationally from a fresh fuel reservoir through fuel reservoir to each of fuel pipes in the natural-slightly enriched uranium region. Then, spent fuels reduced with the reactivity by the burn up are successively taken out from the bottom of each of the fuel pipes through an exit duct and a solenoid valve to the inside of a spent fuel reservoir and the burn up in the natural-slightly enriched uranium region is conducted continuously. (Kawakami, Y.)

  7. Nuclear reactor

    International Nuclear Information System (INIS)

    Sakurai, Mikio; Yamauchi, Koki.

    1983-01-01

    Purpose: To improve the channel stability and the reactor core stability in a spontaneous circulation state of coolants. Constitution: A reactor core stabilizing device comprising a differential pressure automatic ON-OFF valve is disposed between each of a plurality of jet pumps arranged on a pump deck. The stabilizing device comprises a piston exerted with a pressure on the lower side of the pump deck by way of a pipeway and a valve for flowing coolants through the bypass opening disposed to the pump deck by the opening and closure of the valve ON-OFF. In a case where the jet pumps are stopped, since the differential pressure between the upper and the lower sides of the pump deck is removed, the valve lowers gravitationally into an opened state, whereby the coolants flow through the bypass opening to increase the spontaneous circulation amount thereby improve the stability. (Yoshino, Y.)

  8. Nuclear reactor

    International Nuclear Information System (INIS)

    Aleite, W.; Bock, H.W.; Struensee, S.

    1976-01-01

    The invention concerns the use of burnable poisons in a nuclear reactor, especially in PWRs, in order to improve the controllability of the reactor. An unsymmetrical arrangement in the lattice is provided, if necessary also by insertion of special rods for these additions. It is proposed to arrange the burnable poisons in fuel elements taken over from a previous burn-up cycle and to distribute them, going out from the side facing the control rods, over not more than 20% of the lenth of the fuel elements. It seems sufficient, for the burnable poisons to bind an initial reactivity of only 0.1% and to become ineffective after normal operation of 3 to 4 months. (ORU) [de

  9. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Saba, Kazuhisa.

    1979-01-01

    Purpose: To improve the earthquake resistance as well as reduce the size of a container for a nuclear reactor with no adverse effects on the decrease of impact shock to the container and shortening of construction step. Constitution: Reinforcing profile steel materials are welded longitudinally and transversely to the inner surface of a container, and inner steel plates are secured to the above profile steel materials while keeping a gap between the materials and the container. Reactor shielding wall planted to the base concrete of the container is mounted to the pressure vessel, and main steam pipeways secured by the transverse beams and led to the outside of container is connected. This can improve the rigidity earthquake strength and the safetiness against the increase in the inside pressure upon failures of the container. (Yoshino, Y.)

  10. Reactor container

    International Nuclear Information System (INIS)

    Oyamada, Osamu; Furukawa, Hideyasu; Uozumi, Hiroto.

    1979-01-01

    Purpose: To lower the position of an intermediate slab within a reactor container and fitting a heat insulating material to the inner wall of said intermediate slab, whereby a space for a control rod exchanging device and thermal stresses of the inner peripheral wall are lowered. Constitution: In the pedestal at the lower part of a reactor pressure vessel there is formed an intermediate slab at a position lower than diaphragm floor slab of the outer periphery of the pedestal thereby to secure a space for providing automatic exchanging device of a control rod driving device. Futhermore, a heat insulating material is fitted to the inner peripheral wall at the upper side of the intermediate slab part, and the temperature gradient in the wall thickness direction at the time of a piping rupture trouble is made gentle, and thermal stresses at the inner peripheral wall are lowered. (Sekiya, K.)

  11. TA-2 Water Boiler Reactor Decommissioning Project

    International Nuclear Information System (INIS)

    Durbin, M.E.; Montoya, G.M.

    1991-06-01

    This final report addresses the Phase 2 decommissioning of the Water Boiler Reactor, biological shield, other components within the biological shield, and piping pits in the floor of the reactor building. External structures and underground piping associated with the gaseous effluent (stack) line from Technical Area 2 (TA-2) Water Boiler Reactor were removed in 1985--1986 as Phase 1 of reactor decommissioning. The cost of Phase 2 was approximately $623K. The decommissioning operation produced 173 m 3 of low-level solid radioactive waste and 35 m 3 of mixed waste. 15 refs., 25 figs., 3 tabs

  12. Neutronic reactor

    International Nuclear Information System (INIS)

    Lewis, W.R.

    1978-01-01

    Disclosed is a graphite-moderated, water-cooled nuclear reactor including a plurality of rectangular graphite blocks stacked in abutting relationship in layers, alternate layers having axes which are normal to one another, alternate rows of blocks in alternate layers being provided with a channel extending through the blocks, said channeled blocks being provided with concave sides and having smaller vertical dimensions than adjacent blocks in the same layer, there being nuclear fuel in the channels

  13. Nuclear reactors

    International Nuclear Information System (INIS)

    Humphreys, P.; Davidson, D.F.; Thatcher, G.

    1980-01-01

    The cooling system of a liquid metal cooled fast breeder nuclear reactor of the pool kind is described. It has an intermediate heat exchange module comprising a tube-in-shell heat exchanger and an electromagnetic flow coupler in the base region of the module. Primary coolant is flowed through the heat exchanger being driven by electromagnetic interaction with secondary liquid metal coolant flow effected by a mechanical pump. (author)

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    Jungmann, A.

    1975-01-01

    Between a PWR's reactor pressure vessel made of steel and the biological shield made of concrete there is a gap. This gap is filled up with a heat insulation facting the reactor pressure vessel, for example with insulating concrete segments jacketed with sheet steel and with an additional layer. This layer serves for smooth absorption of compressive forces originating in radial direction from the reactor pressure vessel. It consists of cylinder-segment shaped bricks made of on situ concrete, for instance. The bricks have cooling agent ports in one or several rows which run parallel to the wall of the pressure vessel and in alignment with superposed bricks. Between the layer of bricks and the biological shield or rather the heat insulation, there are joints which are filled, however, with injected mortar. That guarantees a smooth series of connected components resistant tom compression. Besides, a slip foil can be set between the heat insulation and the joining joint filled with mortar for the reduction of the friction at thermal expansions. (TK) [de

  15. Reactor building

    International Nuclear Information System (INIS)

    Ebata, Sakae.

    1990-01-01

    At least one valve rack is disposed in a reactor building, on which pipeways to a main closure valve, valves and bypasses of turbines are placed and contained. The valve rack is fixed to the main body of the building or to a base mat. Since the reactor building is designed as class A earthquake-proofness and for maintaining the S 1 function, the valve rack can be fixed to the building main body or to the base mat. With such a constitution, the portions for maintaining the S 1 function are concentrated to the reactor building. As a result, the dispersion of structures of earthquake-proof portion corresponding to the reference earthquake vibration S 1 can be prevented. Accordingly, the conditions for the earthquake-proof design of the turbine building and the turbine/electric generator supporting rack are defined as only the class B earthquake-proof design conditions. In view of the above, the amount of building materials can be saved and the time for construction can be shortened. (I.S.)

  16. Nuclear reactors

    International Nuclear Information System (INIS)

    Yoshioka, Michiko.

    1985-01-01

    Purpose: To obtain an optimum structural arrangement of IRM having a satisfactory responsibility to the inoperable state of a nuclear reactor and capable of detecting the reactor power in an averaged manner. Constitution: As the structural arrangement of IRM, from 6 to 16 even number of IRM are bisected into equial number so as to belong two trip systems respectively, in which all of the detectors are arranged at an equal pitch along a circumference of a circle with a radius rl having the center at the position of the central control rod in one trip system, while one detector is disposed near the central control rod and other detectors are arranged substantially at an equal pitch along the circumference of a circle with a radius r2 having the center at the position for the central control rod in another trip system. Furthermore, the radius r1 and r2 are set such that r1 = 0.3 R, r2 = 0.5 R in the case where there are 6 IRM and r1 = 0.4 R and R2 = 0.8 R where there are eight IRM where R represents the radius of the reactor core. (Kawakami, Y.)

  17. MLR reactor

    International Nuclear Information System (INIS)

    Ryazantsev, E.P.; Egorenkov, P.M.; Nasonov, V.A.; Smimov, A.M.; Taliev, A.V.; Gromov, B.F.; Kousin, V.V.; Lantsov, M.N.; Radchenko, V.P.; Sharapov, V.N.

    1998-01-01

    The Material Testing Loop Reactor (MLR) development was commenced in 1991 with the aim of updating and widening Russia's experimental base to validate the selected directions of further progress of the nuclear power industry in Russia and to enhance its reliability and safety. The MLR reactor is the pool-type one. As coolant it applies light water and as side reflector beryllium. The direction of water circulation in the core is upward. The core comprises 30 FA arranged as hexagonal lattice with the 90-95 mm pitch. The central materials channel and six loop channels are sited in the core. The reflector includes up to 11 loop channels. The reactor power is 100 MW. The average power density of the core is 0.4 MW/I (maximal value 1.0 MW/l). The maximum neutron flux density is 7.10 14 n/cm 2 s in the core (E>0.1 MeV), and 5.10 14 n/cm 2 s in the reflector (E<0.625 eV). In 1995 due to the lack of funding the MLR designing was suspended. (author)

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Shirakawa, Toshihisa.

    1979-01-01

    Purpose: To prevent cladding tube injuries due to thermal expansion of each of the pellets by successively extracting each of the control rods loaded in the reactor core from those having less number of notches, as well as facilitate the handling work for the control rods. Constitution: A recycle flow control device is provided to a circulation pump for forcibly circulating coolants in the reactor container and an operational device is provided for receiving each of the signals concerning number of notches for each of the control rods and flow control depending on the xenon poisoning effect obtained from the signals derived from the in-core instrument system connected to the reactor core. The operational device is connected with a control rod drive for moving each of the control rods up and down and a recycle flow control device. The operational device is set with a pattern for the aimed control rod power and the sequence of extraction. Upon extraction of the control rods, they are extracted successively from those having less notch numbers. (Moriyama, K.)

  19. Reactor container

    International Nuclear Information System (INIS)

    Hidaka, Masataka; Hatamiya, Shigeo; Kawasaki, Terufumi; Fukui, Toru; Suzuki, Hiroaki; Kataoka, Yoshiyuki; Kawabe, Ryuhei; Murase, Michio; Naito, Masanori.

    1990-01-01

    In order to suppress the pressure elevation in a reactor container due to high temperature and high pressure steams jetted out upon pipeway rupture accidents in the reactor container, the steams are introduced to a pressure suppression chamber for condensating them in stored coolants. However, the ability for suppressing the pressure elevation and steam coagulation are deteriorated due to the presence of inactive incondensible gases. Then, there are disposed a vent channel for introducing the steams in a dry well to a pressure suppression chamber in the reactor pressure vessel, a closed space disposed at the position lower than a usual liquid level, a first channel having an inlet in the pressure suppression chamber and an exit in the closed space and a second means connected by way of a backflow checking means for preventing the flow directing to the closed space. The first paths are present by plurality, a portion of which constitutes a syphon. The incondensible gases and the steams are discharged to the dry well at high pressure by using the difference of the water head for a long cooling time after the pipeway rupture accident. Then, safety can be improved without using dynamic equipments as driving source. (N.H.)

  20. Feed water control device in a reactor

    International Nuclear Information System (INIS)

    Okutani, Tetsuro.

    1984-01-01

    Purpose: To prevent substantial fluctuations of the water level in a nuclear reactor and always keep a constant standard level under any operation condition. Constitution: When the causes for fluctuating the reactor water level is resulted, a certain amount of correction signal is added to a level deviation signal for the difference between the reactor standard level and the actual reactor water level to control the flow rate of the feed water pump depending on the addition signal. If reactor scram should occur, for instance, a level correction signal changing stepwise depending on a scram signal is outputted and added to the level deviation signal. As the result, the flow rate of feed water sent into the reactor just after the scram is increased, whereby the lowering in the reactor water level upon scram can be decreased as compared with the case where no such level compensation signal is inputted. (Kamimura, M.)

  1. CERN 50th Anniversary Official Celebration : welcome by CERN Director General Robert Aymar to French President Jacques Chirac, to King of Spain Juan Carlos and to President of the Swiss Confederation Joseph Deiss

    CERN Multimedia

    Patrice Loiez; Michel Blanc

    2004-01-01

    CERN 50th Anniversary Official Celebration : welcome by CERN Director General Robert Aymar to French President Jacques Chirac, to King of Spain Juan Carlos and to President of the Swiss Confederation Joseph Deiss

  2. Imaginário religioso: o simbolismo do herói à luz de Joseph Campbell e Carl Gustav Jung. 2011.

    Directory of Open Access Journals (Sweden)

    Solange Missagia Matos

    2013-03-01

    Full Text Available DISSERTAÇÃO DE MESTRADOMATTOS, Solange Missagia. Imaginário religioso: o simbolismo do herói à luz de Joseph Campbell e Carl Gustav Jung. 2011. 115 folhas. Dissertação (Mestrado – Pontifícia Universidade Católica de Minas Gerais, Programa de Pós-graduação em Ciências da Religião, Belo Horizonte.

  3. Video Release: 47th Vice President of the United States Joseph R. Biden Jr. Speech at HUPO2017 Global Leadership Gala | Office of Cancer Clinical Proteomics Research

    Science.gov (United States)

    The Human Proteome Organization (HUPO) has released a video of the keynote speech given by the 47th Vice President of the United States of America Joseph R. Biden Jr. at the HUPO2017 Global Leadership Gala. Under the gala theme “International Cooperation in the Fight Against Cancer,” Biden recognized cancer as a collection of related diseases, the importance of data sharing and harmonization, and the need for collaboration across scientific disciplines as inflection points in cancer research.

  4. Mountford Joseph Bramley: A pioneering thyroidologist and the first principal of Asia′s oldest medical college

    Directory of Open Access Journals (Sweden)

    Subhankar Chatterjee

    2015-01-01

    Full Text Available Mountford Joseph Bramley was one of the educationists whose sincere efforts are undeniable in the making of modern India. After achieving the Member of the Royal College of Surgeons diploma, he joined the Malta Garrison as a Hospital Assistant and was soon promoted to the rank of Assistant Surgeon of the Rifle Brigade. Following his arrival in India in 1826, he held several important medical posts in the British service. He was one of the early researchers to investigate the role of iodine in the causation of goitre. He was appointed as the first Principal of the Medical College of Bengal, the oldest medical college in Asia, in 1835. Bramley was an educationist from the very core of his heart, and he always wished for the betterment of his students. He died early at the age of 34 years. His legacy as a pioneer in the fields of medical education and endocrinology, specifically thyroidology, has largely been shrouded in a miasma of time.

  5. Educação integral: notas sobre Charles Fourier, Saint Simon e Pierre-Joseph Proudhon

    Directory of Open Access Journals (Sweden)

    José Damiro Moraes

    2015-11-01

    Full Text Available Este artigo procura contribuir para as discussões em torno do conceito histórico de educação integral, tendo em vista que existem algumas lacunas em torno desse tema. Aqui iremos abordar os conceitos de educação integral no pensamento dos intelectuais: Claude-Henri de Rouvroy ou Conde de Saint-Simon (1760-1825, François Marie Charles Fourier (1772-1837 e Pierre-Joseph Proudhon (1809-1865. A pesquisa utiliza as obras dos autores escritas/publicadas no século XIX. A metodologia procura entender a produção intelectual de maneira dialética e dentro do contexto histórico em que foi produzida. Indicamos como conclusões que Proudhon, Saint-Simon e Charles Fourier, consideravam no processo educacional que a parte literária estaria diretamente vinculada com a científica, unindo teoria e prática. Podemos aventar que as contribuições desses pensadores foram importante nas reflexões educacionais e na defesa de uma educação comprometida com a transformação social presente no pensamento socialista e no movimento operário do século XIX e XX.

  6. Lithium carbonate and coenzyme Q10 reduce cell death in a cell model of Machado-Joseph disease

    Directory of Open Access Journals (Sweden)

    C.M. Lopes-Ramos

    Full Text Available Machado-Joseph disease (MJD or spinocerebellar ataxia type 3 (SCA3 is an autosomal dominant neurodegenerative disorder caused by expansion of the polyglutamine domain of the ataxin-3 (ATX3 protein. MJD/SCA3 is the most frequent autosomal dominant ataxia in many countries. The mechanism underlying MJD/SCA3 is thought to be mainly related to protein misfolding and aggregation leading to neuronal dysfunction followed by cell death. Currently, there are no effective treatments for patients with MJD/SCA3. Here, we report on the potential use of lithium carbonate and coenzyme Q10 to reduce cell death caused by the expanded ATX3 in cell culture. Cell viability and apoptosis were evaluated by MTT assay and by flow cytometry after staining with annexin V-FITC/propidium iodide. Treatment with lithium carbonate and coenzyme Q10 led to a significant increase in viability of cells expressing expanded ATX3 (Q84. In addition, we found that the increase in cell viability resulted from a significant reduction in the proportion of apoptotic cells. Furthermore, there was a significant change in the expanded ATX3 monomer/aggregate ratio after lithium carbonate and coenzyme Q10 treatment, with an increase in the monomer fraction and decrease in aggregates. The safety and tolerance of both drugs are well established; thus, our results indicate that lithium carbonate and coenzyme Q10 are good candidates for further in vivo therapeutic trials.

  7. Moral absolutism and the double-effect exception: reflections on Joseph Boyle's Who is entitled to double effect?

    Science.gov (United States)

    Donagan, A

    1991-10-01

    Joseph Boyle raises important questions about the place of the double-effect exception in absolutist moral theories. His own absolutist theory (held by many, but not all, Catholic moralists), which derives from the principles that fundamental human goods may not be intentionally violated, cannot dispense with such exceptions, although he rightly rejects some widely held views about what they are. By contrast, Kantian absolutist theory, which derives from the principle that lawful freedom must not be violated, has a corollary--that it is a duty, where possible, to coerce those who try to violate lawful freedom--which makes superfluous many of the double-effect exceptions Boyle allows. Other implications of the two theories are contrasted. Inter alia, it is argued that, in Boyle's theory, that a violation of a fundamental human good can be viewed as a cost proportionate to a benefit obtained, cannot yield a double-effect exception to the prohibition of intentionally violating that good, because paying a cost cannot be unintentional.

  8. Medical doctors as the captain of a ship: an analysis of medical students' book reports on Joseph Conrad's "Lord Jim".

    Science.gov (United States)

    Hwang, Kun; Lee, Seung Jae; Kim, Seong Yeon; Hwang, Se Won; Kim, Ae Yang

    2014-01-01

    In South Korean ferry disaster in 2014, the captain abandoned the ship with passengers including high school students still aboard. We noticed the resemblance of abandoning the ship with passengers still aboard the ferry (named the Sewol) and the ship Patna, which was full of pilgrims, in Joseph Conrad's novel "Lord Jim." The aim of this study is to see how medical students think about the role of a medical doctor as a captain of a ship by analyzing book reports on Conrad's "Lord Jim." Participants included 49 third-year medical students. Their book reports were analyzed. If placed in the same situation as the character of Jim, 24 students of the 49 respondents answered that they would stay with the passengers, while 18 students indicated they would escape from the ship with the crew. Most of the students thought the role of a doctor in the medical field was like that of a 'captain.' The medical students reported that they wanted to be a doctor who is responsible for his or her patients, highly moral, warm-hearted, honest, and with high self-esteem. In conclusion, we found that "Lord Jim" induced the virtue of 'responsibility' from the medical students. Consequently, "Lord Jim" could be good teaching material for medical humanities.

  9. Integrating Strategic and Operational Decision Making Using Data-Driven Dashboards: The Case of St. Joseph Mercy Oakland Hospital.

    Science.gov (United States)

    Jack Weiner; Balijepally, Venugopal; Tanniru, Mohan

    2015-01-01

    Hospitals have invested and continue to invest heavily in building information systems to support operations at various levels of administration. These systems generate a lot of data but fail to effectively convert these data into actionable information for decision makers. Such ineffectiveness often is attributed to a lack of alignment between strategic planning and information technology (IT) initiatives supporting operational goals. We present a case study that illustrates how the use of digital dashboards at St. Joseph Mercy Oakland (SJMO) Hospital in Pontiac, Michigan, was instrumental in supporting such an alignment. Driven by a focus on key performance indicators (KPIs), dashboard applications also led to other tangible and intangible benefits. An ability to track KPIs over time and against established targets, with drill-down capabilities, allowed leadership to hold staff members accountable for achieving their performance targets. By displaying the dashboards in prominent locations (such as operational unit floors, the physicians' cafeteria, and nursing stations), SJMO ushered in transparency in the planning and monitoring processes. The need to develop KPI metrics and drive data collection efforts became ingrained in the work ethos of people at every level of the organization. Although IT-enabled dashboards have been instrumental in supporting this cultural transformation, the focus of investment was the ability of technology to make collective vision and action the responsibility of all stakeholders.

  10. Neutron source for a reactor

    International Nuclear Information System (INIS)

    Kobayashi, Hiromasa.

    1975-01-01

    Object: To easily increase a start-up power of a reactor without irradiation in other reactors. Structure: A neutron source comprises Cf 252 , a natural antimony rod, a layer of beryllium, and a vessel of neutron source. On upper and lower portion of Cf 252 are arranged natural antimony rods, which are surrounded by the Be layer, the entirety being charged into the vessel. The Cf 252 may emit neutron, has a half life more than a period of operating cycle of the reactor and is less deteriorated even irradiated by radioactive rays while being left within the reactor. The natural antimony rod is radioactivated by neutron from Cf 252 and neutron as reactor power increases to emit γ rays. The Be absorbs γ rays to emit the neutron. The antimony rod is irradiated within the reactor. Further, since the Cf 252 is small in neutron absorption cross section, it is hard to be deteriorated even while being inserted within the reactor. (Kamimura, M.)

  11. Tiede ja tutkijan sosiaalinen vastuu : Joseph Ben-Davidin, Roger Sperryn ja Knut Erik Tranøyn käsitykset tieteestä ja tutkijan sosiaalisesta vastuusta

    OpenAIRE

    Karppela, Lasse

    2006-01-01

    Science and the Scientist's Social Responsibility. Joseph Ben-David's, Roger Sperry's and Knut Erik Tranøy's Views of Science and the Scientist's Social Responsibility The aim of the study was to investigate, whether or not there is any connection between Jewish sociologist Joseph Ben-David's, American neuroscientist Roger Sperry's and Norwegian philosopher Knut Erik Tranøy's views of science and views of the scientist's social responsibility. The sources of information were their writin...

  12. Studies of conceptual spheromak fusion reactors

    International Nuclear Information System (INIS)

    Katsurai, M.; Yamada, M.

    1982-01-01

    Preliminary design studies are carried out for a spheromak fusion reactor. Simplified circuit theory is applied to obtain the characteristic relations among various parameters of the spheromak configuration for an aspect ratio of A >or approx. 1.6. These relations are used to calculate the parameters for the conceptual designs of three types of fusion reactor: (1) the DT reactor with two-component-type operation, (2) the ignited DT reactor, and (3) the ignited catalysed-type DD reactor. With a total wall loading of approx. 4 MW.m -2 , it is found that edge magnetic fields of only approx. 4 T (DT) and approx. 9 T (Cat. DD) are required for ignited reactors of 1 m plasma (minor) radius with output powers in the gigawatt range. An assessment of various schemes of generation, compression and translation of spheromak plasmas is presented. (author)

  13. Brazilian multipurpose reactor

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-01

    The Brazilian Multipurpose Reactor (RMB) Project is an action of the Federal Government, through the Ministry of Science Technology and Innovation (MCTI) and has its execution under the responsibility of the Brazilian National Nuclear Energy Commission (CNEN). Within the CNEN, the project is coordinated by the Research and Development Directorate (DPD) and developed through research units of this board: Institute of Nuclear Energy Research (IPEN); Nuclear Engineering Institute (IEN); Centre for Development of Nuclear Technology (CDTN); Regional Center of Nuclear Sciences (CRCN-NE); and Institute of Radiation Protection and Dosimetry (IRD). The Navy Technological Center in Sao Paulo (CTMSP) and also the participation of other research centers, universities, laboratories and companies in the nuclear sector are important and strategic partnerships. The conceptual design and the safety analysis of the reactor and main facilities, related to nuclear and environmental licensing, are performed by technicians of the research units of DPD / CNEN. The basic design was contracted to engineering companies as INTERTHECNE from Brazil and INVAP from Argentine. The research units from DPD/CNEN are also responsible for the design verification on all engineering documents developed by the contracted companies. The construction and installation should be performed by specific national companies and international partnerships. The Nuclear Reactor RMB will be a open pool type reactor with maximum power of 30 MW and have the OPAL nuclear reactor of 20 MW, built in Australia and designed by INVAP, as reference. The RMB reactor core will have a 5x5 configuration, consisting of 23 elements fuels (EC) of U{sub 3}Si{sub 2} dispersion-type Al having a density of up to 3.5 gU/cm{sup 3} and enrichment of 19.75% by weight of {sup 23{sup 5}}U. Two positions will be available in the core for materials irradiation devices. The main objectives of the RMB Reactor and the other nuclear and radioactive

  14. Brazilian multipurpose reactor

    International Nuclear Information System (INIS)

    2014-01-01

    The Brazilian Multipurpose Reactor (RMB) Project is an action of the Federal Government, through the Ministry of Science Technology and Innovation (MCTI) and has its execution under the responsibility of the Brazilian National Nuclear Energy Commission (CNEN). Within the CNEN, the project is coordinated by the Research and Development Directorate (DPD) and developed through research units of this board: Institute of Nuclear Energy Research (IPEN); Nuclear Engineering Institute (IEN); Centre for Development of Nuclear Technology (CDTN); Regional Center of Nuclear Sciences (CRCN-NE); and Institute of Radiation Protection and Dosimetry (IRD). The Navy Technological Center in Sao Paulo (CTMSP) and also the participation of other research centers, universities, laboratories and companies in the nuclear sector are important and strategic partnerships. The conceptual design and the safety analysis of the reactor and main facilities, related to nuclear and environmental licensing, are performed by technicians of the research units of DPD / CNEN. The basic design was contracted to engineering companies as INTERTHECNE from Brazil and INVAP from Argentine. The research units from DPD/CNEN are also responsible for the design verification on all engineering documents developed by the contracted companies. The construction and installation should be performed by specific national companies and international partnerships. The Nuclear Reactor RMB will be a open pool type reactor with maximum power of 30 MW and have the OPAL nuclear reactor of 20 MW, built in Australia and designed by INVAP, as reference. The RMB reactor core will have a 5x5 configuration, consisting of 23 elements fuels (EC) of U 3 Si 2 dispersion-type Al having a density of up to 3.5 gU/cm 3 and enrichment of 19.75% by weight of 23 5 U. Two positions will be available in the core for materials irradiation devices. The main objectives of the RMB Reactor and the other nuclear and radioactive facilities are

  15. Molten salt reactors: reactor cores

    International Nuclear Information System (INIS)

    1983-01-01

    In this critical analysis of the MSBR I project are examined the problems concerning the reactor core. Advantages of breeding depend essentially upon solutions to technological problems like continuous reprocessing or graphite behavior under neutron irradiation. Graphite deformation, moderator unloading, control rods and core instrumentation require more studies. Neutronics of the core, influence of core geometry and salt composition, fuel evolution, and thermohydraulics are reviewed [fr

  16. Increased SRP reactor power

    International Nuclear Information System (INIS)

    MacAfee, I.M.

    1983-01-01

    Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

  17. Nuclear reactor container

    International Nuclear Information System (INIS)

    Yamaki, Rika; Kawabe, Ryuhei.

    1989-01-01

    A venturi scrubber is connected to a nuclear reactor container. Gases containing radioactive aerosols in the container are introduced into the venturi scrubber in the form of a high speed stream under the pressure of the container. The radioactive aerosols are captured by inertia collision due to the velocity difference between the high speed gas stream and water droplets. In the case of the present invention, since the high pressure of the reactor container generated upon accident is utilized, compressor, etc. is no more required, thereby enabling to reduce the size of the aerosol removing device. Further, since no external power is used, the radioactive aerosols can be removed with no starting failure upon accidents. (T.M.)

  18. 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.)

  19. Nuclear research reactors

    International Nuclear Information System (INIS)

    1985-01-01

    It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.) [pt

  20. U.S. Domestic Reactor Conversion Programs

    International Nuclear Information System (INIS)

    Woolstenhulme, Eric

    2008-01-01

    The Conversion Projects Include: the revision of the facilities safety basis documents and supporting analysis, the fabrication of new LEU fuel, the change-out of the reactor core, and the removal of the used HEU fuel (by INL University Fuels Program or DOE-NE). The major entities involved are: the U.S. Nuclear Regulatory Commission, the University reactor department, the fuel and hardware fabricators, the Spent fuel receipt facilities, the Spent fuel shipping services, and the U.S. Department of Energy and their subcontractors. Three major Reactor Conversion Program milestones have been accomplished since 2006: the conversion of the TRIGA reactor at Texas A and M University Nuclear Science Center, the conversion of the University of Florida Training Reactor, and the conversion of the Purdue University Reactor. Four Reactor Conversion Program milestones yet to be accomplished in 2008 and 2009: the Washington State University Nuclear Radiation Center reactor, the Oregon State University TRIGA Reactor, the University of Wisconsin Nuclear Reactor, and the Neutron Radiography Reactor Facility. NNSA is committed to doing things cheaper, better, smarter, safer through a 'Lessons Learned' process. The conversion team assessed each major activity grouping: Project Initiation, Conversion Proposal Development, Fuel Fabrication and Hardware, Core Conversion, and Spent Nuclear Fuel Removal. Issues were identified and recommendations were given

  1. 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

  2. Assessment of torsatrons as reactors

    International Nuclear Information System (INIS)

    Lyon, J.F.; Painter, S.L.

    1992-12-01

    Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors because stellarators have no dangerous disruptions and no need for continuous current drive or power recirculated to the plasma, both easing the first wall, blanket, and shield design; less severe constraints on the plasma parameters and profiles; and better access for maintenance. This study shows that a reactor based on the torsatron configuration (a stellarator variant) could also have up to double the mass utilization efficiency (MUE) and a significantly lower cost of electricity (COE) than a conventional tokamak reactor (ARIES-I) for a range of assumptions. Torsatron reactors can have much smaller coil systems than tokamak reactors because the coils are closer to the plasma and they have a smaller cross section (higher average current density because of the lower magnetic field). The reactor optimization approach and the costing and component models are those used in the current stage of the ARIES-I tokamak reactor study. Typical reactor parameters for a 1-GW(e) Compact Torsatron reactor example are major radius R 0 = 6.6-8.8 m, on-axis magnetic field B 0 = 4.8-7.5 T, B max (on coils) = 16 T, MUE 140-210 kW(e)/tonne, and COE (in constant 1990 dollars) = 67-79 mill/kW(e)h. The results are relatively sensitive to assumptions on the level of confinement improvement and the blanket thickness under the inboard half of the helical windings but relatively insensitive to other assumptions

  3. Nuclear reactor

    International Nuclear Information System (INIS)

    Jolly, R.

    1979-01-01

    The support grid for the fuel rods of a liquid metal cooled fast breeder reactor has a regular hexagonal contour and contains a large number of unit cells arranged honeycomb fashion. The totality of these cells make up a hexagonal shape. The grid contains a number of strips of material, and there is a window in each of three sidewalls staggered by one sidewall. The other sidewalls have embossed protrusions, thus generating a guide lining or guide bead. The windows reduce the rigidity of the areas in the middle between the ends of the cells. (DG) [de

  4. Nuclear reactor

    International Nuclear Information System (INIS)

    Anthony, A.J.; Gruber, E.A.

    1979-01-01

    A nuclear reactor with control rods in channels between fuel assemblies wherein the fuel assemblies incorporate guide rods which protrude outwardly into the control rod channels to prevent the control rods from engaging the fuel elements. The guide rods also extend back into the fuel assembly such that they are relatively rigid members. The guide rods are tied to the fuel assembly end or support plates and serve as structural members which are supported independently of the fuel element. Fuel element spacing and support means may be attached to the guide rods. 9 claims

  5. US DOE Idaho national laboratory reactor decommissioning

    International Nuclear Information System (INIS)

    Szilagyi, Andrew

    2012-01-01

    The United States Department of Energy (DOE) primary contractor, CH2M-WG Idaho was awarded the cleanup and deactivation and decommissioning contract in May 2005 for the Idaho National Lab (INL). The scope of this work included dispositioning over 200 Facilities and 3 Reactors Complexes (Engineering Test Reactor (ETR), Materials Test Reactor (MTR) and Power Burst Facility (PBF) Reactor). Two additional reactors were added to the scope of the contract during the period of performance. The Zero Power Physics Reactor (ZPPR) disposition was added under a separate subcontractor with the INL lab contractor and the Experimental Breeder Reactor II (EBR-II) disposition was added through American Recovery and Reinvestment Act (ARRA) Funding. All of the reactors have been removed and disposed of with the exception of EBR-II which is scheduled for disposition approximately March of 2012. A brief synopsis of the 5 reactors is provided. For the purpose of this paper the ZPPR reactor due to its unique design as compared to the other four reactors, and the fact that is was relatively lightly contaminated and irradiated will not be discussed with the other four reactors. The ZPPR reactor was readily accessible and was a relatively non-complex removal as compared to the other reactors. Additionally the EBR-II reactor is currently undergoing D and D and will have limited mention in this paper. Prior to decommissioning the reactors, a risk based closure model was applied. This model exercised through the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), Non-Time Critical Removal Action (NTCRA) Process which evaluated several options. The options included; No further action - maintain as is, long term stewardship and monitoring (mothball), entombment in place and reactor removal. Prior to commencing full scale D and D, hazardous constituents were removed including cadmium, beryllium, sodium (passivated and elemental), PCB oils and electrical components, lead

  6. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1979-01-01

    In a nuclear reactor (e.g. one having coolant down-flow through a core to a hearth below) thermal insulation (e.g. of a floor of the hearth) comprises a layer of bricks and a layer of tiles thereon, with smaller clearances between the tiles than between the bricks but with the bricks being of reduced cross-section immediately adjacent the tiles so as to be surrounded by interconnected passages, of relatively large dimensions, constituting a continuous chamber extending behind the layer of tiles. By this arrangement, lateral coolant flow in the inter-brick clearances is much reduced. The reactor core is preferably formed of hexagonal columns, supported on diamond-shaped plates each supported on a pillar resting on one of the hearth-floor tiles. Each plate has an internal duct, four upper channels connecting the duct with coolant ducts in four core columns supported by the plate, and lower channels connecting the duct to a downwardly-open recess common to three plates, grouped to form a hexagon, at their mutually-adjacent corners. This provides mixing, and temperature-averaging, of coolant from twelve columns

  7. Reactor container

    International Nuclear Information System (INIS)

    Oikawa, Hirohide; Otonari, Jun-ichiro; Tozaki, Yuka.

    1993-01-01

    Partition walls are disposed between a reactor pressure vessel and a suppression chamber to separate a dry well to an upper portion and a lower portion. A communication pipe is disposed to the partition walls. One end of the communication pipe is opened in an upper portion of the dry well at a position higher than a hole disposed to a bent tube of the suppression chamber. When coolants overflow from a depressurization valve by an erroneous operation of an emergency reactor core cooling device, the coolants accumulate in the upper portion of the dry well. When the pipeline is ruptured at the upper portion of the pressure vessel, only the inside of the pressure vessel and the upper portion of the dry well are submerged in water. In this case, the water level of the coolants does not elevate to the opening of the commuication pipe but they flow into the suppression chamber from the hole disposed to the bent tube. Since the coolants do not flow out to the lower portion of the dry well, important equipments such as control rod drives disposed at the lower portion of the dry wall can be prevented from submerging in water. (I.N.)

  8. Reactor monitor

    International Nuclear Information System (INIS)

    Takada, Tamotsu.

    1992-01-01

    The device of the present invention monitors a reactor so that each of the operations for the relocation of fuel assemblies and the withdrawal and the insertion of control rods upon exchange of fuel assemblies and control rods in the reactor. That is, when an operator conducts relocating operation by way of a fuel assembly operation section, the device of the present invention judges whether the operation indication is adequate or not, based on the information of control rod arrangement in a control rod memory section. When the operation indication is wrong, a stop signal is sent to a fuel assembly relocating device. Further, when the operator conducts control rod operation by way of a control rod operation section, the device of the present invention judges in the control rod withdrawal judging section, as to whether the operation indication given by the operator is adequate or not by comparing it with fuel assembly arrangement information. When the operation indication is wrong, a stop signal is sent to control rod drives. With such procedures, increase of nuclear heating upon occurrence of erroneous operation can be prevented. (I.S.)

  9. Nuclear reactors

    International Nuclear Information System (INIS)

    Matheson, J.E.

    1983-01-01

    A nuclear reactor has an upper and a lower grid plate. Protrusions project from the upper grid plate. Fuel assemblies having end fittings fit between the grid plates. An arrangement is provided for accepting axial forces generated during the operation of the nuclear reactor by the flow of the cooling medium and thermal expansion and irradiation-induced growth of the fuel assembly, which comprises rods. Each fuel assembly rests on the lower grid plate and its upper end is elastically supported against the upper grid plate by the above-mentioned arrangement. The arrangement comprises four (for example) torsion springs each having a torsion tube and a torsion bar nested within the torsion tube and connected at one end thereto. The other end of the torsion bar is connected to an associated one of four lever arms. The torsion tube is rigidly connected to the other end fitting and the springs are disposed such that the lever arms are biassed against the protrusions. (author)

  10. First preliminary design of an experimental fusion reactor

    International Nuclear Information System (INIS)

    1977-09-01

    A preliminary design of a tokamak experimental fusion reactor to be built in the near future is under way. The goals of the reactor are to achieve reactor-level plasma conditions for a sufficiently long operation period and to obtain design, construction and operational experience for the main components of full-scale power reactors. This design covers overall reactor system including plasma characteristics, reactor structure, blanket neutronics, shielding, superconducting magnets, neutral beam injector, electric power supply system, fuel circulating system, reactor cooling system, tritium recovery system and maintenance scheme. The main design parameters are as follows: the reactor fusion power 100 MW, torus radius 6.75 m, plasma radius 1.5 m, first wall radius 1.75 m, toroidal magnet field on axis 6 T, blanket fertile material Li 2 O, coolant He, structural material 316SS and tritium breeding ratio 0.9. (auth.)

  11. Reactor core fuel management

    International Nuclear Information System (INIS)

    Silvennoinen, P.

    1976-01-01

    The subject is covered in chapters, entitled: concepts of reactor physics; neutron diffusion; core heat transfer; reactivity; reactor operation; variables of core management; computer code modules; alternative reactor concepts; methods of optimization; general system aspects. (U.K.)

  12. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T [Huntington Beach, CA; Sahimi, Muhammad [Altadena, CA; Fayyaz-Najafi, Babak [Richmond, CA; Harale, Aadesh [Los Angeles, CA; Park, Byoung-Gi [Yeosu, KR; Liu, Paul K. T. [Lafayette Hill, PA

    2011-03-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  13. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-11-01

    This single page document is the November 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the production reactor.

  14. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-01

    This single page document is the October 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  15. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-15

    This single page document is the October 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  16. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-09-15

    This single page document is the September 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  17. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-15

    This single page document is the December 16, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

  18. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-01

    This single page document is the December 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

  19. Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

    International Nuclear Information System (INIS)

    Henry, A.F.

    1980-01-01

    Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

  20. What occurred in the reactors

    International Nuclear Information System (INIS)

    Kudo, Kazuhiko

    2013-01-01

    Described is what occurred in the reactors of Fukushima Daiichi Nuclear Power Plant at the Tohoku earthquake and tsunami (Mar. 11, 2011) from the aspect of engineering science. The tsunami attacked the Plant 1 hr after the quake. The Plant had reactors in buildings no.1-4 at 10 m height from the normal sea level which was flooded by 1.5-5.5 m high wave. All reactors in no.1-6 in the Plant were the boiling water type, and their core nuclear reactions were stopped within 3 sec due to the first quake by control rods inserted automatically. Reactors in no.1-5 lost their external AC power sources by the breakdown and subsequent submergence (no.1-4) of various equipments and in no.1, 2 and 4, the secondary DC power was then lost by the battery death. Although the isolation condenser started to cool the reactor in no.1 after DC cut, its valve was then kept closed to heat up the reactor, leading to the reaction of heated Zr in the fuel tube and water to yield H 2 which was accumulated in the building: the cause of hydrogen explosion on 12th. The reactor in no.2 had the reactor core isolation cooling system (RCIC) which operated normally for few hrs, then probably stopped to heat up the reactor, resulting in meltdown of the core but no explosion occurred because of the opened door of the blowout panel on the wall by the blast of no.1 explosion. The reactor in no.3 had RCIC and high pressure coolant injection system, but their works stopped to result in the core damage and H 2 accumulation leading to the explosion on 14th. The reactor in no.4 had not been operated because of its periodical annual examination, but was explored on 15th, of which cause was thought to be due to backward flow of H 2 from no.3. Finally, the author discusses about this accident from the industrial aspect of the design of safety level (defense in depth) on international views, and problems and tasks given. (T.T.)

  1. Risk assessment for the reintroduction of anadromous salmonids upstream of Chief Joseph and Grand Coulee Dams, Northeastern Washington

    Science.gov (United States)

    Hardiman, Jill M.; Breyta, Rachel B.; Haskell, Craig A.; Ostberg, Carl O.; Hatten, James R.; Connolly, Patrick J.

    2017-09-12

    The Upper Columbia United Tribes (UCUT; Spokane, Colville, Kootenai, Coeur d’Alene, and Kalispel Tribes) and Washington Department of Fish and Wildlife want to reintroduce anadromous salmonids to their historical range to restore ecosystem function and lost cultural and spiritual relationships in the upper Columbia River, northeastern Washington. The UCUT contracted with the U.S. Geological Survey to assess risks to resident taxa (existing fish populations in the reintroduction area upstream of Chief Joseph and Grand Coulee Dams) and reintroduced salmon associated with reintroduction. We developed a risk assessment framework for reintroduction of anadromous salmonids upstream of Chief Joseph and Grand Coulee Dams. To accomplish this goal, we applied strategies identified in previous risk assessment frameworks for reintroduction. The risk assessment is an initial step towards an anadromous reintroduction strategy. An initial list of potential donor sources for reintroduction species was developed from previous published sources for Chinook Salmon (Oncorhynchus tshawytscha) donors in the Transboundary Reach of the Columbia River, British Columbia; an ecological risk assessment of upper Columbia River hatchery programs on non-target taxa of concern; and a review of existing hatchery programsDuring two workshops, we further identified and ranked potential donor sources of anadromous Redband Trout (steelhead; O. mykiss), Chinook Salmon, Sockeye Salmon (O. nerka), and Coho Salmon (O. kisutch). We also identified resident fish populations of interest and their primary habitat, location, status, and pathogen concerns to determine the potential risks of reintroduction. Species were deemed of interest based on resource management and potential interactions (that is, genetics, competition, and predation) with introduced species. We developed tables of potential donors by species and characterized potential sources (hatchery and natural origins), populations (individual runs

  2. Double-blind crossover trial of trimethoprim-sulfamethoxazole in spinocerebellar ataxia type 3/Machado-Joseph disease.

    Science.gov (United States)

    Schulte, T; Mattern, R; Berger, K; Szymanski, S; Klotz, P; Kraus, P H; Przuntek, H; Schöls, L

    2001-09-01

    To evaluate the efficiency of a combination of trimethoprim and sulfamethoxazole in patients with spinocerebellar ataxia type 3/Machado-Joseph disease (SCA3/MJD). Placebo-controlled, double-blind crossover trial in 22 patients with genetically confirmed SCA3/MJD. Study phases of 6 months were separated by a washout period of 4 weeks. Dosages were a combination of trimethoprim, 160 mg, and sulfamethoxazole, 800 mg, twice daily for 2 weeks, followed by a combination of trimethoprim, 80 mg, and sulfamethoxazole, 400 mg, twice daily for 5.5 months. Outpatient department of the Neurological Clinic, Ruhr-University, Bochum, Germany. Ataxia ranking scale, self-assessment score, static posturography, and results of motor performance testing. Effects on the visual system were studied using the achromatic Vision Contrast Test System and the Farnsworth-Munsell 100-hue test for color discrimination. Physical and mental health were documented using the Medical Outcomes Study 36-Item Short-Form Health Survey. Subgroup analyses assessed the influence of age, sex, age at onset, duration of the disease, phenotype, and CAG repeat length on test performance. Twenty of 22 patients completed the study. Dropouts were due to a rash (placebo phase) and an attempted suicide in a family conflict. Trimethoprim-sulfamethoxazole therapy had no significant effect in SCA3/MJD patients in the short-term analysis (2 weeks) or in the long-term interval (6 months). In contrast to previous reports that studied smaller groups of patients, treatment with trimethoprim-sulfamethoxazole did not improve the diverse and complex movement disorders caused by SCA3/MJD. Trimethoprim-sulfamethoxazole had no effect on the visual system and cannot be recommended as a continuous treatment for SCA3/MJD patients.

  3. The CEA research reactors

    International Nuclear Information System (INIS)

    Schwartz, J.P.

    1993-01-01

    Two main research reactors, specifically designed, PEGASE reactor and Laue-Langevin high flux reactor, are presented. The PEGASE reactor was designed at the end of the 50s for the study of the gas cooled reactor fuel element behaviour under irradiation; the HFR reactor, was designed in the late 60s to serve as a high yield and high level neutron source. Historical backgrounds, core and fuel characteristics and design, flux characteristics, etc., are presented. 5 figs

  4. 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.

  5. Inherent safety characteristics of innovative reactors

    International Nuclear Information System (INIS)

    Heil, J.A.

    1995-11-01

    The added safety value of innovative or third generation reactor designs has been evaluated in order to determine the most suitable candidate for Dutch government funded research and development support. To this end, four innovative reactor concepts, viz. PIUS (Process Inherent Ultimate Safety), PRISM (Power Reactor Innovative Small), HTR-M (High Temperature Reactor Module) and MHTGR (Modular High Temperature Gas-cooled Reactor), have been studied and their passive and inherent safety characteristics have been outlined. Also the outlook for further technological and industrial development has been considered. The results of the study confirm the perspective of the innovative reactors for reduced dependence on active safety provisions and for a further reduced vulnerability to technical failures and human errors. The accident responses to generic accident initiators, viz. reactivity and cooling accidents, and also to reactor specific accidents show that neither active safety systems nor short term operator actions are required for maintaining the reactor core in a controlled and coolable condition. Whether this gives rise to a higher total safety of the innovative reactor designs, compared to evolutionary or advanced reactors, cannot be concluded. Supplementary experimental and analytical analyses of reactor specific accidents are required to be able to assess the safety of these innovative designs in a more quantitative manner. It is believed that the safety case of innovative reactors, which are less dependent on active safety systems, can be communicated with the general public in a more transparent way. Considering the perspective for further technological and industrial development it is not expected that any of the considered innovative reactor concepts will become commercially available within the next one to two decades. However, they could be made available earlier if they would receive sufficient financial backing. Considering the added safety perspectives

  6. Tokamak engineering test reactor

    International Nuclear Information System (INIS)

    Conn, R.W.; Jassby, D.L.

    1975-07-01

    The design criteria for a tokamak engineering test reactor can be met by operating in the two-component mode with reacting ion beams, together with a new blanket-shield design based on internal neutron spectrum shaping. A conceptual reactor design achieving a neutron wall loading of about 1 MW/m 2 is presented. The tokamak has a major radius of 3.05 m, the plasma cross-section is noncircular with a 2:1 elongation, and the plasma radius in the midplane is 55 cm. The total wall area is 149 m 2 . The plasma conditions are T/sub e/ approximately T/sub i/ approximately 5 keV, and ntau approximately 8 x 10 12 cm -3 s. The plasma temperature is maintained by injection of 177 MW of 200-keV neutral deuterium beams; the resulting deuterons undergo fusion reactions with the triton-target ions. The D-shaped toroidal field coils are extended out to large major radius (7.0 m), so that the blanket-shield test modules on the outer portion of the torus can be easily removed. The TF coils are superconducting, using a cryogenically stable TiNb design that permits a field at the coil of 80 kG and an axial field of 38 kG. The blanket-shield design for the inner portion of the torus nearest the machine center line utilizes a neutron spectral shifter so that the first structural wall behind the spectral shifter zone can withstand radiation damage for the reactor lifetime. The energy attenuation in this inner blanket is 8 x 10 -6 . If necessary, a tritium breeding ratio of 0.8 can be achieved using liquid lithium cooling in the []outer blanket only. The overall power consumption of the reactor is about 340 MW(e). A neutron wall loading greater than 1 MW/m 2 can be achieved by increasing the maximum magnetic field or the plasma elongation. (auth)

  7. Application of autoregressive methods and Lyapunov coefficients for instability studies of nuclear reactors; Aplicação de métodos autorregressivos e coeficientes de Lyapunov para estudos de instabilidades em reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Aruquipa Coloma, Wilmer

    2017-07-01

    Nuclear reactors are susceptible to instability, causing oscillations in reactor power in specific working regions characterized by determined values of power and coolant mass flow. During reactor startup, there is a greater probability that these regions of instability will be present; another reason may be due to transient processes in some reactor parameters. The analysis of the temporal evolution of the power reveals a stable or unstable process after the disturbance in a light water reactor of type BWR (Boiling Water Reactor). In this work, the instability problem was approached in two ways. The first form is based on the ARMA (Autoregressive Moving Average models) model. This model was used to calculate the Decay Ratio (DR) and natural frequency (NF) of the oscillations, parameters that indicate if the one power signal is stable or not. In this sense, the DRARMA code was developed. In the second form, the problems of instability were analyzed using the classical concepts of non-linear systems, such as Lyapunov exponents, phase space and attractors. The Lyapunov exponents quantify the exponential divergence of the trajectories initially close to the phase space and estimate the amount of chaos in a system; the phase space and the attractors describe the dynamic behavior of the system. The main aim of the instability phenomena studies in nuclear reactors is to try to identify points or regions of operation that can lead to power oscillations conditions. The two approaches were applied to two sets of signals. The first set comes from signals of instability events of the commercial Forsmark reactors 1 and 2 and were used to validate the DRARMA code. The second set was obtained from the simulation of transient events of the Peach Bottom reactor; for the simulation, the PARCS and RELAP5 codes were used for the neutronic/thermal hydraulic coupling calculation. For all analyzes made in this work, the Matlab software was used due to its ease of programming and

  8. Fast reactors: the future of nuclear energy

    International Nuclear Information System (INIS)

    Carvalho, H.G. de.

    1988-08-01

    The main problems to be solved for FBR type reactors become viable economically, presenting the research programs of Europe, United States of America, Japan and Brazil are described. The cooperations between interested countries for improving FBR type reactors, and the financial and human resources necessaries for the development of programs, are evaluated. The fuel cycle is also analysed. (M.C.K.) [pt

  9. 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.)

  10. Nuclear reactor recyclation device

    International Nuclear Information System (INIS)

    Takigawa, Yukio; Chuma, Kazuto

    1987-01-01

    Purpose: To prevent the unevenness for the coolant flow rate even when abnormality occurs to one of recycling pumps. Constitution: A plurality of jet pumps disposed at an interval around the reactor core are divided circumferentially into two sets, and a pipeway is disposed to the outside of each pair including recycling pumps corresponding to each of the sets. The pipeway is connected to the recycling inlet of the jet pump by way of a manifold. The discharge portion of the recycling pumps of the loop pipeway are connected with each other by way of communication pipes, and a normally closed valve is disposed to the communication pipe and the normally closed valve of the communication pipe is opened upon detecting abnormality for one of the recycling pumps. Thus, if either one of the pair of recycling pumps shows abnormal state, coolants flows from the other of pipeway to the outside of the loop pipeway and coolants are supplied from all the jet pumps to the reactor core portion and, accordingly, the not-uniform flow rate can be prevented to eliminate undesired effect on the reactor core. (Kamimura, M.)

  11. Feasibility study of application of Prompt Gamma Neutron Activation Analysis (PGNAA) method in TRIGA IPR-R1 reactor; Estudo da viabilidade de aplicação do método Prompt Gamma Neutron Activation Analysis (PGNAA) no reator TRIGA IPR-R1

    Energy Technology Data Exchange (ETDEWEB)

    Guerra, Bruno Teixeira

    2016-07-01

    The TRIGA Mark I IPR-R1 research reactor is located at Nuclear Technology Development Centre (CDTN), Brazilian Commission for Nuclear Energy (CNEN), in Belo Horizonte, Brazil. The reactor operates at 100 kW but the core configuration allows the increasing of the power up to 250 kW. It has been applied research, training and radioisotopes production. The establishment of the Prompt Gamma Neutron Activation Analysis (PGNAA) method at the TRIGA IPR-R1 reactor will significantly increase the types of matrices analysed as well as the number of chemical elements. Additionally it will complement the neutron activation analysis. This work presents a proposed design of a PGNAA facility to be installed at the TRIGA IPR-R1. The proposed design is based on a tube as a neutron guide from the reactor core, inside the reactor pool, 6 m below the room’s level where shall be located the rack containing the set sample/detector/shielding. Thus, the aim of this study is to verify the feasibility to establish the PGNAA method in IPR-R1 through theoretical study applying the Monte Carlo code. The feasibility of establishing the PGAA method at the IPR-R1 installations was evaluated through of the calculations of neutron flux, radioactive capture reaction rates and detection limits for some isotopes. According to the obtained results, it can be concluded that is possible to establish the PGAA method at the IPR-R1 reactor, even with some restrictions in its theoretical design calculated by MCNP. (author)

  12. General aspects of CAREM-25 reactor

    International Nuclear Information System (INIS)

    Delmastro, Dario F.; Gomez, Silvia; Ishida, Viviana; Mazzi, Ruben; Santecchia, Alberto; Gomez de Soler, Susana M.

    2000-01-01

    CAREM project consists on the development and design of an advanced nuclear power plant. In order to verify its innovative features the construction of a prototype is planned. In this paper the main technical characteristics of CAREM-25 prototype reactor are presented. This is a very low power innovative reactor (100 M Wth) conceived with new generation design solutions. Based on an indirect cycle integrated light water reactor using enriched uranium, CAREM has some distinctive features that greatly simplify the reactor and also contribute to a high level of safety: -) Integrated primary system; -) Primary system cooling by natural convection; -) Self pressurization; -) and Passive safety systems. (author)

  13. Tank type LMFBR type reactors

    International Nuclear Information System (INIS)

    Shimizu, Hiroshi

    1985-01-01

    Purpose: To detect the abnormality in the suspended body or reactor core supporting structures thereby improve the safety and reliability of tank type LMFBR reactors. Constitution: Upon inspection during reactor operation period, the top end of the gripper sensing rod of a fuel exchanger is abutted against a supporting bed and the position of the reactor core supporting structures from the roof slab is measured by a stroke measuring device. Then, the sensing rod is pulled upwardly to abut against the arm portion and the position is measured by the stroke measuring device. The measuring procedures are carried out for all of the sensing rods and the measured values are compared with a previously determined value at the initial stage of the reactor operation. As a result, it is possible to detect excess distortions and abnormal deformation in the suspended body or reactor core supporting structures. Furthermore, integrity of the suspended body against thermal stresses can be secured by always measuring the coolant liquid level by the level measuring sensor. (Kamimura, M.)

  14. Reactor safety

    International Nuclear Information System (INIS)

    Meneley, D.A.

    The people of Ontario have begun to receive the benefits of a low cost, assured supply of electrical energy from CANDU nuclear stations. This indigenous energy source also has excellent safety characteristics. Safety has been one of the central themes of the CANDU development program from its very beginning. A great deal of work has been done to establish that public risks are small. However, safety design criteria are now undergoing extensive review, with a real prospect of more stringent requirements being applied in the future. Considering the newness of the technology it is not surprising that a consensus does not yet exist; this makes it imperative to discuss the issues. It is time to examine the policies and practice of reactor safety management in Canada to decide whether or not further restrictions are justified in the light of current knowledge

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Schabert, H.P.; Weber, R.; Bauer, A.

    1975-01-01

    The refuelling of a PWR power reactor of about 1,200 MWe is performed by a transport pipe in the containment leading from an external to an internal fuel pit. A wagon to transport the fuel elements can go from a vertical loading position to an also vertical deloading position in the inner fuel pit via guide rollers. The necessary horizontal movement is effected by means of a cable line through the transport pipe which is inclined at least 10 0 . Gravity thus helps in the movement to the deloading position. The cable line with winch is fastened outside the containment. Swivelling devices tip the wagon from the horizontal to the vertical position or vice versa. Loading and deloading are done laterally. (TK/LH) [de

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Schweiger, F.; Glahe, E.

    1976-01-01

    In a nuclear reactor of the kind which is charged with spherical reaction elements and in which control rods are arranged to be thrust directly into the charge, each control rod has at least one screw thread on its external surface so that as the rod is thrust into the charge it is caused to rotate and thus make penetration easier. The length of each control rod may have two distinct portions, a latter portion which carries a screw thread and a lead-in portion which is shorter than the latter portion and which may carry a thread of greater pitch than that on the latter portion or may have a number of axially extending ribs instead of a thread

  17. Reactor container

    International Nuclear Information System (INIS)

    Furukawa, Hideyasu; Oyamada, Osamu; Uozumi, Hiroto.

    1976-01-01

    Purpose: To provide a container for a reactor provided with a pressure suppressing chamber pool which can prevent bubble vibrating load, particularly negative pressure generated at the time of starting to release exhaust from a main steam escape-safety valve from being transmitted to a lower liner plate of the container. Constitution: This arrangement is characterized in that a safety valve exhaust pool for main steam escape, in which a pressure suppressing chamber pool is separated and intercepted from pool water in the pressure suppressing chamber pool, a safety valve exhaust pipe is open into said safety valve exhaust pool, and an isolator member, which isolates the bottom liner plate in the pressure suppressing chamber pool from the pool water, is disposed on the bottom of the safety valve exhaust pool. (Nakamura, S.)

  18. Research reactors; Les piles de recherche

    Energy Technology Data Exchange (ETDEWEB)

    Kowarski, L [Commissariat a l' Energie Atomique, Paris (France). Centre d' Etudes Nucleaires; [Organisation europeenne pour la Recherche Nucleaire, Geneve (Switzerland)

    1955-07-01

    type of reactors: low power reactors, graphite and natural uranium reactors, heavy water and natural uranium reactors (with water, gas or heavy water as coolant), heavy water and enriched uranium reactors, 'kettle' type reactors, pool type reactors and high power reactors. Finally, additional factors are considered as the correlation of the reactor type with the research program, safety considerations, size of the construction and economical considerations. (M.P.)

  19. Research reactors; Les piles de recherche

    Energy Technology Data Exchange (ETDEWEB)

    Kowarski, L. [Commissariat a l' Energie Atomique, Paris (France). Centre d' Etudes Nucleaires]|[Organisation europeenne pour la Recherche Nucleaire, Geneve (Switzerland)

    1955-07-01

    type of reactors: low power reactors, graphite and natural uranium reactors, heavy water and natural uranium reactors (with water, gas or heavy water as coolant), heavy water and enriched uranium reactors, 'kettle' type reactors, pool type reactors and high power reactors. Finally, additional factors are considered as the correlation of the reactor type with the research program, safety considerations, size of the construction and economical considerations. (M.P.)

  20. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    In the system described the fuel elements are arranged vertically in groups and are supported in such a manner as to tend to tilt them towards the center of the respective group, the fuel elements being urged laterally into abutment with one another. The elements have interlocking bearing pads, whereby lateral movement of adjacent elements is resisted; this improves the stability of the reactor core during refuelling operations. Fuel elements may comprise clusters of parallel fuel pins enclosed in a wrapper of hexagonal cross section, with bearing pads in the form of spline-like ribs located on each side of the wrapper and extending parallel to the longitudinal axis of the fuel element, being interlockable with ribs on pads of adjacent fuel elements. The arrangement is applicable to a reactor core in which fuel elements and control rod guide tubes are arranged in modules each of which comprises a cluster of at least three fuel elements, one of which is rigidly supported whilst the others are resiliently tilted towards the center of the cluster so as to lean on the rigidly supported element. It is also applicable to modules comprising a cluster of six fuel elements, each resiliently tilted towards a central void to form a circular arch. The modules may include additional fuel elements located outside the clusters and also resiliently tilted towards the central voids, the latter being used to accommodate control rod guide tubes. The need for separate structural members to act as leaning posts is thus avoided. Such structural members are liable to irradiation embrittlement, that could lead to core failure. (U.K.)

  1. Control of WWER-440 nuclear reactor

    International Nuclear Information System (INIS)

    Wagner, K.; Drab, F.; Grof, V.

    1978-01-01

    The V-1 reactor control systems are described. The data acquisition and processing system fulfils four main functions, ie., reactor start-up and power increase to 10% of the rated power, automatic power control within 3% and 110% of the rated power, reactivity compensation, and reactor protection. The automatic control system ensures constant steam pressure maintained with an accuracy of +-0.05 MPa. Reactivity compensation and spatial power distribution is mainly safeguarded by boric acid control. The V-1 reactor protection system has four levels of accident protection depending on the gravity of the failure. The philosophy of automation of the V-1 reactor control and protection system is based on autonomous automatic controlers and on the direct control of the individual sets and technological equipment. In conclusion, development trends are briefly outlined of control and protection systems of light water reactor power plants. (Z.M.)

  2. Detection method for nuclear reactor material

    International Nuclear Information System (INIS)

    Isobe, Yusuke; Hashimoto, Motoyuki.

    1995-01-01

    A fine state of a test piece taken out of a reactor core is analyzed upon periodical inspection, and a new test piece previously reproducing the state described above at the outside of the reactor is disposed to the reactor core upon completion of the periodical inspection. Further, a fine state of the material at a time preceding to the operation time at a certain periodical inspection is forecast, and a test piece reproducing the state at the outside of the reactor is disposed to the reactor core upon the completion of the periodical inspection. Since a test piece previously reproducing the change of the state up to a certain periodical inspection by a method other than irradiation of neutrons is newly disposed, radiation of the test piece is not extremely increased even after an extremely long period of summed up reactor operation time, to provide substantially constant radiation level on every test piece. (T.M.)

  3. Nuclear reactor neutron shielding

    Science.gov (United States)

    Speaker, Daniel P; Neeley, Gary W; Inman, James B

    2017-09-12

    A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

  4. Experiment for search for sterile neutrino at SM-3 reactor

    Science.gov (United States)

    Serebrov, A. P.; Ivochkin, V. G.; Samoylov, R. M.; Fomin, A. K.; Zinoviev, V. G.; Neustroev, P. V.; Golovtsov, V. L.; Gruzinsky, N. V.; Solovey, V. A.; Cherniy, A. V.; Zherebtsov, O. M.; Martemyanov, V. P.; Zinoev, V. G.; Tarasenkov, V. G.; Aleshin, V. I.; Petelin, A. L.; Pavlov, S. V.; Izhutov, A. L.; Sazontov, S. A.; Ryazanov, D. K.; Gromov, M. O.; Afanasiev, V. V.; Matrosov, L. N.; Matrosova, M. Yu.

    2016-11-01

    In connection with the question of possible existence of sterile neutrino the laboratory on the basis of SM-3 reactor was created to search for oscillations of reactor antineutrino. A prototype of a neutrino detector with scintillator volume of 400 l can be moved at the distance of 6-11 m from the reactor core. The measurements of background conditions have been made. It is shown that the main experimental problem is associated with cosmic radiation background. Test measurements of dependence of a reactor antineutrino flux on the distance from a reactor core have been made. The prospects of search for oscillations of reactor antineutrino at short distances are discussed.

  5. Methods in nuclear reactors calculations

    International Nuclear Information System (INIS)

    Velarde, G.

    1966-01-01

    Studies are made of the neutron transport equation corresponding to the the real and virtual reactors, as well as the starting hypotheses. Methods are developed to solve the transport equation in slab geometry, and P l ; B l ; M l ; S n and discrete ordinates approximations. (Author)

  6. Device for rearranging control rods of experimental reactors

    International Nuclear Information System (INIS)

    Louda, J.

    1975-01-01

    The invention claims a means for the adjustment of control rods in experimental reactors with a continuously variable pitch of the fuel element spacer. The proposed device permits obtaining maximum variability in the physical modelling of nuclear power reactor cores in experimental reactors. (F.M.)

  7. TREATMENT OF METHANOLIC WASTEWATER BY ANAEROBIC DOWN-FLOW HANGING SPONGE (ANDHS) REACTOR AND UASB REACTOR

    Science.gov (United States)

    Sumino, Haruhiko; Wada, Keiji; Syutsubo, Kazuaki; Yamaguchi, Takashi; Harada, Hideki; Ohashi, Akiyoshi

    Anaerobic down-flow hanging sponge (AnDHS) reactor and UASB reactor were operated at 30℃ for over 400 days in order to investigate the process performance and the sludge characteristics of treating methanolic wastewater (2 gCOD/L). The settings OLR of AnDHS reactor and of UASB reactor were 5.0 -10.0 kgCOD/m3/d and 5.0 kgCOD/m3/d. The average of the COD removal demonstrated by both reactors were over 90% throughout the experiment. From the results of methane producing activities and the PCR-DGGE method, most methanol was directly converted to methane in both reactors. The conversion was carried out by different methanogens: one closely related to Methanomethylovorans hollandica in the AnDHS retainted sludge and the other closely related to Methanosarcinaceae and Metanosarciales in the UASB retainted sludge.

  8. “When Joseph awoke, he did as the angel of the Lord had commanded him” (Mt 1 : 24. Discreet, Effective Service

    Directory of Open Access Journals (Sweden)

    Tomasz Maria Dąbek

    2013-03-01

    Full Text Available Saint Joseph was a righteous man. He respected the Law of Israel. The decision to divorce Mary after she was found with child was not an easy one, although he knew he was not the child’s father. Instructed by the angel of the Lord, he took her to his home, gave a name to her child as his legal guardian (Mt 1 : 18–25, took care of his wife and her child, organised their trip to Egypt (Mt 2 : 13–15, then their return to Palestine and life in Nazareth (Mt 2 : 19–23; cf. Lk 2 : 39–52. His active obedience to God is the fulfilment of all the things Saint James will later describe as faith shown by the works of the faithful (Jas 2 : 14–17. 20–26. Joseph is put among those who bear witness to the faith of the Old Testament. The Gospels give no account of his exact words, although he fulfilled everything that he had been commanded. Saint Joseph can be a patron of everyone who tries to fulfil God’s will in a discreet and effective manner, with perseverance produced by faith (cf. Jas 1 : 3f.. With his works and life he shows how to bridle your tongue (cf. Jas 1 : 26f.; 3 : 1–13 and take care of the ones that need it the most (cf. Jas 1 : 27; 3 : 13, discreetly fulfilling your duties.

  9. Análise dos casos de corrupção na Petrobras sob a ótica dos princípios regulatórios propostos por Joseph Stiglitz / Analysis of the cases of corruption in Petrobras from the point of view of the regulatory principles proposed by Joseph Stiglitz

    Directory of Open Access Journals (Sweden)

    Fernando Antônio da Silva Falcão

    2017-04-01

    Full Text Available Purpose – To find, in light of the principles of regulation proposed by Joseph Stiglitz, how government and market failures contributed to the occurrence of corruption cases in Petrobras. Methodology/approach/design – This article analyzes corruption scandals in Petrobras based on the information gathered in Operation Car Wash and, based on the principles of regulation established by Joseph Stiglitz, critically verifies how market and government failures contributed to the fraud, collusion and corruption in the state-owned enterprise. Findings – Market and government failures contributed decisively to the occurrence of corruption in the state-owned enterprise. Practical implications – The present study can help designing a regulatory framework that effectively discourages the practice of fraud, collusion and corruption in public bids.

  10. FBR type reactor

    International Nuclear Information System (INIS)

    Kimura, Kimitaka; Fukuie, Ken; Iijima, Tooru; Shimpo, Masakazu.

    1994-01-01

    In an FBR type reactor for exchanging fuels by pulling up reactor core upper mechanisms, a connection mechanism is disposed for connecting the top of the reactor core and the lower end of the reactor core upper mechanisms. In addition, a cylindrical body is disposed surrounding the reactor core upper mechanisms, and a support member is disposed to the cylindrical body for supporting an intermediate portion of the reactor core upper mechanisms. Then, the lower end of the reactor core upper mechanisms is connected to the top of the reactor core. Same displacements are caused to both of them upon occurrence of earthquakes and, as a result, it is possible to eliminate mutual horizontal displacement between a control rod guide hole of the reactor core upper mechanisms and a control rod insertion hole of the reactor core. In addition, since the intermediate portion of the reactor core upper mechanisms is supported by the support member disposed to the cylindrical body surrounding the reactor core upper mechanisms, deformation caused to the lower end of the reactor core upper mechanisms is reduced, so that the mutual horizontal displacement with respect to the control rod insertion hole of the reactor core can be reduced. As a result, performance of control rod insertion upon occurrence of the earthquakes is improved, so that reactor shutdown is conducted more reliably to improve reactor safety. (N.H.)

  11. The prototype fast reactor

    International Nuclear Information System (INIS)

    Broomfield, A.M.

    1985-01-01

    The paper concerns the Prototype Fast Reactor (PFR), which is a liquid metal cooled fast reactor power station, situated at Dounreay, Scotland. The principal design features of a Fast Reactor and the PFR are given, along with key points of operating history, and health and safety features. The role of the PFR in the development programme for commercial reactors is discussed. (U.K.)

  12. Department of reactor technology

    International Nuclear Information System (INIS)

    1980-01-01

    The activities of the Department of Reactor Technology at Risoe during 1979 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

  13. NCSU Reactor Sharing Program

    International Nuclear Information System (INIS)

    Perez, P.B.

    1993-01-01

    The Nuclear Reactor Program at North Carolina State University provides the PULSTAR Research Reactor and associated facilities to eligible institutions with support, in part, from the Department of Energy Reactor Sharing Program. Participation in the NCSU Reactor Sharing Program continues to increase steadily with visitors ranging from advance high school physics and chemistry students to Ph.D. level research from neighboring universities

  14. Reactor safety method

    International Nuclear Information System (INIS)

    Vachon, L.J.

    1980-01-01

    This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature

  15. Current Status of TRR-1/M1

    International Nuclear Information System (INIS)

    Sittichai, Chaiyut

    2000-01-01

    In 1961, the first Thai Research Reactor, TRR-1, having power of 1 MW was established. It was located at Office of Atomic Energy for Peace (OAEP) in Bangkok. TRR-1 was completely commissioned in June 1962. Plate typed high-enriched uranium (HEU) and U 3 O 8 -Al were used as fuel. Light water used as moderator and coolant. During 1975-1977, TRR-1 was shut down for modification. The reactor core and control system were disassembled and replaced by TRIGA Mark III. It is a circular hexagonal core typed reactor designed by General Atomics Company (GA). Afterwards, TRR-1 was officially renamed to Thai Research Reactor 1/Modification 1 (TRR-1/M1). TRR-1/M1 is a multipurpose reactor with nominal power of 2 MW. This swimming pool typed reactor uses low-enriched uranium (LEU) as fuel and light water as coolant and moderator. To date, the reactor has been operated with core No.12 that released power 1135 MWD to serve the user. The reactor has been serving for various kinds of utilization, for example, to produce radioisotope, neutron beam experiments and reactor physics experiments. This report explains in detail regarding operational experience and current status of this reactor, for example, reactor operation and reactor utilization. (author)

  16. Joseph Roth in den Niederlanden und Flandern: Vermittlung, Vernetzung und Orchestierung eines vielseitigen Autors im niederländischsprachigen Kontext 1924-1940

    OpenAIRE

    Snick, E.S.

    2011-01-01

    This dissertation investigates the contemporary mediators and networks that played an important role in the canonization of Joseph Roth’s (original and translated) work in Flanders and the Netherlands. These mediators and networks made a substantial contributionto Roth’s intellectual and literary life (and were the key to his ‘survival’) in the period of his exile in these countries. The theoretical framework employed in this study is based on Von Dorleijn and van Rees’s views on the literary...

  17. Medical doctors as the captain of a ship: an analysis of medical students? book reports on Joseph Conrad?s ?Lord Jim?

    OpenAIRE

    Hwang, Kun; Lee, Seung Jae; Kim, Seong Yeon; Hwang, Se Won; Kim, Ae Yang

    2014-01-01

    Purpose: In South Korean ferry disaster in 2014, the captain abandoned the ship with passengers including high school students still aboard. We noticed the resemblance of abandoning the ship with passengers still aboard the ferry (named the Sewol) and the ship Patna, which was full of pilgrims, in Joseph Conrad’s novel “Lord Jim.” The aim of this study is to see how medical students think about the role of a medical doctor as a captain of a ship by analyzing book reports on Conrad’s “Lord Jim...

  18. Physics of nuclear reactors

    International Nuclear Information System (INIS)

    Baeten, Peter

    2006-01-01

    This course gives an introduction to Nuclear Reactor Physics. The first chapter explains the most important parameters and concepts in nuclear reactor physics such as fission, cross sections and the effective multiplication factor. Further on, in the second chapter, the flux distributions in a stationary reactor are derived from the diffusion equation. Reactor kinetics, reactor control and reactor dynamics (feedback effects) are described in the following three chapters. The course concludes with a short description of the different types of existing and future reactors. (author)

  19. 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.)

  20. Remarks of Joseph Marrone

    International Nuclear Information System (INIS)

    Marrone, J.

    1985-01-01

    The author's remarks are directed primarily at proposals that have been made that would substantially tort law with respect to radiation claims in order to ease the ability of claimants to recovery damages from defendants. The change would be based upon what had been assumed to be a ''scientific'' means of measuring the ''probability'' that exposure to ionizing radiation was the case of a cancer in a particular claimant. The remarks are divided into three parts: a summary description of the nuclear insurance pools, including the tort radiation claims filed against the pools; and a brief description of claims against the Federal Government and its contractors; an examination of the elementary principles of tort law, and an outline of the threat that has developed that would transform it into a hybrid social benefits program; and comment on the danger to the integrity of science when it is injected into the legislative process