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Sample records for james a. fitzpatrick reactor

  1. 78 FR 50458 - Entergy Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee...

    2013-08-19

    ... Nuclear Operations, Inc., James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee Nuclear Power Station... that the NRC take action with regard to James A. Fitzpatrick Nuclear Power Plant, Vermont Yankee.... Fitzpatrick Nuclear Power Plant (Fitzpatrick), Vermont Yankee Nuclear Power Station (Vermont Yankee), and...

  2. 75 FR 13323 - James A. Fitzpatrick Nuclear Power Plant; Exemption

    2010-03-19

    ... Power Plant; Exemption 1.0 Background Entergy Nuclear Operations, Inc. (the licensee) is the holder of... nuclear power plants that were licensed before January 1, 1979, satisfy the requirements of 10 CFR Part 50...), as supplemented by letter dated March 30, 2009, ``James A. FitzPatrick Nuclear Power Plant-Response...

  3. 75 FR 16520 - James A. Fitzpatrick Nuclear Power Plant; Exemption

    2010-04-01

    ... Power Plant; Exemption 1.0 Background Entergy Nuclear Operations, Inc. (the licensee) is the holder of Facility Operating License No. DPR-59, which authorizes operation of the James A. FitzPatrick Nuclear Power... date for all operating nuclear power plants, but noted that the Commission's regulations provide...

  4. 75 FR 11575 - James A. Fitzpatrick Nuclear Power Plant Environmental Assessment and Finding of No Significant...

    2010-03-11

    ... Power Plant Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory...), for the operation of the James A. FitzPatrick Nuclear Power Plant (JAFNPP) located in Oswego County... the Final Environmental Statement for the James A. FitzPatrick Nuclear Power Plant, Docket No. 50-333...

  5. James A. FitzPatrick Nuclear Power Plant recirculation pumps vibration system installation and performance since July 7, 1990

    Lefter, J.

    1992-01-01

    James A. FitzPatrick recirculation pumps are vertical units consisting of General Electric 5,300 hp variable speed motors driving Byron Jackson Pumps. Speed range is from 400 rpm at 20% reactor power to 1,480 rpm at 100% power. Full speed pump output is 42,500 gpm at 530 ft. head. This paper describes the vibration monitoring system. The design of this vibration monitoring system took about five months and was installed during plant refueling outage between February and May 1990. The objectives of this project were as follows: (1) document and assess the mechanical condition of each RRP during plant startup normal operation and shutdown; (2) identify any areas of operation that might be harmful to the unit; (3) perform impact testing of the proximity probe brackets to determine if any bracket resonances existed in the 0 to 20 times operating speed region (0 to 20X); (4) define and recommend Acceptance Regions in the TDM system

  6. James A. FitzPatrick Nuclear Power Plant. Semiannual operating report, January--June 1975

    1975-01-01

    The reactor, which was licensed for operation on October 17, 1974, has been in the start-up testing phase and has successfully completed the 50 percent testing plateau. Information is presented concerning operations, maintenance, instrumentation and control, radiochemistry and radiation protection; luel loading, and abnormal occurrences. Two supplements are included. Supplement A is the environmental report and Supplement B describes effluents and waste disposal. (FS)

  7. James A. FitzPatrick Nuclear Power Plant. Semiannual operating report, July--December 1975

    1976-01-01

    Net electrical power generated was 1,824,209 MWh(e) with the reactor on line 3,229.2 hrs. Information is presented concerning operation, power generation, shutdowns, corrective maintenance, physics and testing, occupational radiation exposure, release of radioactive materials, and abnormal and reportable occurrences

  8. Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the James A. Fitzpatrick Nuclear Power Plant (Docket No. 50-333)

    Selan, J.C.

    1983-01-01

    This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the James A. FitzPatrick Nuclear Power Plant. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations

  9. Divers muscle Fitzpatrick's mussels

    Hobbs, B.; Kahabka, J.

    1996-01-01

    This article describes how an effective manual cleaning technique has helped rid submerged intake structures of this passive-aggressive pest. The New York Power Authority's (NYPA) James A. Fitzpatrick (JAF) Nuclear Power Plant is located in Lycoming, NY, on the southeast shore of Lake Ontario. An 850-MWe, GE-design boiling water reactor (BWR), the unit has been in service since 1975. Water drawn from the Lake supplies cooling to plant loads via the circulating water system and three service water systems. These share a common intake system consisting of an offshore cap (crib), horizontal intake tunnel, two vertical risers and forebay/screenwell area

  10. Decide, design, and dewater de waste: A blueprint from Fitzpatrick

    Robert, D.E.

    1994-01-01

    Using a different process to clean concentrated waste tanks at the James A. FitzPatrick nuclear power plant in New York saved nearly half million dollars. The plan essentially allowed processing concentrator bottoms as waste sludge (solidification versus dewatering) that could still meet burial ground requirements. The process reduced the volume from 802.2 to 55 cubic feet. This resin throwaway system eliminated chemicals in the radwaste systems and was designed to ease pressure on the pradwaste processing system, reduce waste and improve plant chemistry. This article discusses general aspects of the process

  11. Use of human factors in the integration of a safety parameter display system (SPDS) and emergency response facility (ERF) capabilities for the James A. Fitzpatrick nuclear power plant

    Fish, H.C. Jr.; Gutierrez, R.

    1987-01-01

    In 1987, New York Power Authority's Emergency and Process Information Computer (EPIC) System will be operational. The EPIC system was designed to perform two distinct functions: to serve as an advanced replacement for the existing plant process computer and to assist in providing the JAFNPP operations staff with information during plant emergency conditions. Besides meeting the operational and regulatory goals of NYPA, EPIC was designed to meet NYPA human factors criteria. Using human factors literature, industry standards and guidelines, a Human Factors Criteria document was prepared for the EPIC project. This document served as the bases for all hardware, display, and documentation design applicable to EPIC. The major tasks of the EPIC human factors plan include integration of past and present applicable human factors information, establishment of a user definition using data gathered from control room observations (startup and shutdown of JAFNPP), survey of computer programs used by the operators, and obtaining input from licensed operators. These major tasks played a role in the design of the design of the control room configuration, the design and development of computer generated displays, and the format in which the displayed and hard copy information would be presented to the user. This paper presents an overview of the human factors work performed and the documents researched or developed in the design of EPIC displays, software, and hardware. The location and operation of this new computer based information system, like the displays was based on the systematic application of operations and human factors principles

  12. Entrevista a James Curran

    Curran, James; Figueiras, Rita; Ribeiro, Nelson

    2012-01-01

    James Curran é professor catedrático e diretor do Goldsmiths Leverhulme Media Research Centre. A sua investigação centra-se sobretudo na relação entre os media e a democracia, quer através do ângulo da história dos media, quer da economia política dos media, áreas sobre as quais publicou mais de duas dezenas de livros, como Media and Democracy, Power without Responsability (co-autoria de Jean Seaton) e Media and Society. Na sua obra mais recente, Misunderstanding the Internet (co-autoria de N...

  13. Interview with Kathleen Fitzpatrick

    Andrés Lomeña Cantos

    2012-12-01

    Full Text Available Kathleen Fitzpatrick, born in 1967, teaches Media Studies in Pomona University (California, coordinator of the MediaCommons plattaform and one of the most remarkable Digital Humantties academic. His first book The Anxiety of Obsolescence (http://www.anxietyofobsolescence.com reflects on some novelist technophilia as a mecanism to maintain his privilege status inside a media ecology increasingly comptetive. His next essay, Planned obsolecence (http://www.plannedobsolescence.net, extends his critics to the old humanities role and meditate about pressent and future of academic publications.

  14. James B. Macdonald: A Bibliography.

    Brubaker, Dale L., Comp.; Brookbank, Gayle, Comp.

    1986-01-01

    Presents a bibliography of James B. Macdonald's writings and printed speeches arranged chronologically according to the educator's themes of inquiry. Macdonald's videotaped autobiography identifies four explorative stages: (1) Scientism, (2) person-centered humanism, (3) sociopolitical humanism, and (4) transcendentalism, signaling a need for…

  15. A Conversation with James Hannan

    Gilliland, Dennis; Ramamoorthi, R. V.

    2010-01-01

    Jim Hannan is a professor who has lived an interesting life and one whose fundamental research in repeated games was not fully appreciated until late in his career. During his service as a meteorologist in the Army in World War II, Jim played poker and made weather forecasts. It is curious that his later research included strategies for repeated play that apply to selecting the best forecaster. ¶ James Hannan was born in Holyoke, Massachusetts on September 14, 1922. He attended St. Jero...

  16. James A. FitzPatrick Nuclear Power Plant. Annual report of operations: January-December 1976

    1977-01-01

    Net electrical energy generated was 4,156,298 MWH with the generator on line 6,289.1 hrs. Information is presented concerning operating experience, specification changes, maintenance, licensee event reports, fuel performance and data tabulations

  17. A chat with James Watson

    2011-01-01

    On 6 September, Nobel laureate James Watson paid a visit to CERN. In this interview, he shares his views with CERN's Paola Catapano.      var flash_video_player=get_video_player_path(); insert_player_for_external('Video/Public/Movies/2011/CERN-MOVIE-2011-144/CERN-MOVIE-2011-144-0753-kbps-640x360-25-fps-audio-64-kbps-44-kHz-stereo', 'mms://mediastream.cern.ch/MediaArchive/Video/Public/Movies/2011/CERN-MOVIE-2011-144/CERN-MOVIE-2011-144-0480-kbps-512x288-25-fps-audio-128-kbps-48-kHz-stereo.wmv', 'false', 480, 360, 'https://mediastream.cern.ch/MediaArchive/Video/Public/Movies/2011/CERN-MOVIE-2011-144/CERN-MOVIE-2011-144-posterframe-640x360-at-10-percent.jpg', '1384418', true, 'Video/Public/Movies/2011/CERN-MOVIE-2011-144/CERN-MOVIE-2011-144-0600-kbps-maxH-360-25-fps-audio-128-kbps-48-kHz-stereo.mp4');

  18. Poor and Rich in James: A Relevance Theory Approach to James's Use of the Old Testament

    Morales, Nelson R.

    2015-01-01

    The epistle of James was for years a forgotten book in academic circles. In recent decades, however, a renewed focus on early Judaism has generated interest in looking at James with new eyes. Poverty and wealth in the epistle continues to be a point of interest. Other topics, however, are still to be explored. One of these topics is the rhetorical…

  19. A retrospective chart review to assess the safety of nonablative fractional laser resurfacing in Fitzpatrick skin types IV to VI.

    Clark, Charlotte M; Silverberg, Jonathan I; Alexis, Andrew F

    2013-04-01

    Laser resurfacing in patients with Fitzpatrick skin phototypes (SPT) IV to VI is associated with a higher risk of pigmentary alteration. There is a paucity of studies evaluating optimum treatment parameters for fractional lasers in darkly pigmented skin types. This is a retrospective review of medical records for patients with SPT IV to VI who were treated with a 1,550 nm erbium-doped fractional nonablative laser (Fraxel Re:Store SR 1550; Solta Medical, Hayword, CA). Data were collected from patient charts and the clinic laser logbook from January 2008 to January 2012. The frequency of treatment-associated postinflammatory hyperpigmentation (PIH) and treatment settings used were evaluated. A total of 115 total laser sessions (45 patients) were included in our analysis. Five of the sessions (4%) were accompanied by PIH, 2 of which occurred in a single patient. Only 1 episode of PIH lasted longer than 1 month (2 months). Two of the 5 cases had only transient PIH (≤7 days), one of which was reported by the patient and not clinically evident on examination. The 1,550 nm erbium-doped fractional laser is well tolerated in SPT IV to VI. Fractional laser resurfacing, with the settings used and pretreatment and posttreatment hydroquinone 4% cream, was associated with a low risk of PIH in darker skin types.

  20. Laser and Light Treatments for Hair Reduction in Fitzpatrick Skin Types IV-VI: A Comprehensive Review of the Literature.

    Fayne, Rachel A; Perper, Marina; Eber, Ariel E; Aldahan, Adam S; Nouri, Keyvan

    2018-04-01

    Unwanted facial and body hair presents as a common finding in many patients, such as females with hirsutism. With advances in laser and light technology, a clinically significant reduction in hair can be achieved in patients with light skin. However, in patients with darker skin, Fitzpatrick skin types (FST) IV-VI, the higher melanin content of the skin interferes with the proposed mechanism of laser-induced selective photothermolysis, which is to target the melanin in the hair follicle to cause permanent destruction of hair bulge stem cells. Many prospective and retrospective studies have been conducted with laser and light hair-removal devices, but most exclude patients with darkly pigmented skin, considering them a high-risk group for unwanted side effects, including pigmentation changes, blisters, and crust formation. We reviewed the published literature to obtain studies that focused on hair reduction for darker skin types. The existing literature for this patient population identifies longer wavelengths as a key element of the treatment protocol and indicates neodymium-doped yttrium aluminum garnet (Nd:YAG), diode, alexandrite, and ruby lasers as well as certain intense pulsed light sources for safe hair reduction with minimal side effects in patients with FST IV-VI, so long as energy settings and wavelengths are appropriate. Based on the findings in this review, safe and effective hair reduction for patients with FST IV-VI is achievable under proper treatment protocols and energy settings.

  1. A word from James Gillies

    2008-01-01

    On Wednesday 10 September, CERN started up the LHC and put basic science firmly on the public agenda. The statistics speak for themselves: 300 journalists on site, over 2000 TV broadcasts, 100 million hits on the CERN website, and an estimated global audience rivalling the number of particles in the LHC’s first beam. Since then, the media have not let us go. An LHC article carried by one on-line news channel was its most successful story ever, and science correspondents are finding themselves in the unfamiliar position of being asked for more stories on particle physics. By inviting the media in to share the start-up with us, we’ve created a platform to build on as we go through first collisions and into physics. Those journalists here on the day saw the reality of starting up the LHC, complete with all the emotional highs and lows. There’s no doubt that they appreciated it. "I felt very much like I’d been given a front row ...

  2. 75 FR 14637 - James A. FitzPatrick Nuclear Power Plant; Environmental Assessment and Finding of No Significant...

    2010-03-26

    ...). There will be no change to radioactive effluents that affect radiation exposures to plant workers and... cultural resources. There would be no impact to socioeconomic resources. Therefore, no changes to or...

  3. A case of Swyer-James syndrome

    Suzuki, Toshimitsu; Ohtani, Naoshi; Kimura, Sohichi; Izuchi, Rokuro; Iio, Masaaki; Fujinami, Kenji.

    1982-01-01

    Infantile infections are thought to constitute one of the main bases of the etiology of Swyer-James syndrome. This case seems to support the above theory allowing for the anamnesis of the pleuritis at 2 years of age, bronchographical findings - bilateral but markedly left-sided bud-like bronchiectatic changes - and left pulmonary angiographical findings - simultaneous appearance of pulmonary arteries and veins with scarce capillary image. Concerning the ventilation of this syndrome, 133 Xe inhalation test showed a ''Pendelluft'' phenomenon, shift of 133 Xe from the healthy to the affected lung on forced expiration. (author)

  4. James Hillman: Toward a poetic psychology.

    Avens, R

    1980-09-01

    InThe Dream and the Underworld James Hillman continues to deepen and to refine Jung's recovery of the spontaneous image-making of the soul. Hillman's contribution lies in his "imaginai reduction"-relating of images to their archetypal background in Greek mythology. Myth is seen as the maker of the psyche, and, in turn, the soul-making ispoesis-a return to the imaginal and poetic basis of consciousness. Dreams, understood poetically, are neither messages to be deciphered and used for the benefit of the rational ego (Freud) nor compensatory to the ego (Jung); they are complete in themselves and must be allowed to speak for themselves. Hillman also sees dreams as initiations into the underworld of death-the other side of life where our imaginal substance is unobstructed by the literal and dualistic standpoints of the dayworld.

  5. James Madison High School. A Curriculum for American Students.

    Bennett, William J.

    This document presents the Secretary of Education's personal concept of a sound secondary school core curriculum. It is called "James Madison High School" in honor of President James Madison and his strong views that the people, in order to govern properly, must arm themselves with knowledge. The theoretical curriculum consists of four…

  6. Resurfacing of facial acne scars with a new variable-pulsed Er:YAG laser in Fitzpatrick skin types IV and V

    Namitha Chathra

    2018-01-01

    Full Text Available Introduction: The Er:YAG laser, considered to be less effective than CO2 laser in its traditional form, in its new modulated version has variable pulse technology that is claimed to be superior to the earlier versions of the laser.Aim: The aim of the study was to check efficacy and safety of the new variable square pulse (VSP Er:YAG laser in the management of acne scar in patients with Fitzpatrick skin types IV and V.Materials and Methods: This retrospective study consisted of 80 patients (Fitzpatrick skin types IV and V with atrophic and hypertrophic facial acne scars. Records of the patients who had undergone four treatment sessions with VSP technology equipped with Er:YAG laser were extracted. Each patient had undergone a minimum of four sessions. Fractional mode at medium laser pulse (SP and long pulse (LP was employed for the depressed center of the scars to stimulate neocollagenogenesis. Short laser pulse (MSP in nonfractionated mode was used for ablating the raised scar border and hypertrophic scars. Goodman and Baron global scarring grading system was used for qualitative and quantitative assessments. Patient’s satisfaction to the treatment and observer’s assessment of improvement (based on photographs was graded as poor (75% improvement.Results: At the end of the four sessions, the number of patients in grade IV postacne scarring reduced from 16 to 2 and that in grade III from 47 to 29. The mean score significantly dropped from 36.94 to 27.5. Subjective assessment revealed that 78 of 80 patients had noticed more than 25% improvement, with 50 of them showing more than 50% improvement at the end of four sessions. Eight patients perceived an excellent response and 42 reported a good response. This is notably higher than the observer’s grading, which showed an excellent response in only 2 patients and a good response in 35. Adverse effects were limited to prolonged erythema (two patients, prolonged crusting (one patient, and

  7. Resurfacing of Facial Acne Scars With a New Variable-Pulsed Er:YAG Laser in Fitzpatrick Skin Types IV and V.

    Chathra, Namitha; Mysore, Venkataram

    2018-01-01

    The Er:YAG laser, considered to be less effective than CO 2 laser in its traditional form, in its new modulated version has variable pulse technology that is claimed to be superior to the earlier versions of the laser. The aim of the study was to check efficacy and safety of the new variable square pulse (VSP) Er:YAG laser in the management of acne scar in patients with Fitzpatrick skin types IV and V. This retrospective study consisted of 80 patients (Fitzpatrick skin types IV and V) with atrophic and hypertrophic facial acne scars. Records of the patients who had undergone four treatment sessions with VSP technology equipped with Er:YAG laser were extracted. Each patient had undergone a minimum of four sessions. Fractional mode at medium laser pulse (SP) and long pulse (LP) was employed for the depressed center of the scars to stimulate neocollagenogenesis. Short laser pulse (MSP) in nonfractionated mode was used for ablating the raised scar border and hypertrophic scars. Goodman and Baron global scarring grading system was used for qualitative and quantitative assessments. Patient's satisfaction to the treatment and observer's assessment of improvement (based on photographs) was graded as poor (75% improvement). At the end of the four sessions, the number of patients in grade IV postacne scarring reduced from 16 to 2 and that in grade III from 47 to 29. The mean score significantly dropped from 36.94 to 27.5. Subjective assessment revealed that 78 of 80 patients had noticed more than 25% improvement, with 50 of them showing more than 50% improvement at the end of four sessions. Eight patients perceived an excellent response and 42 reported a good response. This is notably higher than the observer's grading, which showed an excellent response in only 2 patients and a good response in 35. Adverse effects were limited to prolonged erythema (two patients), prolonged crusting (one patient), and postinflammatory hyperpigmentation (one patient). Ninety-seven percent of

  8. Skin color parameters and Fitzpatrick phototypes in estimating the risk of skin cancer: A case-control study in the Polish population.

    Sitek, Aneta; Rosset, Iwona; Żądzińska, Elżbieta; Kasielska-Trojan, Anna; Neskoromna-Jędrzejczak, Aneta; Antoszewski, Bogusław

    2016-04-01

    Light skin pigmentation is a known risk factor for skin cancer. Skin color parameters and Fitzpatrick phototypes were evaluated in terms of their usefulness in predicting the risk of skin cancer. A case-control study involved 133 individuals with skin cancer (100 with basal cell carcinoma, 21 with squamous cell carcinoma, 12 with melanoma) and 156 healthy individuals. All of them had skin phototype determined and spectrophotometric skin color measurements were done on the inner surfaces of their arms and on the buttock. Using those data, prediction models were built and subjected to 17-fold stratified cross-validation. A model, based on skin phototypes, was characterized by area under the receiver operating characteristic curve = 0.576 and exhibited a lower predictive power than the models, which were mostly based on spectrophotometric variables describing pigmentation levels. The best predictors of skin cancer were R coordinate of RGB color space (area under the receiver operating characteristic curve 0.687) and melanin index (area under the receiver operating characteristic curve 0.683) for skin on the buttock. A small number of patients were studied. Models were not externally validated. Skin color parameters are more accurate predictors of skin cancer occurrence than skin phototypes. Spectrophotometry is a quick, easy, and affordable method offering relatively good predictive power. Copyright © 2015 American Academy of Dermatology, Inc. Published by Elsevier Inc. All rights reserved.

  9. Underwater cleaning techniqued used for removal of zebra mussels at the FitzPatrick Nuclear Power Plant

    Hobbs, B.; Kahabka, J.

    1995-01-01

    This paper discusses the use of a mechanical brush cleaning technology recently used to remove biofouling from the Circulating Water (CW) System at New York Power Authority's James A. FitzPatrick Nuclear Power Plant. The FitzPatrick plant had previously used chemical molluscicide to treat zebra mussels in the CW system. Full system treatment was performed in 1992 with limited forebay/screenwell treatment in 1993. The New York Power Authority (NYPA) decided to conduct a mechanical cleaning of the intake system in 1994. Specific project objectives included: (1) Achieve a level of surface cleaniness greater than 98%; (2) Remove 100% of debris, both existing sediment and debris generated as a result of cleaning; (3) Inspect all surfaces and components, identifying any problem areas; (4) Complete the task in a time frame within the 1994-95 refueling outage schedule window, and; (5) Determine if underwater mechanical cleaning is a cost-effective zebra mussel control method suitable for future application at FitzPatrick. A pre-cleaning inspection, including underwater video photography, was conducted of each area. Cleaning was accomplished using diver-controlled, multi-brush equipment included the electro-hydraulic powered Submersible Cleaning and Maintenance Platform (SCAMP), and several designs of hand-held machines. The brushes swept all zebra mussels off surfaces, restoring concrete and metal substrates to their original condition. Sensitive areas including pump housings, standpipes, sensor piping and chlorine injection tubing, were cleaned without degradation. Submersible vortex vacuum pumps were used to remove debris from the cavity. More than 46,000 ft 2 of surface area was cleaned and over 460 cubic yards of dewatered debris were removed. As each area was completed, a post-clean inspection with photos and video was performed

  10. Are lasers superior to lights in the photoepilation of Fitzpatrick V and VI skin types? - A comparison between Nd:YAG laser and intense pulsed light.

    Bs, Bibilash; Chittoria, Ravi Kumar; Thappa, Devinder Mohan; Mohapatra, Devi Prasad; Mt, Friji; S, Dineshkumar; Pandey, Sandhya

    2017-10-01

    There are no large volume comparative studies available to compare the efficacy of lasers over lights for hair removal in Fitzpatrick V and VI skin types. This study is designed to compare the efficacy of Nd:YAG laser versus IPL in the darker skin types. Thirty-nine patients included in Group-1 were treated with Nd:YAG and 31 in Group-2 with IPL. Both groups received 5 sessions of treatment. The hair counts were assessed using digital photography and manual counting method before and after treatment and the results were analysed. Patient satisfaction scores and pain scores were recorded in each session and compared. Mean hair reduction in the IPL group was 25.70 and Nd:YAG group was 24.12 (95% CI). In the Nd:YAG group, 59% of subjects had burning sensation while the figure was 32.3% in IPL group. Burning was less in IPL group (p < 0.023). There were no statistically significant differences noticed regarding hyperpigmentation in both the groups (p < 0.115). Both Nd:YAG and IPL are equally effective for epilation of the darker skin types. Nd:YAG is associated with mild burning sensation in a significant number of patients. Patient satisfaction scores were comparable in both the groups.

  11. James Madison High: A School at the Crossroads

    Stroup, John T.; Salmonowicz, Michael J.; Broom, Christopher C.

    2007-01-01

    This case tells the story of James Madison High School, which became the epicenter of a debate over the future reorganization and control of large secondary schools in the Los Angeles Unified School District (LAUSD). The LAUSD, recently taken over by the newly elected mayor, was fighting for control of this 3,000-student high school with a charter…

  12. Non-invasive high-intensity focused ultrasound for UV-induced hyperpigmentation in Fitzpatrick skin types III and IV: a prospective, randomized, controlled, evaluator-blinded trial.

    Vachiramon, Vasanop; Jurairattanaporn, Natthachat; Harnchoowong, Sarawin; Chayavichitsilp, Pamela

    2018-02-01

    Skin hyperpigmentation is a frequently encountered problem, particularly in darker skin types. Unfortunately, standard treatments for this condition have shown disappointing results. High-intensity focused ultrasound (HIFU) is commonly indicated for skin laxity, but recently was used to treat UV-induced hyperpigmentation in animal models. This study is aimed to evaluate the efficacy and safety of high-intensity focused ultrasound for UVB-induced hyperpigmentation in human subjects. A randomized, evaluator-blinded pilot study was conducted on 20 subjects. Each subject was induced three hyperpigmentary spots by local broadband UVB. After 2 weeks, each spot was randomly allocated to control, low-energy, and high-energy HIFU. Subjects were instructed to follow up weekly for a duration of 1 month. Lightness index measurements, mean improvement scores, subjects' satisfaction, pain scores, and side effects were evaluated. All 20 subjects completed the study. Fourteen subjects had Fitzpatrick (FPT) skin type III and six subjects had FPT skin type IV. Twelve subjects showed greater improvement at control sites while eight subjects showed greater improvement at HIFU-treated sites. In FPT skin type III, HIFU appeared to be inferior to control in both lightness index and mean improvement scores, but in FPT skin type IV, HIFU had greater lightness index improvement and higher improvement scores than control. Side effects were more frequent in high-energy-treated areas. Focused ultrasound may be offered in some patients with hyperpigmentary conditions. More research is needed to determine proper energy settings for optimal outcome.

  13. "To Mediate Relevantly": A Response to James Simpson

    Waters, Alan

    2009-01-01

    In Waters (2009), it was contended that, because of its ideological orientation, a good deal of applied linguistics for language teaching (ALLT) fails to "mediate relevantly" between academic and practitioner perspectives. James Simpson's rejoinder to my article (Simpson 2009) attempts to refute its claims. However, in my view, it fails to do so,…

  14. A tribute to James A. Holcombe

    Sturgeon, Ralph

    2015-03-01

    My first interaction with Jim Holcombe was by letter in late 1977 (well before our instant e-mail communications age we all enjoy and/or curse). Jim was enquiring via some subtle questions about a paper I had recently published in Analytical Chemistry on the mechanisms of atomization in the graphite furnace. This brief correspondence initiated a 35 year period of technical interaction and friendship which literally carried us throughout the world to many conferences and more than a few shared hotel rooms in the days when one would make sacrifices to reduce travel costs to enable conference attendance. At the SciX 2013 (FACSS) meeting in Milwaukee WI, a special symposium was organized by John Molloy in honor of Jim's achievements. This was the closest "public" venue to correspond with Jim's announced 2013 spring retirement and his "exit" from a working career at the Department of Chemistry, University of Texas at Austin. It was a distinct honor for me to have Nicolo Omenetto ask if I would help coordinate this special issue of Spectrochim. Acta, Part B in honor of Jim's career/achievements. This gives me the opportunity to publicly comment on my personal association with this "Texas" gentleman from Colorado, a genuine "out of the box" thinker, a productive, highly acknowledged but humble character that I am grateful to have known, and with whom I have traveled the world and enjoyed so many good times.

  15. James Madison and a Shift in Precipitation Seasonality

    Druckenbrod, D. L.; Mann, M. E.; Stahle, D. W.; Cleaveland, M. K.; Therrell, M. D.; Shugart, H. H.

    2001-12-01

    An eighteen-year meteorological diary and tree ring data from James Madison's Montpelier plantation provide a consistent reconstruction of early summer and prior fall rainfall for the 18th Century Virginia piedmont. The Madison meteorological diary suggests a seasonal shift in monthly rainfall towards an earlier wet season relative to 20th Century norms. Furthermore, dendroclimatic reconstructions of early summer and prior fall rainfall reflect this shift in the seasonality of summer rainfall. The most pronounced early summer drought during the Madison diary period is presented as a case study. This 1792 drought occurs during one of the strongest El Niño events on record and is highlighted in the correspondence of James Madison.

  16. Socio-economic impacts of nuclear generating stations: Nine Mile Point and Fitzpatrick case study

    Branch, K.; Cochran, R.; Meale, R.

    1982-07-01

    This report documents a case study of the socio-economic impacts of the construction and operation of the Nine Mile Point and Fitzpatrick nuclear power stations. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of the construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

  17. James Baldwin: Biographical Dispatches on a Freedom Writer

    Phillip Luke Sinitiere

    2016-12-01

    Full Text Available This essay presents the idea of James Baldwin as a freedom writer, the organizing idea of my biography in progress. As a freedom writer, Baldwin was a revolutionary intellectual, an essayist and novelist committed unfailingly to the realization of racial justice, interracial political equality, and economic democracy. While the book is still in process, this short essay narrates autobiographically how I came to meet and know Baldwin’s work, explains in critical fashion my work in relation to existing biographies, and reflects interpretively my thoughts-in- progress on this fascinating and captivating figure of immense historical and social consequence.

  18. The case of James A. Garfield: a historical perspective.

    Weiner, Bradley K

    2003-05-15

    In 1881, President James A. Garfield was shot in the back and died 79 days later. During this time, many controversies arose that had repercussions for years to come. Who was to manage the President's care? A prominent local physician took on the case, but after Garfield's death, he was highly criticized for inappropriate care and for excluding more highly qualified surgeons. Where was the bullet? Multiple opinions were given including that of Alexander Graham Bell. The correct suggestion turned out to be that of a young, unknown assistant demonstrator of anatomy. What was the proper treatment? Local wound care, removal of the bullet, and laparotomy all were considered. Many have felt that the choice of treatment may have proved to be worse than the injury itself. What did the autopsy show? Even this was controversial, with different observers claiming different results. This historical perspective reviews the case as well the controversies that surrounded it.

  19. James Gillies

    2008-01-01

    "Physicist James gillies is chief of communications at CERN (the European Organisation for Nuclear Research). Based in the Jura foothills, just outside Geneva, Gillies is part of a teamt hat will fire up CERN's Large Hadron Collierd (LHC) - the most complicated piece of scientific equipment ever built." (1/2 page)

  20. Swyer-James-Macleod's syndrome. A case report

    Pacheco C, Dario; Ojeda Leon, Paulina; Varo Acosta, Humberto; Salcedo Veles, Patricia; Salazar Juan Carlos

    1998-01-01

    This is a case report about a 67 years-old female patient with respiratory syndrome of 8 years with cough and dyspnoea. End-inspiration crackles in the pulmonary auscultation were found in left hemi thorax. Chest x-ray in expiration and inspiration showed hyperluscency and air trapping in the same hemi-thorax. Chest high-resolution CT revealed a low sized, oligohemic left lung with cylindrical bronchiectasis. Perfusion scintigraphy 99Tc labeled showed markedly left lung hypo-perfusion. Mild obstructive process was found in pulmonary function test. Lung biopsy of lingula reported bronchiolitis obliterans. Considered all the results that were obtained from clinical, x-ray and histopathology, a diagnosis of Swyer-James-Macleods syndrome was made

  1. Physiology as the antechamber to metaphysics: the young William James's hope for a philosophical psychology.

    Croce, P J

    1999-11-01

    In the 5 years before 1878, when his career in psychology was becoming established, William James wrote a series of notes and reviews assessing the work of many of the pioneers in the new field. Adopting a public and confident voice, even while he was privately still uncertain and searching, James criticized the dogmatism of positivist and idealist claims to the study of the human brain and mind. In his short writings of 1873-1877, James started to formulate his own middle path. His first steps on that path show that he did not reject either scientific or philosophic inquiry; instead, he viewed scientific knowledge as a way to understand philosophical questions more deeply. Saving his sharpest critiques for positivism, James endorsed scientific investigation without materialist assmptions. While his career in psychology was still only a hope, James treated science as a means toward humanist insight.

  2. A New Observing Tool for the James Clerk Maxwell Telescope

    Folger, Martin; Bridger, Alan; Dent, Bill; Kelly, Dennis; Adamson, Andy; Economou, Frossie; Hirst, Paul; Jenness, Tim

    A new Observing Tool (OT) has been developed at the UK Astronomy Technology Centre, Edinburgh, UK and the Joint Astronomy Centre, Hilo, Hawaii, USA. It is based on the Gemini Observing Tool and provides the first graphical observation preparation tool for the James Clerk Maxwell Telescope (JCMT) as well as being the first use of the OT for a non-optical/IR telescope. The OT allows the observer to assemble high level Science Programs using graphical representations of observation components such as instrument, target, and filter. This is later translated into low level control sequences for telescope and instruments. The new OT is designed to work on multiple telescopes: currently the UK Infrared Telescope (UKIRT) and JCMT. Object-oriented design makes the inclusion of telescope and instrument specific packages easy. The OT is written in Java using GUI packages such as Swing and JSky. A new component for the JCMT OT is the graphical Frequency Editor for Heterodyne instruments. It can be used to specify parameters such as frequencies, bandwidths, and sidebands of multiple subsystems, while graphically displaying the front-end frequency, emission lines and atmospheric transmission. In addition, Flexible Scheduling support has been added to the OT. The observer can define scheduling constraints by arranging observations graphically. Science Programs can be saved as XML or sent directly from the OT to a database (via SOAP).

  3. A Scientific Revolution: The Hubble and James Webb Space Telescopes

    Gardner, Jonathan P.

    2010-01-01

    Astronomy is going through a scientific revolution, responding to a flood of data from the Hubble Space Telescope, other space missions, and large telescopes on the ground. In this talk, I will discuss some of the important discoveries of the last decade, from dwarf planets in the outer Solar System to the mysterious dark energy that overcomes gravity to accelerate the expansion of the Universe. The next decade will be equally bright with the newly refurbished Hubble and the promise of its successor, the James Webb Space Telescope. An infrared-optimized 6.5m space telescope, Webb is designed to find the first galaxies that formed in the early universe and to peer into the dusty gas clouds where stars and planets are born. With MEMS technology, a deployed primary mirror and a tennis-court sized sunshield, the mission presents many technical challenges. I will describe Webb's scientific goals, its design and recent progress in constructing the observatory. Webb is scheduled for launch in 2014.

  4. 75 FR 59237 - TRICARE Co-Pay Waiver at Captain James A. Lovell Federal Health Care Center Demonstration Project

    2010-09-27

    ... DEPARTMENT OF DEFENSE Office of the Secretary TRICARE Co-Pay Waiver at Captain James A. Lovell.... ACTION: Notice of TRICARE Co-Pay waiver at Captain James A. Lovell Federal Health Care Center... ``TRICARE Co-Pay Waiver at Captain James A. Lovell Federal Health Care (FHCC) Demonstration Project.'' Under...

  5. Q-Switched Nd:YAG Laser Removal of Facial Amateur Tattoos in Patients With Fitzpatrick Type VI: Case Series.

    Haik, Josef; Kornhaber, Rachel; Harats, Moti; Israeli, Hadar; Orenstein, Arie

    2016-11-01

    Q-switched neodymium:YAG (Nd:YAG) lasers are reported to be gold standard for laser tattoo removal. In particular, the Q-switched Nd:YAG laser at 1064 nm is widely recognized for the removal of blue/black amateur tattoos. However, treatment modalities in Fitzpatrick Type VI skin carry a greater risk of complications including alterations in pigmentation compared to fairer skin (Fitzpatrick Type I-IV skin). Therefore, the aim of this case series was to describe with the use of the Q-Switched Nd:YAG laser, the removal of carbon-based amateur tattoos on patients with Fitzpatrick Type VI skin as an effective and safe method. Twenty- five patients with Fitzpatrick type VI skin, from Ethiopian origins, with facial tribal tattoos, were treated with the Q- Switched Nd:YAG laser at 1064 nm. Digital images were taken upon every treatment and the clearance rates of the tattoo was evalu- ated by imaging software. We observed an average tattoo clearance rate of 95% among the 45 facial tattoos in 25 patients presented in the case series with minimal pigmentary and textual changes evident. These positive aesthetic results have a signi cant psychosocial impact on the lives of those with Fitzpatrick Type VI skin, in particular the Ethiopian Jewish population. J Drugs Dermatol. 2016;15(11):1448-1452..

  6. Treatment of burn scars in Fitzpatrick phototype III patients with a combination of pulsed dye laser and non-ablative fractional resurfacing 1550 nm erbium:glass/1927 nm thulium laser devices.

    Tao, Joy; Champlain, Amanda; Weddington, Charles; Moy, Lauren; Tung, Rebecca

    2018-01-01

    Burn scars cause cosmetic disfigurement and psychosocial distress. We present two Fitzpatrick phototype (FP) III patients with burn scars successfully treated with combination pulsed dye laser (PDL) and non-ablative fractional lasers (NAFL). A 30-year-old, FP III woman with a history of a second-degree burn injury to the bilateral arms and legs affecting 30% body surface area (BSA) presented for cosmetic treatment. The patient received three treatments with 595 nm PDL (7 mm, 8 J, 6 ms), six with the 1550 nm erbium:glass laser (30 mJ, 14% density, 4-8 passes) and five with the 1927 nm thulium laser (10 mJ, 30% density, 4-8 passes). Treated burn scars improved significantly in thickness, texture and colour. A 33-year-old, FP III man with a history of a second-degree burn injury of the left neck and arm affecting 7% BSA presented for cosmetic treatment. The patient received two treatments with 595 nm PDL (5 mm, 7.5 J, 6 ms), four with the 1550 nm erbium:glass laser (30 mJ, 14% density, 4-8 passes) and two with the 1927 nm thulium laser (10 mJ, 30% density, 4-8 passes). The burn scars became thinner, smoother and more normal in pigmentation and appearance. Our patients' burn scars were treated with a combination of PDL and NAFL (two wavelengths). The PDL targets scar hypervascularity, the 1550 nm erbium:glass stimulates collagen remodelling and the 1927 nm thulium targets epidermal processes, particularly hyperpigmentation. This combination addresses scar thickness, texture and colour with a low side effect profile and is particularly advantageous in patients at higher risk of post-procedure hyperpigmentation. Our cases suggest the combination of 595nm PDL plus NAFL 1550 nm erbium:glass/1927 nm thulium device is effective and well-tolerated for burn scar treatment in skin of colour.

  7. Prospective Evaluation of the Safety and Efficacy of a 1060-nm Large Spot Size, Vacuum-Assisted Hair Removal Diode Laser System in Asian/Pacific Fitzpatrick's Skin Types IV-V Patients.

    Tahiliani, Sushil T; Tahiliani, Harsh S

    2016-11-01

    Laser-based photoepilation of dark skin types demands a delicate combination of appropriate light wavelengths and spot size to achieve optimal epidermal-to-follicular energy absorption ratios. This prospective study assessed the axillary, arm, thigh, and back hair clearing ef cacy of the LightSheer In nity 1060 nm diode laser in 10 Fitzpatrick skin type IV-V patients. Each area was treated up to ve times, at 4-6-week intervals, after which immediate skin responses and adverse events were recorded. Hair count, color and coarseness were assessed before each treatment session, as well as 1, 3, and 6 months following the last session. Both patients and the treating physician rated the degree of improvement with time, and patients also ranked their satisfaction with the treatment outcome. Percent hair reduction from baseline gradually increased with treatment and peaked at 74.6%, 68.4%, and 65.7% for axillary, arm and thigh regions, respectively, 6 months following the last treatment session. Baseline hair growth patterns precluded effective selection of a representative area for hair counting. Patients satisfaction was consistently higher for axillary hair clearance rates, followed by thigh and arm responses. Throughout the follow-up period, the investigator rated 50-67% of the treated axillae as presenting "good" or "very good" hair clearance, and provided similar ratings for 67% of the treated thigh regions at both the 1 and 6 month follow-up sessions. Immediate responses to treatment were mild to moderate and short-lived and no incidents of brosis or scarring were reported. Taken together, the LightSheer In nity 1060 HS Handpiece provided for an ideal ef cacy-safety balance in treating dark-skinned patients, providing for long-term hair clearance with minimal downtime. J Drugs Dermatol. 2016;15(11):1427-1434.

  8. Totally James

    Owens, Tom

    2006-01-01

    This article presents an interview with James Howe, author of "The Misfits" and "Totally Joe". In this interview, Howe discusses tolerance, diversity and the parallels between his own life and his literature. Howe's four books in addition to "The Misfits" and "Totally Joe" and his list of recommended books with lesbian, gay, bisexual, transgender,…

  9. Minimal erythema dose and minimal melanogenesis dose relate better to objectively measured skin type than to Fitzpatricks skin type

    Wulf, Hans Christian; Philipsen, Peter A; Ravnbak, Mette H

    2010-01-01

    Fitzpatrick skin type (FST I-IV) is a subjective expression of ultraviolet (UV) sensitivity based on erythema and tanning reactivity after a single exposure. Pigment protection factor (PPF) is an objective measurement of skin sensitivity in all skin types after a single exposure....

  10. How James Kept the Pace?; A Look into the Organic Unity of "Daisy Miller"

    Movaghati, Sina; Comcar, Milad

    2015-01-01

    Many Critics believe that Henry James has set the definitive standards of modern fiction writing. Undoubtedly his groundbreaking article "The Art of Fiction," which published for the first time in 1884, has a major contribution in developing the theories of fiction writing. The term Organic Unity has derived from a major Formalist…

  11. James Edward Scott: The Leadership Journey of a Senior-Level African American Student Affairs Officer

    Willis, Salatha T.

    2013-01-01

    The purpose of this study was to examine, understand, and describe the life, leadership, and influence of Dr. James Edward Scott on higher education and more specifically student affairs; as one of the most well-known and respected African American male chief student affairs officers in the late 20th and early 21st centuries. Using a qualitative…

  12. Media, Digital Technology and Learning in Sport: A Critical Response to Hodkinson, Biesta and James

    Enright, Eimear; Gard, Michael

    2016-01-01

    Background: In their 2008 paper, Hodkinson, Biesta and James draw on the sociological theories of Pierre Bourdieu to construct what they claim is a "holistic" theoretical framework for understanding learning. While not an attempt to dissolve the long-standing opposition between "cognitive" and "situated" theories, the…

  13. Socioeconomic impacts of nuclear generating stations: Nine Mile Point and Fitzpatrick case study. Technical report 1 Oct 78-4 Jan 82

    Branch, K.; Cochran, R.; Meale, R.

    1982-07-01

    The report documents a case study of the socioeconomic impacts of the construction and operation of the Nine Mile Point and Fitzpatrick nuclear power stations. It is part of a major post-licensing study of the socioeconomic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period, 1980-81. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socioeconomic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

  14. Modification of the Fitzpatrick system of skin phototype classification for the Indian population, and its correlation with narrowband diffuse reflectance spectrophotometry.

    Sharma, V K; Gupta, V; Jangid, B L; Pathak, M

    2018-04-01

    The Fitzpatrick classification for skin phototyping is widely used, but its usefulness in dark-skinned populations has been questioned by some researchers. Recently, skin colour measurement has been proposed for phototyping skin colour objectively. To modify the Fitzpatrick system of skin phototyping for the Indian population and to study its correlation with skin colour using narrowband diffuse reflectance spectrophotometry METHODS: Answer choices for three items (eye colour, hair colour, colour of unexposed skin) out of 10 in the original Fitzpatrick questionnaire were modified, followed by self-administration of the original and the modified Fitzpatrick questionnaire by 70 healthy Indian volunteers. Skin colour (melanin and erythema indices) was measured from two photoexposed and two photoprotected sites using a narrowband reflectance spectrophotometer. The mean ± SD scores for the original and modified Fitzpatrick questionnaires were 25.40 ± 4.49 and 23.89 ± 4.82, respectively (r = 0.97, P Spectrophotometry can be a useful objective tool for skin phototyping. © 2018 British Association of Dermatologists.

  15. A Case of Swyer-James (Macleod’s Syndrome with Bilateral Involvement

    Ömer Özbudak

    2005-01-01

    Full Text Available Swyer-James (Macleod’s syndrome (SJMS is a rare disorder thought to be a complication of childhood infections. Unilateral hyperlucency, reduced lung volume, diminished vascular markings and bronchiectasis may be detected on radiological analysis. Bilateral involvement is rare. We present a 20-yearl-old man who was diagnosed as having bilateral SJMS by radiological analysis and ventilation-perfusion scintigraphy.

  16. Television as a tool for promoting Nigerian culture | James ...

    The need for cultural preservation and cultural identity among nations has become an important consideration in this age of globalization. Today, the world has not only become a global village, but a global bedroom. With the tremendous development of the communication and information sectors, particular attention has ...

  17. James A. Van Allen: The Trip to Jupiter

    Jacobsen, Sally

    1973-01-01

    Discusses the research purposes and activities of the Pioneer mission, including the instruments used, data on Jupiter's radiation belt, and information about cosmic ray intensity. Included is a description of the scientist's view about the value of the space program. (CC)

  18. Reading and Theorizing James Baldwin: A Bibliographic Essay

    Conseula Francis

    2015-09-01

    Full Text Available Readers and critics alike, for the past sixty years, generally agree that Baldwin is a major African-American writer. What they do not agree on is why. Because of his artistic and intellectual complexity, Baldwin’s work resists easy categorization and Baldwin scholarship, consequently, spans the critical horizon. This essay provides an overview of the three major periods of Baldwin scholarship. 1963–73 is a period that begins with the publication of The Fire Next Time and sees Baldwin grace the cover of Time magazine. This period ends with Time declaring Baldwin too passé to publish an interview with him and with critics questioning his relevance. The second period, 1974–87, finds critics attempting to rehabilitate Baldwin’s reputation and work, especially as scholars begin to codify the African-American literary canon in anthologies and American universities. Finally, scholarship in the period after Baldwin’s death takes the opportunity to challenge common assumptions and silences surrounding Baldwin’s work. Armed with the methodologies of cultural studies and the critical insights of queer theory, critics set the stage for the current Baldwin renaissance.

  19. James Watt's Leicester Walk

    Bell, Kathleen

    2016-01-01

    a poem in which James Watt, inventor of the separate condenser, walks through contemporary Leicester (his route is from Bonners Lane and alongside the canal, taking in the Statue of Liberty on its traffic island near Sage Road). It is derived from the exercise of taking a character for a walk,

  20. How James Wood Works

    Goldstein, Evan R., Comp.

    2008-01-01

    Reading through news-media clippings about James Wood, one might reasonably conclude that "pre-eminent critic" is his official job title. In fact, Wood is a staff writer for "The New Yorker" and a professor of the practice of literary criticism at Harvard University. But at a time when there is much hand-wringing about the death of the…

  1. William James on a phenomenological psychology of immediate experience: the true foundation for a science of consciousness?

    Taylor, Eugene

    2010-01-01

    Throughout his career, William James defended personal consciousness. In his "Principles of Psychology" (1890), he declared that psychology is the scientific study of states of consciousness as such and that he intended to presume from the outset that the thinker was the thought. But while writing it, he had been investigating a dynamic psychology of the subconscious, which found a major place in his Gifford Lectures, published as "The Varieties of Religious Experience" in 1902. This was the clearest statement James was able to make before he died with regard to his developing tripartite metaphysics of pragmatism, pluralism and radical empiricism, which essentially asked "Is a science of consciousness actually possible?" James's lineage in this regard, was inherited from an intuitive psychology of character formation that had been cast within a context of spiritual self-realization by the Swedenborgians and Transcendentalists of New England. Chief among these was his father, Henry James, Sr., and his godfather, Ralph Waldo Emerson. However, james was forced to square these ideas with the more rigorous scientific dictates of his day, which have endured to the present. As such, his ideas remain alive and vibrant, particularly among those arguing for the fusion of phenomenology, embodiment and cognitive neuroscience in the renewed search for a science of consciousness.

  2. Rotating reactors : a review

    Visscher, F.; Schaaf, van der J.; Nijhuis, T.A.; Schouten, J.C.

    2013-01-01

    This review-perspective paper describes the current state-of-the-art in the field of rotating reactors. The paper has a focus on rotating reactor technology with applications at lab scale, pilot scale and industrial scale. Rotating reactors are classified and discussed according to their geometry:

  3. Hydrological functions of a mine-impacted and natural peatland-dominated watershed, James Bay Lowland

    Leclair, Melissa; Whittington, Pete; Price, Jonathan

    2015-01-01

    Study region: This study was conducted in Northern Ontario, Canada, in the middle of the Hudson-James Bay. Lowland: one of the world’s largest wetland complexes. Study focus: Northern latitudes are expected to be the most impacted by climate change in the next century and adding to this stressor are increased mineral exploration activities, such as the De Beers Victor Mine, a large open-pit diamond mine. Because of the extremely low relief and presence of marine sediments, horizontal runof...

  4. Making James Joyce’s life into a graphic novel. An interview with Alfonso Zapico

    Carlos Menéndez Otero

    2014-03-01

    Full Text Available Alfonso Zapico was born in Blimea, Asturias, Spain, in 1981.He started working as a professional illustrator and cartoonist in 2006 and has since published four graphic novels: La guerre du professeur Bertenev (2006, set in the Crimean War; Café Budapest (2008, about the Israeli-Palestinian conflict; Dublinés (2011, a biography of James Joyce, and  La ruta Joyce (2011, a kind of ‘making of’ of Dublinés. His works have received several prestigious awards and been published in Spain, France, Belgium, Switzerland, Poland, Germany and Ireland, where The O’Brien Press released the English version of Dublinés, James Joyce. Portrait of a Dubliner, in May 2013. Just a few days before, the Niemeyer Center in Avilés, Asturias, opened Pasos encontrados. Un viaje dibujado de Alfonso Zapico, an exhibition focused on his career and, more particularly, on Dublinés and La ruta Joyce. He will soon be publishing his fifth graphic novel, El otro mar, about Vasco Núñez de Balboa and the expedition that led to the European discovery of the Pacific Ocean in 1513.We interviewed Zapico at the Niemeyer Center on June 29th, 2013.

  5. EARP [environmental assessment and review process] and the aboriginal women of James Bay: A structural bias?

    Hawkes, S.

    1993-07-01

    The massive James Bay hydroelectric development project in northern Quebec is studied to explore the themes of the impact on women of rapid resource development projects and the process of environmental assessment of such projects, particularly as it relates to aboriginal peoples. Field surveys were conducted in the Cree community of Fort George, now relocated to Chisasibi as a result of hydroelectric development on the LaGrande River. The surveys examined the kinds of social impacts, the impacts (if any) that were particular to women, the degree of gender bias in Cree society which may have affected those impacts and the participation of women in the environmental assessment process, and the possibility of a bias against women in the environmental assessment process. A number of direct and indirect social effects of the James Bay developments were identified, but the extent to which women and men experienced different impacts, or to which they experienced the same impacts differently, was not entirely clear. It is concluded that the original question of bias against women needs to be reframed: whether the environmental assessment process is adequate to address the range of indirect social impacts which accrue to many social sectors, including youths, elders, men, and women. It is then concluded that the process is not adequate, and a number of recommendations are offered which may help to facilitate cross-cultural impact assessment. 35 refs

  6. An interview with James Briscoe.

    Brown, Katherine

    2018-03-27

    James Briscoe is a group leader at The Francis Crick Institute in London. His lab's research focusses on the developing vertebrate spinal cord, with a particular interest in how sonic hedgehog gradients, and the downstream signal transduction and transcriptional networks, regulate the development of this tissue. In September 2018, James will become the new Editor-in-Chief of Development. We met with James to discuss his career and research interests, the importance of interdisciplinary thinking in developmental biology, and his views on the current state and future opportunities in scientific publishing. © 2018. Published by The Company of Biologists Ltd.

  7. Farewell to a reactor

    Skanborg, P.

    1976-01-01

    Denmark's second reactor, DR 2, whose first criticality took place the night of 18/19 December 1958 was shut down for the last time on 31 October 1975. It was a light-water moderrated and cooled reactor of swimming-pool type with a thermal power of 5 MW, using 90% enriched uranium. The operation is described. The reactor and auxiliary equipment are now being put 'in store' - all fuel elements sent for reprocessing, the reactor tank and cooling circuits emptied, and a lead shielding placed over the tank opening. The rest of the equipment will remain in place. (B.P.)

  8. I've Got a Testimony: James Baldwin and the Broken Silences of Black Queer Men

    McKinley E Melton

    2016-12-01

    Full Text Available James Baldwin writes within and against the testimonial tradition emerging from the Black Church, challenging the institution’s refusal to acknowledge the voices and experiences of black queer men. Baldwin’s autobiographical novel, Go Tell It on the Mountain, creates a space for Baldwin’s testimony to be expressed, and also lays the foundation for a tradition of black queer artists to follow. In the contemporary moment, poet Danez Smith inhabits Baldwin’s legacy, offering continuing critiques of the rigidity of conservative Christian ideologies, while publishing and performing poetry that gives voice to their own experiences, and those of the black queer community at large. These testimonies ultimately function as a means of rhetorical resistance, which not only articulates black queer lives and identities, but affirms them.

  9. Research priorities in mesothelioma: A James Lind Alliance Priority Setting Partnership.

    Stephens, R J; Whiting, C; Cowan, K

    2015-08-01

    In the UK, despite the import and use of all forms of asbestos being banned more than 15 years ago, the incidence of mesothelioma continues to rise. Mesothelioma is almost invariably fatal, and more research is required, not only to find more effective treatments, but also to achieve an earlier diagnosis and improve palliative care. Following a debate in the House of Lords in July 2013, a package of measures was agreed, which included a James Lind Alliance Priority Setting Partnership, funded by the National Institute for Health Research. The partnership brought together patients, carers, health professionals and support organisations to agree the top 10 research priorities relating to the diagnosis, treatment and care of patients with mesothelioma. Following the established James Lind Alliance priority setting process, mesothelioma patients, current and bereaved carers, and health professionals were surveyed to elicit their concerns regarding diagnosis, treatment and care. Research questions were generated from the survey responses, and following checks that the questions were currently unanswered, an interim prioritisation survey was conducted to identify a shortlist of questions to take to a final consensus meeting. Four hundred and fifty-three initial surveys were returned, which were refined into 52 unique unanswered research questions. The interim prioritisation survey was completed by 202 responders, and the top 30 questions were taken to a final meeting where mesothelioma patients, carers, and health professionals prioritised all the questions, and reached a consensus on the top 10. The top 10 questions cover a wide portfolio of research (including assessing the value of immunotherapy, individualised chemotherapy, second-line treatment and immediate chemotherapy, monitoring patients with pleural thickening, defining the management of ascites in peritoneal mesothelioma, and optimising follow-up strategy). This list is an invaluable resource, which should be

  10. A Political Case of Penetrating Cranial Trauma: The Injury of James Scott Brady.

    Menger, Richard; Kalakoti, Piyush; Hanif, Rimal; Ahmed, Osama; Nanda, Anil; Guthikonda, Bharat

    2017-09-01

    James Brady, the White House press secretary during President Ronald Reagan's first term in office, was 1 of 4 people (including the President) wounded during an attempted assassination attempt on President Reagan's life on March 30, 1981. John Hinckley, Jr. was found not guilty of this attempt by reason of insanity. The assassination attempt was a ploy by Hinckley, Jr. to impress the actress Jodie Foster. Brady was the most seriously injured of the 4 who were wounded. He suffered a gunshot wound to the left forehead that traveled through the left frontal lobe, corpus callosum, and then into the right frontal and temporal lobes. He initially required a bifrontal craniotomy for evacuation of a right frontotemporal intraparenchymal hemorrhage and debridement of tract. His postoperative course was complicated by seizures, cerebrospinal fluid leakage (necessitating multiple reparative procedures), aspiration pneumonia, and pulmonary emboli. Despite the severity of his injury and perioperative morbidities, Mr. Brady made good recovery. Although permanently left with residual weakness on the left side of his body, making a wheelchair necessary, Brady maintained cognitive and personality traits that were very close to his preinjury baseline. As a result, James Brady and his wife, Sarah, led a call to create legislative reform subsequently known as the "Brady Bill." This bill controversially made mandatory background checks for the purchase of firearms from licensed dealers. Our work aims to describe the assassination attempt, the neurosurgical injury and management of Mr. Brady's case, and the brief historical sequel that followed. Copyright © 2017 by the Congress of Neurological Surgeons.

  11. Application of Molecular Adsorber Coatings in Chamber A for the James Webb Space Telescope

    Abraham, Nithin S.

    2017-01-01

    As a coating made of highly porous zeolite materials, the Molecular Adsorber Coating (MAC) was developed to capture outgassed molecular contaminants, such as hydrocarbons and silicones. For spaceflight applications, the adsorptive capabilities of the coating can alleviate on-orbit outgassing concerns on or near sensitive surfaces and instruments within the spacecraft. Similarly, this sprayable paint technology has proven to be significantly beneficial for ground-based space applications, in particular, for vacuum chamber environments. This presentation describes the application of the MAC technology for the James Webb Space Telescope (JWST) at NASA Johnson Space Center (JSC). The coating was used as a mitigation tool to entrap outgassed contaminants, specifically silicone-based diffusion pump oil, from within JSCs cryogenic optical vacuum chamber test facility called Chamber A. This presentation summarizes the background, fabrication, installation, chemical analysis test results, and future plans for the MAC technology, which was effectively used to protect the JWST test equipment from vacuum chamber contamination. As a coating made of highly porous zeolite materials, the Molecular Adsorber Coating (MAC) was developed to capture outgassed molecular contaminants, such as hydrocarbons and silicones. For spaceflight applications, the adsorptive capabilities of the coating can alleviate on-orbit outgassing concerns on or near sensitive surfaces and instruments within the spacecraft. Similarly, this sprayable paint technology has proven to be significantly beneficial for ground-based space applications, in particular, for vacuum chamber environments. This presentation describes the application of the MAC technology for the James Webb Space Telescope (JWST) at NASA Johnson Space Center (JSC). The coating was used as a mitigation tool to entrap outgassed contaminants, specifically silicone-based diffusion pump oil, from within JSCs cryogenic optical vacuum chamber test

  12. Discovering and Developing Successful Cardiovascular Therapeutics: A Conversation With James N. Topper, MD, PhD.

    Topper, James N; Rutherford, John D

    2016-11-15

    Dr James (also known as Jamie) N. Topper, MD, PhD, serves as Managing General Partner at Frazier Healthcare Partners, where he leads the Life Science Venture practice. In 2011, and 2016, he was named to the Midas List of leading venture capitalists, and, in 2013, he was recognized by Forbes as one of the top 10 healthcare investors. He has >25 years of experience working with entrepreneurs to found and build successful therapeutics-focused companies. Dr Topper holds a BS from the University of Michigan. He received an MD and PhD (in biophysics) from Stanford University School of Medicine. He completed postgraduate training in internal medicine and cardiovascular disease at the Brigham and Women's Hospital in Boston and is board certified in both disciplines. © 2016 American Heart Association, Inc.

  13. A nuclear power reactor

    Borrman, B.E.; Broden, P.; Lundin, N.

    1979-12-01

    The invention consists of shock absorbing support beams fastened to the underside of the reactor tank lid of a BWR type reactor, whose purpose is to provide support to the steam separator and dryer unit against accelerations due to earthquakes, without causing undue thermal stresses in the unit due to differential expansion. (J.I.W.)

  14. Ecrire et souffrir : L’inspiration partagée de Constance Fenimore Woolson et de Henry James Literature and Grief: Constance Fenimore Woolson and Henry James, A Common Inspiration

    Jeannine Hayat

    2007-01-01

    Full Text Available Miss Grief is a story by Constance Fenimore Woolson, an American novelist who often wrote about the difficulty a woman had in becoming an artist — a writer or a painter — in the nineteenth century. This tale is a very strange text, a kind of anticipation of a meeting to come, in Italy, in 1880, between Woolson and Henry James, and a friendship which lasted until the former’s death in 1894. For thirteen years, both writers would share a common inspiration. Death itself could not break the links between the two authors, who were connected even when settled in different European countries. William James, who was a member of the American Society for Psychical Research, probably helped his brother Henry to communicate — or so it appears — in some way with Woolson, even after her fatal accident, or possible suicide, in Venice. Henry James probably had in mind Miss Grief, a story by his dead friend, before writing some of his books. Indeed, Woolson had been the first to develop the image of “the figure in the carpet,” which was later transformed by Henry James. Woolson was also the first to devise a plot which Henry James would later use as a canvas for his novel The Wings of the Dove. What is an author and what is authorship? It seems impossible to separate what is Woolson’s and what is Henry James’s in four works of fiction that are in fact to be read together : Miss Grief, The Figure in the Carpet, The Beast in the Jungle, The Wings of the Dove.

  15. Research priorities by professional background - A detailed analysis of the James Lind Alliance Priority Setting Partnership.

    Arulkumaran, Nishkantha; Reay, Hannah; Brett, Stephen J

    2016-05-01

    The Intensive Care Foundation, in partnership with the James Lind Alliance, has supported a national project to identify and prioritise unanswered questions about adult intensive care that are important to people who have been critically ill, their families, and the health professionals who care for them. We conducted a secondary analysis to explore differences in priorities determined by different respondent groups in order to identify different groups' perceptions of gaps in knowledge. There were two surveys conducted as part of the original project. Survey 1 comprised a single open question to identify important research topics; survey 2 aimed to prioritise these topics using a 10-point Likert scale. In survey 1, despite clear differences in suggestions amongst the respondent groups, themes of comfort/communication and post-ICU rehabilitation were the within the top 2 suggestions across all groups. Patients and relatives suggested research topics to which they could easily relate, whereas there was a greater breadth of suggestions from clinicians. In survey 2, the number of research priorities that received a mode score of 10 varied from 1 to 36. Patients scored 36 out of the 37 topics with a mode score of 10. All other groups scored topics with more discrimination, with the number of topics with a mode score of 10 ranging from 1 to 20. Differences in the proportions of the representative groups are therefore unlikely to have translated to an impartial conclusion. Clinicians, patients, and family members have jointly identified the research priorities for UK ICM practice.

  16. Reactor coolant pump for a nuclear reactor

    Burkhardt, W.; Richter, G.

    1976-01-01

    An improvement is proposed concerning the easier disengagement of the coupling at the reactor coolant pump for a nuclear reactor transporting a pressurized coolant. According to the invention the disengaging coupling consists of two parts separated by screws. At least one of the screws contains a propellent charge ananged within a bore and provided with a speed-dependent ignition device in such a way that by separation of the screws at overspeeds the coupling is disengaged. The sub-claims are concerned with the kind of ignition ot the propellent charge. (UWI) [de

  17. Evolution of clinical research: A history before and beyond james lind

    Arun Bhatt

    2010-01-01

    Full Text Available The evolution of clinical research traverses a long and fascinating journey. From the first recorded trial of legumes in biblical times to the first randomized controlled of trial of streptomycin in 1946, the history of clinical trial covers a wide variety of challenges - scientific, ethical and regulatory. The famous 1747 scurvy trial conducted by James Lind contained most elements of a controlled trial. The UK Medical Research Council′s (MRC trial of patulin for common cold in 1943 was the first double blind controlled trial. This paved the way for the first randomized control trial of streptomycin in pulmonary tuberculosis carried out in 1946 by MRC of the UK. This landmark trial was a model of meticulousness in design and implementation, with systematic enrolment criteria and data collection compared with the ad hoc nature of other contemporary research. Over the years, as the discipline of controlled trials grew in sophistication and influence, the streptomycin trial continues to be referred to as ground breaking. The ethical advances in human protection include several milestones - Nuremberg Code, Declaration of Helsinki, Belmont Report, and 1996, International Conference on Harmonization Good Clinical Practice guidance. In parallel to ethical guidelines, clinical trials started to become embodied in regulation as government authorities began recognizing a need for controlling medical therapies in the early 20th century. As the scientific advances continue to occur, there will be new ethical and regulatory challenges requiring dynamic updates in ethical and legal framework of clinical trials.

  18. Reactor building for a nuclear reactor

    Haidlen, F.

    1976-01-01

    The invention concerns the improvement of the design of a liner, supported by a latticed steel girder structure and destined for guaranteeing a gastight closure for the plant compartments in the reactor building of a pressurized water reactor. It is intended to provide the steel girder structure on their top side with grates, being suited for walking upon, and to hang on their lower side diaphragms in modular construction as a liner. At the edges they may be sealed with bellows in order to avoid thermal stresses. The steel girder structure may at the same time serve as supports for parts of the steam pipe. (RW) [de

  19. Proportional Systems in the History of Architecture: A Conversation with James S. Ackerman

    Matthew A Cohen

    2014-06-01

    Full Text Available In November 2010, James S. Ackerman, today the only living participant of the conference ‘De divina proportione’, which was held in Milan in 1951, sat for a video interview that was later shown at the conference ‘Proportional Systems in the History of Architecture’ in Leiden in 2011 to mark the sixtieth anniversary of the Milan conference. In this interview, conducted by Matthew A. Cohen, Ackerman discusses how the study of proportional systems has changed over the past six decades, and thereby provides a unique link between the two conferences. The interview begins with Ackerman’s experiences in northern Italy at the close of World War II, and a few years later at the Milan conference. It considers prevailing twentieth-century attitudes toward proportion up to the time of the conference, and compares them with prevailing medieval and Renaissance attitudes. Ackerman then shares his thoughts on the works and legacies of Rudolf Wittkower, Le Corbusier and Colin Rowe, before exploring the influences of architectural proportional theory on architectural design, and possible relationships between proportional systems and architectural beauty. After exploring changes in the uses of proportional systems that accompanied the rise of Abstract Expressionism, the arc of the interview concludes with Ackerman’s thoughts about the future of proportional systems in light of the evolving role of the computer in architectural practice today.

  20. Feedback stabilization of the resistive shell mode in a tokamak fusion reactor

    Fitzpatrick, R.

    1997-01-01

    Stabilization of the 'resistive shell mode' is vital to the success of the 'advanced tokamak' concept. The most promising reactor relevant approach is to apply external feedback using, for instance, the previously proposed 'fake rotating shell' scheme [R. Fitzpatrick and T. H. Jensen, Phys. Plasmas 3, 2641 (1996)]. This scheme, like other simple feedback schemes, only works if the feedback controlled conductors are located inside the 'critical radius' at which a perfectly conducting shell is just able to stabilize the ideal external kink mode. In general, this is not possible in a reactor, since engineering constraints demand that any feedback controlled conductors be placed outside the neutron shielding blanket (i.e., relatively far from the edge of the plasma). It is demonstrated that the fake rotating shell feedback scheme can be modified so that it works even when the feedback controlled conductors are located well beyond the critical radius. The gain, bandwidth, current, and total power requirements of such a feedback system for a reactor sized plasma are estimated to be less than 100, a few Hz, a fews tens of kA, and a few MW, respectively. These requirements could easily be met using existing technology. It is concluded that feedback stabilization of the resistive shell mode is possible in a tokamak fusion reactor. copyright 1997 American Institute of Physics

  1. 47 A DISCUSSION OF JAMES 1: 27 AND ITS IMPACT ON ...

    HP

    Christ as one's personal Saviour, trust in the life, death and resurrection of Jesus .... who began their work of evangelization in 1834, and the Bremen Mission ... the fundamental principles of the Christian faith to the culture and needs of the ... James' notion of pure Christianity or religion seems to be somewhat different.

  2. A multi-purpose reactor

    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)

  3. A Jaguar is an Awful Cat”. Animals and Animal Metaphors in James M. Cain’s Novels

    Giulio Segato

    2018-02-01

    Full Text Available James M. Cain is often linked with hard-boiled writers such as Dashiell Hammett and Raymond Chandler. Actually, he wrote a different kind of novels, where there are no ‘private eye’ detectives and very few murders. Robert Polito describes them as Noir Novels, using a term normally associated with the famous Hollywood genre, because of their particular emphasis on psyche and drama issues – distinctive elements of the Film Noir Era.

  4. Payer Perspectives on PCSK9 Inhibitors: A Conversation with Stephen Gorshow, MD, and James T. Kenney, RPh, MBA.

    Mehr, Stanton R

    2016-02-01

    The new proprotein convertase subtilisin/kexin type 9 (PCSK9) inhibitors can have significant budget effects, depending on the breadth of the US Food and Drug Administration (FDA)'s approved labeling. American Health & Drug Benefits asked Stephen Gorshow, MD, Regional Medical Director, UnitedHealthcare, and James T. Kenney, RPh, MBA, Manager, Specialty and Pharmacy Contracts, Harvard Pilgrim Health Care, to participate in a teleconference to better understand how payers are approaching the management of these agents.

  5. From movement to pain: a tribute to professor James P. Lund.

    Westberg, Karl-Gunnar; McFarland, David; Kolta, Arlette; Stohler, Christian; Feine, Jocelyne; Woda, Alain

    2008-01-01

    This tribute article to Professor James P. Lund stems from 6 of the presentations delivered at the July 1, 2008, symposium that honored 3 "giants" in orofacial neuroscience: B. J. Sessle, A. G. Hannam, and J. P. Lund. It was noted that soon after his training as a dentist in Australia, Jim Lund became interested in research. At the time he decided to do a PhD, there was a lot of discussion about how rhythmic movements were programmed. The early belief, based on Sherrington's studies of motor systems, was that these movements were simply an alternating series of reflexes. In the late 1960s and early 1970s, some still shared this belief, whereas others favored Graham Brown's hypothesis that repetitive movements were centrally programmed and did not depend on reflexes triggered by sensory inputs. There was no strong evidence then for either scenario except for the rhythmic movements of respiration. Lund's pioneering work during his PhD proved the existence of a central pattern generator (CPG) for mastication in the brainstem. Since then he has been interested in understanding how CPGs function and how sensory feedback works to adjust the motor patterns that they produce. Sections in this tribute article to Lund are written by some of his close collaborators and reflect the evolution of his work throughout the years. The first 4 presentations in this article (by K.-G. Westberg, D. McFarland, A. Kolta, and C. Stohler) highlight various aspects of these interests, and the final 2 presentations (by J. Feine and A. Woda) focus especially on clinical aspects of Lund's interests. The last section of this article is a final commentary from Professor Lund.

  6. James Stevens / James Stevens ; interv. Tilman Baumgärtel

    Stevens, James

    2006-01-01

    Inglise disainerist James Stevensist (sünd. 1962) ja tema tegevusest. J. Stevens 2000. a. Amsterdamis tehtud intervjuus koos Jon Bainsi ja Kim Bulliga 1995. a. Londonis avatud Interneti-agentuurist Obsolete, 1996-2000 tegutsenud Interneti-kohvikust Backspace, mittekommertsiaalse juhtmeteta nerworki Consume.net rajamisest Londonis

  7. Method of operating a reactor

    Oosumi, Katsumi; Yamamoto, Michiyoshi.

    1980-01-01

    Purpose: To prevent stress corrosion cracking in the structural material of a reactor pressure vessel. Method: Prior to the starting of a reactor, the reactor pressure vessel is evacuated to carry out degassing of reactor water, and, at the same time, reactor water is heated. After reactor water is heated to a predetermined temperature, control rods are extracted to start nuclear heating. While the temperature of the reactor water is in a temperature range where elution of a metal which is a structural material of the reactor pressure vessel becomes vigorous and the sensitivity to the stress corrosion cracks increases, the reactor is operated at the maximum permissible temperature raising speed or maximum permissible cooling speed. (Aizawa, K.)

  8. Advanced reactors: A retrospective

    Starr, C.

    1989-01-01

    The objectives for nuclear power have always emphasized competitive costs, reliability, and public safety. During its initial two decades, the nuclear reactor program was enthusiastically and generously supported by the public, government, and industry. In the subsequent decades this external support was substantially eroded by the growing public fears of catastrophic accidents, poor economic performance of many nuclear plants, regulatory constraints, and a plethora of engineering issues disclosed by plant operations. The technical and institutional histories are discussed with particular relevance to their influence on the framework for future development of the several proposed advance reactors

  9. Nonablative Fractional Laser Resurfacing for Acne Scarring in Patients With Fitzpatrick Skin Phototypes IV-VI.

    Alexis, Andrew F; Coley, Marcelyn K; Nijhawan, Rajiv I; Luke, Janiene D; Shah, Sejal K; Argobi, Yahya A; Nodzenski, Michael; Veledar, Emir; Alam, Murad

    2016-03-01

    There is a paucity of studies investigating laser resurfacing in Fitzpatrick skin phototypes (SPT) IV to VI. To assess the efficacy and safety of fractional nonablative laser resurfacing in the treatment of acne scarring in patients with SPT IV to VI. The authors conducted a randomized, investigator-blinded and rater-blinded, split-face comparative study of adults with SPT IV to VI and facial acne scars treated with 2 different density settings and the same fluence. Quantitative global scarring grading system (QGSGS) scores were significantly improved from baseline at 16 and 24 weeks (p = .0277). Improvements in QGSGS scores after higher and lower density treatments were statistically similar (p = .96). The live-blinded dermatologist, the blinded dermatologist photoraters, and the patients rated scars as being significantly more improved by visual analog scale at weeks 16 and 24 compared with baseline (p skin types IV to VI. Self-limited postinflammatory hyperpigmentation was a common occurrence, especially with higher treatment densities.

  10. Decommissioning a nuclear reactor

    Montoya, G.M.

    1991-01-01

    The process of decommissioning a facility such as a nuclear reactor or reprocessing plant presents many waste management options and concerns. Waste minimization is a primary consideration, along with protecting a personnel and the environment. Waste management is complicated in that both radioactive and chemical hazardous wastes must be dealt with. This paper presents the general decommissioning approach of a recent project at Los Alamos. Included are the following technical objectives: site characterization work that provided a thorough physical, chemical, and radiological assessment of the contamination at the site; demonstration of the safe and cost-effective dismantlement of a highly contaminated and activated nuclear-fuelded reactor; and techniques used in minimizing radioactive and hazardous waste. 12 figs

  11. Fusion reactor development: A review

    Anon.

    1983-01-01

    This paper is a review of the current prospects for fusion reactor development based upon the present status in plasma physics research, fusion technology development and reactor conceptual design for the tokamak magnetic confinement concept. Recent advances in tokamak plasma research and fusion technology development are summarized. The direction and conclusions of tokamak reactor conceptual design are discussed. The status of alternate magnetic confinement concept research is reviewed briefly. A feasible timetable for the development of fusion reactors is presented

  12. ‘Two Minds With but a Single Thought’: W. T. Stead, Henry James, and the Zancig Controversy

    Paul Horn

    2013-04-01

    Full Text Available In 1906, two writers of disparate repute watched, and then wrote about a series of notorious performances by the London telepathists Julius and Agnes Zancig.One was W. T. Stead, the pugnacious purveyor of New Journalism and hugely influential in shaping public opinion; the other was Henry James, the author of a great number of highbrow, complex, and ultimately poorly selling works of prose fiction.James wrote in a letter of his impression of ‘the 'reality 'of their performance’ in the face of accusations of fraud based on a supposed ‘very wonderfully elaborated code of signalling’ between the pair.A persuasive factor was the rumour, told to him by the actor and theatre manager John Hare at a party, that Stead had proved the Zancigs’ telepathic powers during private tests at his own home.Stead published his own defence of the Zancigs in the 'Review of Reviews',' 'covering in detail their performance at the Alhambra Music Hall, and, indeed, the tests that seem likely to have been the subject of the gossip heard by James.What is especially remarkable about Stead’s article is that its description of the physical reality of telepathy is strikingly reminiscent of the instances of wordless communication that occur between the sensitive protagonists who populate James’s 'fin-de-siècle' novels.The aim of my paper is to use Stead’s and James’s shared interest in the Zancigs as a starting point from which to explore how the two writers’ authorial voices, ostensibly so different to each other, become closely imbricated as they converge on the topic of thought transference.In this way, I hope to show that in addition to the operation of rumour among their social milieu, Stead and James were connected by their appreciation of a more occulted form of communication, which would help define their apparently distinct contributions to 'fin-de-siècle' culture.

  13. Metagenomic analysis of planktonic microbial consortia from a non-tidal urban-impacted segment of James River.

    Brown, Bonnie L; LePrell, Rebecca V; Franklin, Rima B; Rivera, Maria C; Cabral, Francine M; Eaves, Hugh L; Gardiakos, Vicki; Keegan, Kevin P; King, Timothy L

    2015-01-01

    Knowledge of the diversity and ecological function of the microbial consortia of James River in Virginia, USA, is essential to developing a more complete understanding of the ecology of this model river system. Metagenomic analysis of James River's planktonic microbial community was performed for the first time using an unamplified genomic library and a 16S rDNA amplicon library prepared and sequenced by Ion PGM and MiSeq, respectively. From the 0.46-Gb WGS library (GenBank:SRR1146621; MG-RAST:4532156.3), 4 × 10(6) reads revealed >3 × 10(6) genes, 240 families of prokaryotes, and 155 families of eukaryotes. From the 0.68-Gb 16S library (GenBank:SRR2124995; MG-RAST:4631271.3; EMB:2184), 4 × 10(6) reads revealed 259 families of eubacteria. Results of the WGS and 16S analyses were highly consistent and indicated that more than half of the bacterial sequences were Proteobacteria, predominantly Comamonadaceae. The most numerous genera in this group were Acidovorax (including iron oxidizers, nitrotolulene degraders, and plant pathogens), which accounted for 10 % of assigned bacterial reads. Polaromonas were another 6 % of all bacterial reads, with many assignments to groups capable of degrading polycyclic aromatic hydrocarbons. Albidiferax (iron reducers) and Variovorax (biodegraders of a variety of natural biogenic compounds as well as anthropogenic contaminants such as polycyclic aromatic hydrocarbons and endocrine disruptors) each accounted for an additional 3 % of bacterial reads. Comparison of these data to other publically-available aquatic metagenomes revealed that this stretch of James River is highly similar to the upper Mississippi River, and that these river systems are more similar to aquaculture and sludge ecosystems than they are to lakes or to a pristine section of the upper Amazon River. Taken together, these analyses exposed previously unknown aspects of microbial biodiversity, documented the ecological responses of microbes to urban

  14. Reactor utilization, Annex A

    Martinc, R.; Stanic, A.

    1984-01-01

    Reactor was operated until August 1984 due to prohibition issued by the Ministry since the reactor does not have the emergency cooling system nor special filters in the ventilation system yet. This means that the operation plan was fulfilled by 69%. This annex includes detailed tables containing data about utilization of reactor experimental channels, irradiated samples, as well as interruptions of operation. Detailed data about reactor power during this period are shown as well

  15. Creating the Thermal Environment for Safely Testing the James Webb Space Telescope at the Johnson Space Center's Chamber A

    Homan, Jonathan L.; Lauterbach, John; Garcia, Sam

    2016-01-01

    Chamber A is the largest thermal vacuum chamber at the Johnson Space Center and is one of the largest space environment chambers in the world. The chamber is 19.8 m (65 ft) in diameter and 36.6 m (120 ft) tall and is equipped with cryogenic liquid nitrogen panels (shrouds) and gaseous helium shrouds to create a simulated space environment. The chamber was originally built to support testing of the Apollo Service and Command Module for lunar missions, but underwent major modifications to be able to test the James Webb Space Telescope in a simulated deep space environment. To date seven tests have been performed in preparation of testing the flight optics for the James Webb Space Telescope (JWST). Each test has had a uniquie thermal profile and set of thermal requirements for cooling down and warming up, controlling contamination, and releasing condensed air. These range from temperatures from 335K to 15K, with tight uniformity and controllability for maintining thermal stability and pressure control. One unique requirement for two test was structurally proof loading hardware by creating thermal gradients at specific temperatures. This paper will discuss the thermal requirements and goals of the tests, the original requirements of the chamber thermal systems for planned operation, and how the new requirements were met by the team using the hardware, system flexiblilty, and engineering creativity. It will also discuss the mistakes and successes to meet the unique goals, especially when meeting the thermal proof load.

  16. On a Vision to Educating Students in Sustainability and Design—The James Madison University School of Engineering Approach

    Olga Pierrakos

    2011-12-01

    Full Text Available In order for our future engineers to be able to work toward a sustainable future, they must be versed not only in sustainable engineering but also in engineering design. An engineering education must train our future engineers to think flexibly and to be adaptive, as it is unlikely that their future will have them working in one domain. They must, instead, be versatilists. The School of Engineering at James Madison University has been developed from the ground up to provide this engineering training with an emphasis on engineering design, systems thinking, and sustainability. Neither design nor sustainability are mutually exclusive, and consequently, an education focusing on design and sustainability must integrate these topics, teaching students to follow a sustainable design process. This is the goal of the James Madison University School of Engineering. In this paper, we present our approach to curricular integration of design and sustainability as well as the pedagogical approaches used throughout the curriculum. We do not mean to present the School’s model as an all or nothing approach consisting of dependent elements, but instead as a collection of independent approaches, of which one or more may be appropriate at another university.

  17. REHISTORIAR LA BIOÉTICA EN LATINOAMÉRICA: LA CONTRIBUCIÓN DE JAMES DRANE RE-HISTORIAR A BIOÉTICA NA AMÉRICA LATINA: A CONTRIBUIÇÃO DE JAMES DRANE REMAKING BIOETHICS' HISTORY IN LATIN AMERICA: JAMES DRANE'S CONTRIBUTION

    Fernando Lolas Stepke

    2005-01-01

    Full Text Available Este artículo presenta la persona y la obra de James Drane en su relación con la bioética en Latinoamérica. Tras un breve examen de su carrera y publicaciones, se destaca la creación de un centro de estudios en Edinboro University of Pennsylvania, legado de la filantropía de Russell B. Roth y su familia, que perpetuará el espíritu de interrogación libre y lealtad a sus principios que Drane ha mantenido a lo largo de su vidaEste artigo apresenta a pessoa e a obra de James Drane relacionada com a bioética na América Latina. Após um breve exame de sua carreira e publicações, destaca-se a criação de um centro de estudo na Edinboro Univerisity na Pensilvânia (EUA, legado da filantropia de Russell B. Roth e sua família. Este centro perpetuará o espírito de livre pensador e lealdade aos seus princípios que Drane tem defendido ao longo de sua vidaThis article presents the person and work of James Drane in their relation to bioethics in Latin America. After a brief analysis of his career and publications, the establishment of a study center at the Edinboro University of Pennsylvania is underscored, a legacy of the late Russell B. Roth and his family, which will perpetuate the spirit of free inquiry and loyalty to his principles that Drane has kept throughout his life

  18. Conference James F.Buckli

    Buckli,J

    1988-01-01

    L'association du personnel a le plaisir d'accueillir Mons. James F.Buckli, astronaute, né en 1947. Il a participé à la mission Space Lab D1 qui pour la première fois mettait 8 personnes sur orbite.L'ass.du pers. remercie aussi Gordon White(s) de la mission américaine d'avoir permis d'organiser cette conférence

  19. James Peacock, Understanding Paul Auster

    Chrysavgi Papayianni

    2011-10-01

    Full Text Available Paul Auster’s impressive gamut of work continues to incite fascination and controversy. Indeed, his compelling storytelling style taken together with his mixing of crime fiction and absurdism has made his readers and critics vacillate between praise and condemnation. James Peacock’s Understanding Paul Auster, sheds new light to otherwise obscure aspects of Auster’s novels, films, and other works undermining in this way the negative criticism of the past and thus creating a new appreciation fo...

  20. James Alfred Loader: ’n Huldeblyk aan ’n krities-solidêre profeet in die eties-teologiese tradisie/James Alfred Loader: A tribute to a critical-solidary prophet in the ethical theological tradition

    Andries G. van Aarde

    2013-11-01

    Full Text Available This article is the introduction to the James Alfred Loader Dedication. It consists of a tribute to Professor Loader’s academic contribution to Old Testament, Middle-Eastern religio-literary studies and the Rabbinical background of the Old- and New Testament. The article is modelled after the tribute published in German in the annual publication of the Evangelisch-Theologische Fakultät Wien (Vienna, Austria due to the honorary doctorate conferred on Professor Loader by the University of Pretoria (South Africa in 2009. The tribute is combined with a comprehensive curriculum vitae, in part written in German, Afrikaans and English, and consisting of referencing Professor Loader’s personal data, his role as minister of religion, his academic awards, participation in scholarly societies, professional academic positions, academic reviewing, editorial activity, presentation of academic papers and a list of publications.

  1. A nuclear reactor

    Keller, W.

    1974-01-01

    Between the steel pressure vessel of the pressurized water power reactor and the biological shield a gap is found which enables inspections as well as cooling by air or gas. Within the gap, fins are equally distributed around the circumference of the pressure vessel summing parallel to each other and to the longitudinal axis of the vessel or being inclined. The fins cross the gap for about 9/10. Each fin consists of a sectional bar supported with its foot on a girder. The girder has got a rectangular steel section of two sectional iron parts. Between one of the parts and a plate anchored in the biological shield a ceramic body is inserted as a heat insulation. A further heat insulation of aluminium foils connects the fins with each other and divides the gap into two concentric subspaces which can be streamed through by a gas having different temperatures. (DG) [de

  2. James Homer Wright: a biography of the enigmatic creator of the Wright stain on the occasion of its centennial.

    Lee, Robert E; Young, Robert H; Castleman, Benjamin

    2002-01-01

    James Homer Wright (1869-1928), the eldest son of a Pittsburgh glass merchant, was educated in Baltimore and practiced pathology in Boston from 1893 until his death in 1928. In 1896, when not quite 27 years old, he assumed directorship of the newly founded Pathology Laboratory at the Massachusetts General Hospital, a post he held for the next 30 years. He is remembered eponymously by the blood cell stain that bears his name and the Homer Wright pseudorosettes of neuroblastoma, but he made many additional contributions to pathology. These include the following: determination of the cellular lineage of multiple myeloma, identification of the megakaryocyte as the cell of origin of blood platelets, recognition of the cell of origin of the neuroblastoma, demonstration of spirochetes in syphilitic aneurysms of the aorta, and clarification of misconceptions about actinomycosis. Additionally, Wright coauthored, with Dr. Frank B. Mallory, the book Pathological Technique, which was a staple of laboratories for >40 years and exemplifies Wright's wide-ranging interests in, and contributions to, practical aspects of pathology including staining, culture and frozen section techniques, photography, and development of the rotary microtome. He received Honorary Doctor of Science Degrees from Harvard University, the University of Maryland (his alma mater), and the University of Missouri. He was the recipient of the Gross prize in 1905 for his publication on actinomycosis and the Boylston Medical Prize in 1908 for his discovery of the origin of platelets, and he was inducted into the American Academy of Arts and Sciences in 1915. Although shy and somewhat austere in the workplace, a different side was shown by his anonymously sending flowers to a young Norwegian opera singer whom he subsequently married. The pathology laboratories of the Massachusetts General Hospital were named the "James Homer Wright Pathology Laboratories" in 1956. Today James Homer Wright is remembered and

  3. Reactor

    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.)

  4. Using Repertory Grids to Explore Musical Skills and Attitudes in a Mature-Age Adult at the Early Stages of Learning for Self-Fulfilment: A Case Study of James

    Taylor, Angela

    2012-01-01

    Repertory grids were used as a research tool to explore 73-year-old James' musical development over two years. Choosing two music learning cultures for his instrumental learning, James learned the piano in a college workshop and the Appalachian dulcimer in his local folk group. There were clear changes in his musical skills and attitudes,…

  5. Reactor

    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. Beyond xeroderma pigmentosum: DNA damage and repair in an ecological context. A tribute to James E. Cleaver.

    Karentz, Deneb

    2015-01-01

    The ability to repair DNA is a ubiquitous characteristic of life on Earth and all organisms possess similar mechanisms for dealing with DNA damage, an indication of a very early evolutionary origin for repair processes. James E. Cleaver's career (initiated in the early 1960s) has been devoted to the study of mammalian ultraviolet radiation (UVR) photobiology, specifically the molecular genetics of xeroderma pigmentosum and other human diseases caused by defects in DNA damage recognition and repair. This work by Jim and others has influenced the study of DNA damage and repair in a variety of taxa. Today, the field of DNA repair is enhancing our understanding of not only how to treat and prevent human disease, but is providing insights on the evolutionary history of life on Earth and how natural populations are coping with UVR-induced DNA damage from anthropogenic changes in the environment such as ozone depletion. © 2014 The American Society of Photobiology.

  7. Temporal modulation visual fields, normal aging, Parkinson's disease and methyl-mercury in the James Bay Cree: a feasibility study

    Jocelyn Faubert

    2003-01-01

    Full Text Available We assessed temporal modulation visual fields (TMFs for 91 observers including controls, Parkinson patients and members of the James Bay Cree community of Northern Québec suspected of being chronically exposed to relatively low levels of methyl-mercury. The main goal was to establish the feasibility of using such procedures to rapidly evaluate visual function in a large field study with the James Bay Cree community. The results show clear normal aging effects on TMFs and the pattern of loss differed depending on the flicker rates used. Group data comparisons between the controls and the experimental groups showed significant effects only between the Cree and normal controls in the 40 to 49 year-old age category for the low temporal frequency condition (2 Hz. Examples of individual analysis shows a Cree observer with severe visual field constriction at the 2 Hz condition with a normal visual field at the 16 Hz condition and a reverse pattern was demonstrated for a Parkinson's patient where a visual field constriction was evident only for the 16 Hz condition. The general conclusions are: Such a technique can be used to evaluate the visual consequences of neuropathological disorders and it may lead to dissociation between certain neurotoxic and neurodegenerative effects depending on the parameters used; this technique can be used for a large field study because it is rapid and easily understood and performed by the subjects; the TMF procedure used showed good test-retest correlations; normal aging causes changes in TMF profiles but the changes will show different patterns throughout the visual field depending on the parameters used.

  8. Safety equipment in a reactor

    Shiratori, Hirozo; Ishiyama, Satoshi; Ugawa, Yukio.

    1976-01-01

    Object: To safely retain, even if fuel should be molten and flown through the bottom of a container in a reactor, the molten fuel to remove heat generation of the fuel to prevent occurrence of a critical trouble. Structure: A reactor container housing a core and coolant has thereunder a separation dome in a central portion thereof and a partitioning plate coaxially and circularly disposed in the periphery of the separation dome, with a tray formed of magnesium oxide being disposed. Further, a cooling path system is provided so as to surround the tray. The cooling path system and the reactor container are surrounded and protected by a reactor wall provided with heat insulating refractory bricks, a coolant pouring system extends through the reactor wall, and the coolant is supplied to the tray. (Furukawa, Y.)

  9. Confiabilidad y reproducibilidad de la escala de fototipos de Fitzpatrick antes y después de un ejercicio de estandarización clínica

    Guillermo Sánchez

    2008-12-01

    Full Text Available Introducción. La escala de fototipos de Fitzpatrick permite conocer la sensibilidad de la piel frente a la luz ultravioleta; una estimación confiable del fototipo permite establecer el verdadero riesgo de cáncer de piel de acuerdo con esta característica. Objetivo. Establecer si existen diferencias en la concordancia intraobservador e interobservador de dos dermatólogos que evalúan el fototipo utilizando la escala de Fitzpatrick, antes y después de un proceso de estandarización clínica. Materiales y métodos. Se realizó un estudio analítico de concordancia intraobservador e interobservador. La escala de fototipos de Fitzpatrick se estandarizó mediante la metodología de grupos focales. Para conocer el acuerdo intra e interobservador se utilizó el estadístico kappa ponderado. El efecto de la estandarización se midió mediante un contraste de hipótesis de igualdad de coeficientes kappa utilizando el estadístico de Wald, a través de la metodología de mínimos cuadrados ponderados. Resultados. Se incluyeron 155 pacientes mayores de 15 años evaluados en cuatro oportunidades, por dos observadores independientes. En la fase de pre-estandarización, el kappa ponderado interobservador basal fue de 0,31 y de 0,40 a las seis semanas. El kappa intraobservador A fue de 0,47 y el intraobservador B fue de 0,51. Después del proceso de estandarización, se obtuvo un kappa ponderado interobservador basal de 0,77, y de 0,82 a las seis semanas. Los coeficientes kappa intraobservador A y B fueron 0,78 y 0,82, respectivamente. Se establecieron diferencias estadísticamente significativas entre los coeficientes antes y después de la estandarización (p=0,000 en todas las comparaciones. Conclusiones. La escala de fototipos de Fitzpatrick posterior a un ejercicio de estandarización arroja resultados confiables, reproducibles y estables en el tiempo.

  10. Preparing the construction of a school reactor

    Matejka, K.

    1977-01-01

    The possibilities are discussed of teaching and training nuclear reactor operation and control, teaching experimental reactor physics and investigating reactor lattice parameters using a training reactor to be installed at the Faculty of Nuclear Science and Physical Engineering in Prague. Requirements are indicated for the reactor's technical design and the Faculty's possibilities to contribute to its construction. (J.B.)

  11. A technical-scientific production of James Prescott Joule: a reading from the epistemology of Ludwik Fleck

    Wellington Pereira de Queirós

    2014-03-01

    Full Text Available This paper aims an epistemologically analysis of the attempt of James Prescott Joule to replace the steam engine by the electric one. In this historical analysis, we use the epistemological categories: style of thinking, collective thinking, intercollective circulation of ideas and practices,Joule and other technicians in Machester received in that time financial incentives from governments and industry to replace the steam engine by the electric one, since it was in Manchester a culture of the technique of the accuracy and precision in which Joule was immersed, which allowed us to initially identify the styles of techniques thinking and experimental efficiency, However, Joule could not replace the steam engine by the electric; and the awareness of the problems faced by him, in the attempt to make such a substitution, led him to seek, through an intercollective circulation of ideas and practices, such as the studies of Faraday and Jacobi, a change of direction in his researches. According to our analysis, what happened was a change of style from a technical to a scientific thinking. In this sense, Joule began to investigate issues of a scientific nature, as the Joule’s effect and the mechanical equivalent of heat, which contributed significantly to the establishment of the principle of conservation of energy. We present here the contributions of this epistemological analysis to the discussion of questions of the nature of science in the basic education and for the training of physics teachers

  12. On Politics and Education Finance: A Bibliography of Joel S. Berke, James W. Guthrie, and Michael W. Kirst. Vance Bibliographies, Public Administration Series: Bibliography P-821.

    Quay, Richard H.

    A bibliography of Joel S. Berke, James W. Guthrie, and Michael W. Kirst on politics and educational finance is presented. Specific topics include the following: whether financial support of public schools should be assumed completely by states, school finance policies and practices, school finance reform versus the spending and tax limitation…

  13. From Performance to Decision Processes in 33 Years: A History of Organizational Behavior and Human Decision Processes under James C. Naylor.

    Weber

    1998-12-01

    For the past 33 years, Organizational Behavior and Human Decision Processes has thrived under a single editor. That editor, James C. Naylor, is retiring from his long stewardship. This article chronicles the course of the journal under Jim's direction and marks some of the accomplishments and changes over the past three decades that go to his credit. Copyright 1998 Academic Press.

  14. St. James marine terminal facility description

    1993-10-01

    The US Department of Energy (DOE) currently owns and operates a marine terminal on the west bank of the Mississippi River at St. James, Louisiana. The St. James facility was constructed by the Department to provide marine services associated with the fill and drawdown of the Strategic Petroleum Reserve (SPR) crude oil storage facilities located at Bayou Choctaw and Weeks Island, Louisiana. Although strategic to the mission of the SPR in the event of a national emergency, the St. James terminal is situated such that it has a high potential to also serve the commercial industry`s needs for crude oil terminalling and storage. The St. James terminal is located approximately 45 miles west of New Orleans and 30 miles southeast of Baton Rouge, and approximately 160 miles upstream from the mouth of the Mississippi River. Construction of the St. James terminal was initiated in 1978 and was completed in 1980. Since then, the terminal has received and transferred over 125 million barrels of crude oil to the SPR sites for storage. For crude oil distribution, the St. James terminal was connected to the neighboring LOCAP terminal by a 0.1 mile 36-inch pipeline in 1981 and to the Capline terminal by a 0.5 mile 30-inch pipeline in 1988. The terminal also has a 30-inch pipeline connection to the Koch oil terminal which was used for initial fill purposes; however, this pipeline has been disconnected and is currently inactive. A complete description of the St. James terminal facilities, operational capabilities, operational certifications, and future Government requirements are presented in Sections 2, 3, 4, and 5 respectively.

  15. Neutron source for a reactor

    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.)

  16. James Joyce, music and memory

    Brown, Katie

    2007-01-01

    This thesis, James Joyce, Music and Memory, explores the connection between music and Irish cultural memory in Joyce’s works from Chamber Music to the “pure music” of Finnegans Wake. Overall, it shows that Joyce’s ongoing desire to emulate musical forms must be seen in light of Joyce’s wish to come to terms with Irish cultural history, as these are the driving forces that bring about his changes in style. TARA (Trinity’s Access to Research Archive) has a robust takedown policy. Please cont...

  17. Who needs a small reactor?

    Wood, Janet.

    1991-01-01

    The opportunities and problems facing small reactors were debated at the Delhi seminar. It was established that these were markets where small reactors, producing heat as well as electricity, might be of use. Small combined heat and power reactors would be more useful in district heating than would large reactors, as their optimum heat production is in line with current district heating schemes. Most process heat requirements are below 900 o C and so may be provided by small nuclear plants. Several areas in electricity supply where small and medium sized reactors could find a market were also identified. Despite good reasons for favouring nuclear plants in these markets, such as no production of carbon dioxide, no need to use expensive oil or other scarce fossil fuels and flexibility, these are, however, disincentives to potential buyers. While serial production would decrease plant costs, the lead plants would bear heavy financial risks. Currently too many options in plant design make it difficult to present the advantages of small reactor technology. Siting reactors near centres of population would be problematical. The disposal of spent fuel and radioactive wastes would create problems in developing or non-nuclear countries. Over and above all these problems, however, was that of public acceptance. Some ways of overcoming these disincentives were discussed. (author)

  18. A community responds to collective trauma: an ecological analysis of the James Byrd murder in Jasper, Texas.

    Wicke, Thomas; Silver, Roxane Cohen

    2009-12-01

    The brutal murder of James Byrd Jr. in June 1998 unleashed a storm of media, interest groups, high profile individuals and criticism on the Southeast Texas community of Jasper. The crime and subsequent response-from within the community as well as across the world-engulfed the entire town in a collective trauma. Using natural disaster literature/theory and employing an ecological approach, Jasper, Texas was investigated via an interrupted time series analysis to identify how the community changed as compared to a control community (Center, Texas) on crime, economic, health, educational, and social capital measures collected at multiple pre- and post-crime time points between 1995 and 2003. Differences-in-differences (DD) analysis revealed significant post-event changes in Jasper, as well as a surprising degree of resilience and lack of negative consequences. Interviews with residents conducted between March 2005 and 2007 identified how the community responded to the crisis and augmented quantitative findings with qualitative, field-informed interpretation. Interviews suggest the intervention of external organizations exacerbated the severity of the events. However, using strengths of specific local social institutions-including faith based, law enforcement, media, business sector and civic government organizations-the community effectively responded to the initial threat and to the potential negative ramifications of external entities.

  19. Neuroblastoma - remembering the three physicians who described it a century ago: James Homer Wright, William Pepper, and Robert Hutchison

    Rothenberg, Alexis B.; Berdon, Walter E.; D'Angio, Giulio J.; Yamashiro, Darrell J.; Cowles, Robert A.

    2009-01-01

    Neuroblastoma is often widespread at the time of diagnosis. Three physicians between 1900 and 1910 played an important role in the pathologic definition of neuroblastoma and its route of spread in relation to the age of the patient. These findings eventually led to the advances in treatment and decreased morbidity of today. In 1910 James Homer Wright was the first to recognize the tumor as being of primitive neural cell origin, calling it neuroblastoma and emphasizing the bundle of cells termed rosettes. While Wright recognized the neural nature of the tumor, the authors of previous reports had described its two distinct patterns of spread. In 1901 William Pepper published a series of infants with massive hepatic infiltration associated with adrenal tumors without spread to bone, and in 1907 Robert Grieve Hutchison reported his experience with a similar pathologic process in older infants and children who had orbital and skull metastases. Wright's valuable unifying concept served to tie together the descriptions of Pepper and Hutchison. A century later the names of these physicians should be remembered - Wright, who defined the adrenal tumor as of primitive neural origin, Pepper for his clinically accurate report of massive liver involvement in the infant, and Hutchison for describing the propensity of the tumor to spread to bone in older children. (orig.)

  20. Brigadier General James Stevens Simmons (1890-1954), Medical Corps, United States Army: a career in preventive medicine.

    Marble, Sanders

    2012-02-01

    James Simmons began his career in the US Army as a laboratory officer and his assignments progressed into tropical medicine research. His interests and work evolved into preventive medicine (PM, as the Army termed public health), and he took both a PhD and a Doctorate in Public Health. As the Army's leading PM officer he was appointed head of PM in 1940 and guided the Army's PM effort through World War II. His responsibility ran from gas masks through healthy nutrition and occupational health to an enormous variety of diseases; by the war's end, the breadth and importance of PM was reflected in the Preventive Medicine Division, having fully one-sixth of all military personnel at the Surgeon General's Office. Simmons used his strong professional credentials to tap into civilian medicine for expertise the Army lacked and he established organizations that survive to this day. After retirement, he sought to expand the field of public health and raise another generation of public health physicians.

  1. “Talk of contracts”: Gift-giving vs. Reciprocity in James Joyce’s “A Mother”

    Raghinaru Camelia

    2014-12-01

    Full Text Available This essay measures the extent to which gift-giving fails in an economy of reciprocity. Reading James Joyce’s story “A Mother” in terms of Derrida’s notion of the gift as “absolute loss,” I consider the implications of an economy of loss for Joyce’s notion of sacrifice. Thus, I argue that the absence of an economy of sacrifice integrating “absolute loss” engenders the zero-sum game at the heart of Dubliners. I depart from other readings of the short story in the context of an economy based on the ideal of balanced reciprocity, since these versions deny the pure gratuity of gift in its connotations of sacrifice and loss. While such theories form a good starting point for analyzing the “moral economy” of Dubliners, they tend to overlook the fact that the only means to counteract the paralysis resulting from reciprocity is through the suspension of the economy of exchange.

  2. Utilization of research reactors - A global perspective

    Muranaka, R.G.

    1988-01-01

    This paper presents 1) a worldwide picture of research reactors, operable, shutdown, under construction and planned, 2) statistics on utilization of research reactors including TRIGA reactors, and 3) some results of a survey conducted during 1988 on the utilization of research reactors in developing Member States in the Asia-Pacific Region

  3. William James, Gustav Fechner, and Early Psychophysics

    Stephanie L. Hawkins

    2011-10-01

    Full Text Available American psychologist and philosopher William James devoted the entirety of his career to exploring the nature of volition, as expressed by such phenomena as will, attention, and belief. As part of that endeavor, James's unorthodox scientific pursuits, from his experiments with nitrous oxide and hallucinogenic drugs to his investigation of spiritualist mediums, represent his attempt to address the "hard problems" of consciousness for which his training in brain physiology and experimental psychology could not entirely account. As a student, James's reading in chemistry and physics had sparked his interest in the concepts of energy and force, terms that he later deployed in his writing about consciousness and in his arguments against philosophical monism and scientific materialism, as he developed his radically empiricist ideas privileging discontinuity and plurality. Despite James's long campaign against scientific materialism, he was, however, convinced of the existence of a naturalistic explanation for the more "wayward and fitful" aspects of mind, including transcendent experiences associated with hysteria, genius, and religious ecstasy. In this paper, I examine aspects of James's thought that are still important for contemporary debates in psychology and neuroscience: his "transmission theory" of consciousness, his ideas on the "knowing of things together," and, finally, the related concept of "the compounding of consciousness," which postulates the theoretical possibility for individual entities within a conscious system of thought to "know" the thoughts of others within the system. Taken together, these ideas suggest that James, in spite of, or perhaps because of, his forays into metaphysics, was working toward a naturalistic understanding of consciousness, what I will term a "distributive model," based on his understanding of consciousness as an "awareness" that interacts dynamically within, and in relation to, its environment.

  4. The Rocky Horror (Picture Show: a Camp Parody of the Gothic between Mary Shelley, J. B. Priestley and James Whale

    Armando Rotondi

    2016-11-01

    Full Text Available Lo spettacolo teatrale The Rocky Horror Show (1973 di Richard O’Brien e, successivamente, l’adattamento cinematografico The Rocky Horror Picture Show (1975 di Jim Sharman possono essere considerate due pietre miliari del musical. Per temi e struttura, essi rappresentano la massima espressione della rivoluzione sessuale che va a cavalli tra gli anni '60 e '70 ed emblema del movimento di libertà sessuale. Il successo del musical risiede nella presa in giro degli stereotipi del gotico sia letterario che cinematografico, creando una enorme, irriverente parodia. Se il riferimento più evidente è il Frankenstein di Mary Shelley e la versione cinematografica di James Whale, meno analizzato è il rapporto con Benighted (1927 by John B. Priestley e la pellicola The Old Dark House (1932 sempre di Whale e adattata dal romanzo di Priestley. Proprio questa risulta, infatti, vera fonte di ispirazione per il lavoro di O’Brien, piuttosto che il Frankestein. Il contributo analizzerà questo rapporto, focalizzando la sua attenzione sugli elementi della “liturgia del Rocky Horror Show”, sui riferimenti in parodia e proponendo una visione dell’opera di O’Brien come una meta-aprodia.

  5. First a hero of science and now a martyr to science: the James Watson Affair - political correctness crushes free scientific communication.

    Charlton, Bruce G

    2008-01-01

    In 2007 James D. Watson, perhaps the most famous living scientist, was forced to retire from his position and retreat from public life in the face of international mass media condemnation following remarks concerning genetically-caused racial differences in intelligence. Watson was punished for stating forthright views on topics that elite opinion has determined should be discussed only with elaborate caution, frequent disclaimers, and solemn deference to the currently-prevailing pieties. James Watson has always struck many people as brash; however this blunt, truth-telling quality was intrinsic to his role in one of the greatest scientific discoveries. Much more importantly than 'good manners', Watson has consistently exemplified the cardinal scientific virtue: he speaks what he understands to be the truth without regard for the opinion of others. The most chilling aspect of the Watson Affair was the way in which so many influential members of the scientific research community joined the media condemnation directed against Watson. Perhaps the most egregious betrayal of science was an article by editorialists of the premier UK scientific journal Nature. Instead of defending the freedom of discourse in pursuit of scientific truth, Nature instead blamed Watson for being 'crass' and lacking 'sensitivity' in discussing human genetic differences. But if asked to choose between the 'sensitive' editors of Nature or the 'crass' genius of James D. Watson, all serious scientists must take the side of Watson. Because when a premier researcher such as Watson is hounded from office by a vicious, arbitrary and untruthful mob; all lesser scientists are made vulnerable to analogous treatment at the whim of the media. A zealous and coercive brand of 'political correctness' is now making the biological truth of human genetic differences intolerably difficult to discover and discuss in US and UK. This needs to change. My hope is that truth will prevail over political correctness and

  6. Reactor physics aspects of burning actinides in a nuclear reactor

    Hage, W.; Schmidt, E.

    1978-01-01

    A short review of the different recycling strategies of actinides other than fuel treated in the literature, is given along with nuclear data requirements for actinide build-up and transmutation studies. The effects of recycling actinides in a nuclear reactor on the flux distribution, the infinite neutron multiplication factor, the reactivity control system, the reactivity coefficients and the delayed neutron fraction are discussed considering a notional LWR or LMFBR as an Actinide Trasmutaton Reactor. Some operational problems of Actinide Transmutation reactors are mentioned, which are caused by the α-decay heat and the neutron sources of Actinide Target Elements

  7. Doctors, disease and James Joyce.

    Kaplan, Robert M

    2008-08-01

    The Irish author James Joyce is regarded as the greatest modernist writer of his time. His works, notably The Dead, A Portrait of the Artist as a Young Man, Ulysses and Finnegans Wake--are intensely autobiographic including meticulous descriptions of illness and states of health--no surprise in view of Joyce's medical history and hypochondria. The Dead revolves around the tragic love of a doomed tubercular youth. Ulysses has a graphic description of Mary Joyce-s death, a funeral and a birth; Stephen Dedalus, the character based on Joyce, attends a drinking session with medical students at the lying-in hospital just as Joyce had done as a student; references to syphilis, alcoholism and other illnesses abound.

  8. ATFSR: a small torsatron reactor

    Houlberg, W.A.; Lacatski, J.T.; Uckan, N.A.

    1985-01-01

    A small (average minor radius anti a approx. = 1 m), moderate-aspect-ratio torsatron reactor based on the Advanced Toroidal Facility (ATF) is proposed as a starting point for improved stellarator reactor designs. The major limitation of the compact size is the lack of space under the helical coils for the blanket and shield. Neoclassical confinement models for helically trapped particles show that a large electric potential (radial electric field) is necessary to achieve ignition in a device of this size, although high-Q operation is still attainable with more modest potentials

  9. James Cronin, CP Violation, and the Pierre Auger Observatory

    dropdown arrow Site Map A-Z Index Menu Synopsis James Cronin, CP Violation and the Pierre Auger Observatory matter over antimatter."1 "The experiment uncovered the CP [charge-parity] violation, or a with Additional Information Additional information about James Cronin and the charge-parity (CP

  10. Shared research priorities for pessary use in women with prolapse: results from a James Lind Alliance Priority Setting Partnership.

    Lough, Kate; Hagen, Suzanne; McClurg, Doreen; Pollock, Alex

    2018-04-28

    To identify the shared priorities for future research of women affected by and clinicians involved with pessary use for the management of prolapse. A priority setting project using a consensus method. A James Lind Alliance Pessary use for prolapse Priority Setting Partnership (JLA Pessary PSP) conducted from May 2016 to September 2017 in the UK. The PSP was run by a Steering Group of three women with experience of pessary use, three experienced clinicians involved with management of prolapse, two researchers with relevant experience, a JLA adviser and a PSP leader. Two surveys were conducted in 2016 and 2017. The first gathered questions about pessaries, and the second asked respondents to prioritise a list of questions. A final workshop was held on 8 September 2017 involving 10 women and 13 clinician representatives with prolapse and pessary experience. A top 10 list of priorities for future research in pessary use for prolapse was agreed by consensus. Women with experience of pessary use and clinicians involved with prolapse management have worked together to determine shared priorities for future research. Aligning the top 10 results with existing research findings will highlight the gaps in current evidence and signpost future research to areas of priority. Effective dissemination of the results will enable research funding bodies to focus on gathering the evidence to answer the questions that matter most to those who will be affected. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  11. STARFIRE: a commercial tokamak reactor

    1979-12-01

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

  12. Creating the Deep Space Environment for Testing the James Webb Space Telescope (JWST) at NASA Johnson Space Center's Chamber A

    Homan, Jonathan L.; Cerimele, Mary P.; Montz, Michael E.; Bachtel, Russell; Speed, John; O'Rear, Patrick

    2013-01-01

    Chamber A is the largest thermal vacuum chamber at the Johnson Space Center and is one of the largest space environment chambers in the world. The chamber is 19.8 m (65 ft) in diameter and 36.6 m (120 ft) tall and is equipped with cryogenic liquid nitrogen panels (shrouds) and gaseous helium shrouds to create a simulated space environment. It was originally designed and built in the mid 1960 s to test the Apollo Command and Service Module and several manned tests were conducted on that spacecraft, contributing to the success of the program. The chamber has been used since that time to test spacecraft active thermal control systems, Shuttle DTO, DOD, and ESA hardware in simulated Low Earth Orbit (LEO) conditions. NASA is now moving from LEO towards exploration of locations with environments approaching those of deep space. Therefore, Chamber A has undergone major modifications to enable it to simulate these deeper space environments. Environmental requirements were driven, and modifications were funded by the James Webb Space Telescope program, and this telescope which will orbit Solar/Earth L2, will be the first test article to benefit from the chamber s new capabilities. To accommodate JWST, the Chamber A high vacuum system has been modernized, additional LN2 shrouds have been installed, the liquid nitrogen system has been modified to remove dependency on electrical power and increase its reliability, a new helium shroud/refrigeration system has been installed to create a colder more stable and uniform heat sink, and the controls have been updated to increase the level of automation and improve operator interfaces. Testing of these major modifications was conducted in August of 2012 and this initial test was very successful, with all major systems exceeding their performance requirements. This paper will outline the changes in overall environmental requirements, discuss the technical design data that was used in the decisions leading to the extensive modifications

  13. Creating the Deep Space Environment for Testing the James Webb Space Telescope at NASA Johnson Space Center's Chamber A

    Homan, Jonathan L.; Cerimele, Mary P.; Montz, Michael E.; Bachtel, Russell; Speed, John; O'Rear, Patrick

    2013-01-01

    Chamber A is the largest thermal vacuum chamber at the Johnson Space Center and is one of the largest space environment chambers in the world. The chamber is 19.8 m (65 ft.) in diameter and 36.6 m (120 ft.) tall and is equipped with cryogenic liquid nitrogen panels (shrouds) and gaseous helium shrouds to create a simulated space environment. It was originally designed and built in the mid 1960 s to test the Apollo Command and Service Module and several manned tests were conducted on that spacecraft, contributing to the success of the program. The chamber has been used since that time to test spacecraft active thermal control systems, Shuttle DTO, DOD, and ESA hardware in simulated Low Earth Orbit (LEO) conditions. NASA is now moving from LEO towards exploration of locations with environments approaching those of deep space. Therefore, Chamber A has undergone major modifications to enable it to simulate these deeper space environments. Environmental requirements were driven, and modifications were funded by the James Webb Space Telescope program, and this telescope, which will orbit Solar/Earth L2, will be the first test article to benefit from the chamber s new capabilities. To accommodate JWST, the Chamber A high vacuum system has been modernized, additional LN2 shrouds have been installed, the liquid nitrogen system has been modified to minimize dependency on electrical power and increase its reliability, a new helium shroud/refrigeration system has been installed to create a colder more stable and uniform heat sink, and the controls have been updated to increase the level of automation and improve operator interfaces. Testing of these major modifications was conducted in August of 2012 and this initial test was very successful, with all major systems exceeding their performance requirements. This paper will outline the changes in overall environmental requirements, discuss the technical design data that was used in the decisions leading to the extensive

  14. Creating the Deep Space Environment for Testing the James Webb Space Telescope at the Johnson Space Center's Chamber A

    Homan, Jonathan L.; Cerimele, Mary P.; Montz, Michael E.

    2012-01-01

    Chamber A is the largest thermal vacuum chamber at the Johnson Space Center and is one of the largest space environment chambers in the world. The chamber is 19.8 m (65 ft) in diameter and 36.6 m (120 ft) tall and is equipped with cryogenic liquid nitrogen panels (shrouds) and gaseous helium shrouds to create a simulated space environment. It was originally designed and built in the mid 1960's to test the Apollo Command and Service Module and several manned tests were conducted on that spacecraft, contributing to the success of the program. The chamber has been used since that time to test spacecraft active thermal control systems, Shuttle DTO, DOD, and ESA hardware in simulated Low Earth Orbit (LEO) conditions. NASA is now moving from LEO towards exploration of locations with environments approaching those of deep space. Therefore, Chamber A has undergone major modifications to enable it to simulate these deeper space environments. Environmental requirements were driven, and the modifications were funded, by the James Webb Space Telescope program, and this telescope which will orbit Solar/Earth L2, will be the first test article to benefit from the chamber s new capabilities. To accommodate JWST, the Chamber A high vacuum system has been modernized, additional LN2 shrouds have been installed, the liquid nitrogen system has been modified to remove dependency on electrical power and increase its reliability, a new helium shroud/refrigeration system has been installed to create a colder more stable and uniform heat sink and, the controls have been updated to increase the level of automation and improve operator interfaces. Testing of these major modifications was conducted in August 2012 and this initial test was very successful, with all major systems exceeding their performance requirements. This paper will outline the changes in the overall environmental requirements, discuss the technical design data that was used in the decisions leading to the extensive

  15. James Craufurd Gregory, 19th century Scottish physicians, and the link between occupation as a coal miner and lung disease.

    Donaldson, K; Wallace, W A; Elliot, T A; Henry, C

    2017-09-01

    By the mid-19th century about 200,000 miners were employed in a UK coal mining industry still growing with the advances of the Industrial Revolution. Coal miners were long known to suffer poor health but the link to inhaling dust in the mines had not been made. In 1813 George Pearson was the first to suggest that darkening of lungs seen in normal individuals as they aged was caused by inhaled soot from burning oil, candles and coal, which were the common domestic sources of heat and light. In 1831 Dr James Craufurd Gregory first described black pigmentation and disease in the lungs of a deceased coal miner and linked this to pulmonary accumulation of coal mine dust. Gregory hypothesised that the black material seen at autopsy in the collier's lungs was inhaled coal dust and this was confirmed by chemical analysis carried out by Professor Sir Robert Christison. Gregory suggested that coal dust was the cause of the disease and warned physicians in mining areas to be vigilant for the disease. This first description of what came to be known as 'coal worker's pneumoconiosis' sparked a remarkable intellectual effort by physicians in Scotland, culminating in a large body of published work that led to the first understandings of this disease and its link to coalblackened lungs. This paper sets out the history of the role of Scottish physicians in gaining this understanding of coal worker's pneumoconiosis. It describes Gregory's case and the lung - recently discovered in the pathology collection of the Surgeons' Hall Museums, Edinburgh, where it has lain unnoticed for over 180 years - on which Gregory based his landmark paper.

  16. James Madison and "The Federalist Papers."

    Patrick, John J.; And Others

    A collection of resources for high school history and government teachers and their students, this volume treats core ideas on constitutional government in the United States. James Madison's ideas as found in "The Federalist Papers" are examined in conjunction with their counterpoints in essays of the Anti-Federalists. This volume…

  17. Sodium as a reactor coolant

    Cesar, S.B.G.

    1989-01-01

    This work is related to the use of sodium as a reactor coolant, to the advantages and problems related to its use, its mechanical, thermophysics, eletronical, magnetic and nuclear properties. It is mainly a bibliographic review, with the aim of gathering the necessary information to persons initiating in the study of sodium and also as reference source. (author) [pt

  18. A READING OF “OIL” (JAMES 5:14) IN THE GHANAIAN CHRISTIAN ...

    User

    with the oil has indicated that in the Ghanaian Christian ministry, it is strongly ..... healing properties, namely, coconut, shea butter, palm kernel and the like. ... colonial husk.33 Thus, this study seeks to suggest a fresh understanding on the.

  19. Remote Sensing of Light Use Efficiency in a Boreal Forest and Peatland in James Bay, Quebec

    Rogers, Cheryl

    The photochemical reflectance index (PRI) is a remotely sensed vegetation index that detects a decrease in spectral reflectance at 531nm associated with xanthophyll cycle activity. PRI has been shown to track light use efficiency (LUE) in a number of plant species. PRI shows great promise in improving our ability to sense photosynthetic fluxes of CO2 remotely. However, it has not been tested in all environments, and its applicability is particularly uncertain for peatland environments dominated by mosses. This research investigates the ability of PRI to track LUE in a boreal forest and peatland, and examines the spectral signal associated with xanthophyll cycle activity in heterogeneous peatland plots. This research also investigates the relationship between PRI and leaf area index (LAI) over space and time in a peatland. We found most plots examined in the peatland site did not exhibit a spectral signal associated with xanthophyll cycle activity when exposed to a transition from dark conditions to full sunlight. This transition should lead to a de-epoxidation of xanthophylls in leaf tissues and a decrease in reflectance at 531nm. Plots that did show the decrease in reflectance at 531nm after this change in light conditions also displayed a decrease in PRI. This indicates that PRI effectively detects the 531nm signal as well as xanthophyll cycle activity and light stress in these plots. However, the variability in the strength of the spectral response to changing light conditions may confound the PRI signal in practice, and make it difficult to interpret results of airborne or satellite data. We also found PRI at the peatland site to be sensitive to and directly correlated with spatial variability in LAI, and negatively correlated with temporal variability in LAI. These characteristics may result in further difficulties applying PRI in peatlands. PRI and LUE were correlated at both the forest and peatland site, however at both sites the PRI signal saturated around

  20. James Blunt matuselaulude edetabeli tipus

    2006-01-01

    Bereavement Registeri andmetel Suurbritannias matustel tellitavate laulude edetabelis: James Blunt "Goodbye My Lover", Robbie Williams "Angels", Jennifer Warnes ja Bill Medley "I've Had the Time Of My Life", Elton John "Candle in the Wind", Righteous Brothers "Unchained Melody"

  1. The contribution of W. James to the understanding of personality as a psychological reality

    Sergey A. Kapustin

    2017-03-01

    Full Text Available There are more than a dozen of personality theories in psychology currently. However, among psychologists there is no general agreement in understanding personality as a psychological reality, i.e. the agreement of phenomena opened to introspection and the facts established by observing the activity of the subject and his/her products, all together designated by the term «personality». The authors of these theories are dealing with very different phenomena and facts, sometimes not quite compatible ones, making impossible comparative analysis based on the criterion of adequacy, designed to assess the extent to which the scientific theory corresponds to the psychological reality explained by it. Thus, it is useful to turn to the analysis of William James’s works in order to clarify the issue of the psychological reality of the person who according to the author did the most thorough job of identifying the basic phenomena and facts that need be referred to using the term «personality». The results of this study allowed to draw the following conclusions. From James’s point of view, the psychological reality of personality must include the phenomenon of personal ego and the fact of hierarchically organized motivational sphere that has been developed as a result of individual’s self-determination. James’s representations have withstood the test of time, they were in demand by a number of renowned theorists of personality especially those that considered consciousness as a subject matter of scientific psychology. Perpetual interest in James’s concept of personality among theorists turns to be quite durable in time and is a subject matter of psychological reality.

  2. 75 FR 9904 - James A. Holland; Denial of Hearing; Final Debarment Order

    2010-03-04

    ... relating to the regulation of a drug product under the act and that the type of conduct underlying the... product under the act and (2) that the type of conduct underlying the conviction undermines the process... Acting Chief Scientist and Deputy Commissionerhas considered Holland's arguments and concludes that they...

  3. da james joyce a john assurbanipal smith. la (de)legittimazione del ...

    User

    Vedremo come Eco sembri a prima vista allineato con queste posizioni, ma anche come il suo discorso sul comico non sia privo di contraddizioni e non costituisca fino in fondo una legittimazione. Per prima cosa bisognerebbe fermarsi e dare una definizione di cosa sia il comico, ma rinuncio subito. In questo mi sento ...

  4. Chaos Theory and James Joyce's "ulysses": Leopold Bloom as a Human COMPLEX@SYSTEM^

    Mackey, Peter Francis

    1995-01-01

    These four ideas apply as much to our lives as to the life of Leopold Bloom: (1) A trivial decision can wholly change a life. (2) A chance encounter can dramatically alter life's course. (3) A contingent nexus exists between consciousness and environment. (4) A structure of meaning helps us interpret life's chaos. These ideas also relate to a contemporary science called by some "chaos theory." The connection between Ulysses and chaos theory enhances our understanding of Bloom's day; it also suggests that this novel may be about the real process of life itself. The first chapter explains how Joyce's own essays and comments to friends compel attention to the links between Ulysses and chaos theory. His scientific contemporaries anticipated chaos theory, and their ideas seem to have rubbed off on him. We see this in his sense of trivial things and chance, his modernistic organizational impulses, and the contingent nature of Bloom's experience. The second chapter studies what chaos theory and Joyce's ideas tell us about "Ithaca," the episode which particularly implicates our processes of interpreting this text as well as life itself as we face their chaos. The third chapter examines Bloom's close feel for the aboriginal world, a contingency that clarifies his vulnerability to trivial changes. The fourth chapter studies how Bloom's stream of consciousness unfolds--from his chance encounters with trivial things. Beneath this stream's seeming chaos, Bloom's distinct personality endures, similar to how Joyce's schemas give Ulysses an imbedded, underlying order. The fifth chapter examines how trivial perturbations, such as Lyons' misunderstanding about "Throwaway," produce small crises for Bloom, exacerbating his seeming impotence before his lonely "fate.". The final chapter analyzes Bloom's views that fate and chance dictate his life. His views provide an opportunity to explore the implications chaos theory has for our understanding of free will and determinism. Ultimately

  5. Pulsed reactors: A dissenting view

    Ganev, I.Kh.; Orlov, V.V.

    1995-01-01

    The preceding article, by G.A. Ivanov et al., contains interesting estimates of the expanded production of plutonium in thermonuclear explosions initiated by plutonium charges. It must be noted that more than 40 years of efforts, despite some technical successes, have not led to a fast-reactor technology suitable for large-scale power production. This explains the incessant search for a nuclear technology for the future and the renewed interest in accelerator, hybrid, and explosive approaches to plutonium production. The success of such efforts will depend largely on the formulation of goals and the choice of the principal criteria. It is appropriate to discuss these issues here because the adoption of the rate of plutonium production or the plutonium doubling time as the principal criterion sets the stage for the repetition of previous errors. However, as a preliminary, I would like to question some categorical assertions that were made by Ivanov et al. without the presentation of adequate supporting data (the assertions that open-quotes the creation of an power industry on the basis of ordinary breeder reactors is practically impossibleclose quotes and that open-quotes adequate power generation in the 21st centuryclose quotes is impossible). In fact, it is simple to calculate that, given a realistic doubling time for fast reactors of ∼10 years and the plutonium produced by thermal reactors (around 10 12 W), it would be possible, if so desired, to introduce power far exceeding 10 14 W in the 21st century

  6. Medicine in the age of " Ulysses ": James Joyce's portrait of life, medicine, and disease on a Dublin day a century ago.

    Shanahan, Fergus; Quigley, Eamonn M

    2006-01-01

    Over time, contemporary writing becomes part of the historical record. In medicine, it is an important learning tool, particularly for understanding the experience and context of disease and illness. Although a century has elapsed since the fictional events on a single day described in James Joyce's Ulysses, the work is still fresh with references and allusions to doctors, illnesses, and the human experience. Ulysses provides perspective on medical and social history and offers a biting commentary of continuing relevance to the doctor-patient relationship.

  7. Hydrological functions of a mine-impacted and natural peatland-dominated watershed, James Bay Lowland

    Melissa Leclair

    2015-09-01

    New hydrological insights: Deep seepage (groundwater recharge varied with marine sediment thickness and represented a significant loss to the local system. Large downward fluxes were also measured in fen systems that are typically local discharge zones. Evaporation rates were also found to be lower in the bogs and fens and where impacted by lower water tables. When evaluating the water balance, with only 14.5% of the watershed impacted by the mine, the hydrological function of the entire watershed is more driven by seasonal climate variations than mine dewatering.

  8. Digital computer operation of a nuclear reactor

    Colley, R.W.

    1984-01-01

    A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state

  9. Auxiliary reactor for a hydrocarbon reforming system

    Clawson, Lawrence G.; Dorson, Matthew H.; Mitchell, William L.; Nowicki, Brian J.; Bentley, Jeffrey M.; Davis, Robert; Rumsey, Jennifer W.

    2006-01-17

    An auxiliary reactor for use with a reformer reactor having at least one reaction zone, and including a burner for burning fuel and creating a heated auxiliary reactor gas stream, and heat exchanger for transferring heat from auxiliary reactor gas stream and heat transfer medium, preferably two-phase water, to reformer reaction zone. Auxiliary reactor may include first cylindrical wall defining a chamber for burning fuel and creating a heated auxiliary reactor gas stream, the chamber having an inlet end, an outlet end, a second cylindrical wall surrounding first wall and a second annular chamber there between. The reactor being configured so heated auxiliary reactor gas flows out the outlet end and into and through second annular chamber and conduit which is disposed in second annular chamber, the conduit adapted to carry heat transfer medium and being connectable to reformer reaction zone for additional heat exchange.

  10. Lateral restraint assembly in a nuclear reactor

    Brown, S.J.; Gorholt, W.

    1977-01-01

    A lateral restraint assembly is described for a reactor of, for example, the high temperature gas-cooled type which commonly includes a reactor core of relatively complex construction supported within a shell or vessel providing a shielded cavity for containing the reactor core. (U.K.)

  11. Nuclear reactor with a suspended vessel

    Lemercier, Guy.

    1977-01-01

    This invention relates to a nuclear reactor with a suspended vessel and applies in particular when this is a fast reactor, the core or active part of the reactor being inside the vessel and immersed under a suitable volume of flowing liquid metal to cool it by extracting the calories released by the nuclear fission in the fuel assemblies forming this core [fr

  12. RA Reactor applications, Annex A

    Cupac, S.; Vukadin, Z.

    2000-01-01

    Full text: In 2000 Ra reactor was not operated. New instrumentation is not complete, without it, it is not possible to think about reactor start-up. Since 1985, when reactor operation was forbidden, there are 480 fuel elements left in 48 fuel channels in the reactor core. Heavy water was removed from the reactor core because of the repair of the heavy water pumps in 1986. The old instrumentation was removed. Eleven years after being left to its own destiny, it would be difficult to imagine that anybody would think of reactor restart without examining the state of reactor vessel and other vital reactor components. Maintaining the reactor under existing conditions without final decision about restart or permanent shutdown is destructive for this nuclear facility. The existing state that pertains for more than 10 years would have only one result, destruction of the RA reactor [sr

  13. RA Reactor applications, Annex A

    Cupac, S.; Vukadin, Z.

    1998-01-01

    Full text: In 1998 Ra reactor was not operated. New instrumentation is not complete, without it, it is not possible to think about reactor start-up. Since 1985, when reactor operation was forbidden, there are 480 fuel elements left in 48 fuel channels in the reactor core. Heavy water was removed from the reactor core because of the repair of the heavy water pumps in 1986. The old instrumentation was removed. Eleven years after being left to its own destiny, it would be difficult to imagine that anybody would think of reactor restart without examining the state of reactor vessel and other vital reactor components. Maintaining the reactor under existing conditions without final decision about restart or permanent shutdown is destructive for this nuclear facility. The existing state that pertains for more than 10 years would have only one result, destruction of the RA reactor [sr

  14. RA Reactor applications, Annex A

    Cupac, S.; Vukadin, Z.

    1996-01-01

    Full text: In 2000 Ra reactor was not operated. New instrumentation is not complete, without it, it is not possible to think about reactor start-up. Since 1985, when reactor operation was forbidden, there are 480 fuel elements left in 48 fuel channels in the reactor core. Heavy water was removed from the reactor core because of the repair of the heavy water pumps in 1986. The old instrumentation was removed. Eleven years after being left to its own destiny, it would be difficult to imagine that anybody would think of reactor restart without examining the state of reactor vessel and other vital reactor components. Maintaining the reactor under existing conditions without final decision about restart or permanent shutdown is destructive for this nuclear facility. The existing state that pertains for more than 10 years would have only one result, destruction of the RA reactor [sr

  15. A recycling molecular beam reactor

    Prada-Silva, G.; Haller, G.L.; Fenn, J.B.

    1974-01-01

    In a Recycling Molecular Beam Reactor, RMBR, a beam of reactant gas molecules is formed from a supersonic free jet. After collision with a target the molecules pass through the vacuum pumps and are returned to the nozzle source. Continuous recycling permits the integration of very small reaction probabilities into measurable conversions which can be analyzed by gas chromatography. Some preliminary experiments have been carried out on the isomerization of cyclopropane

  16. Starfire: a commercial tokamak reactor

    Baker, C.C.; Abdou, M.A.; DeFreece, D.A.; Trachsel, C.A.; Graumann, D.; Kokoszenski, J.

    1979-01-01

    The basic objective of the STARFIRE Project is to develop a design concept for a commercial tokamak fusion electric power plant based on the deuterium/tritium/lithium fuel cycle. The key technical objective is to develop the best embodiment of the tokamak as a power reactor consistent with credible engineering solutions to design problems. Another key goal of the project is to give careful attention to the safety and environmental features of a commercial fusion reactor. The STARFIRE Project was initiated in May 1979, with the goal of completing the design study by October 1980. The purpose of this paper is to present an overview of the major parameters and design features that have been tentatively selected for STARFIRE

  17. Teaching the “Grandsons of Balzac” a Lesson: Henry James in the 1890’s

    Dennis F. TREDY

    2004-06-01

    Full Text Available Lyall H. Powers, in Henry James and the Naturalist Movement, dubs the period spanning from “The Art of Fiction” in 1884 to The Tragic Muse in 1890 Henry James’s “Naturalist Experiment”, and rightfully so (Powers 3. There is much evidence, in James’s own notebooks, that The Bostonians was influenced by Daudet’s L’Évangeliste, The Princess Casamassima by Turgeneff’s Virgin Soil, and The Tragic Muse by the narrative techniques of Maupassant (NB 47, Powers 91, NB 92, and Powers effectively show...

  18. James Stirling Regionalismo y modernidad

    Javier de Esteban Garbayo

    2015-05-01

    Full Text Available ResumenEn los años treinta, la arquitectura moderna se había introducido en los más remotos lugares del mundo enfrentándose con la infinita idiosincrasia de lo local, y al mismo tiempo, el arquitecto, sintiendo las limitaciones de su estilo e intentando ampliar su vocabulario, se embarcó en un proceso de difusión, asimilación y personalización.La idea de una renovada época después de la posguerra británica, sería compartida por una joven generación de arquitectos con el fin de encontrar una nueva forma de modernidad.Si en sus proyectos domésticos de mediados de los cincuenta, James Stirling partió de una aproximación al regionalismo y a la 'tradición funcional' con el fin de renovar el lenguaje moderno, no abandonaría la idea 'programática' inicial de entender la arquitectura desde una consistencia formal y una lógica que combinaba 'una síntesis común del pasado reciente y una certera actitud hacia el futuro'. AbstractThirties, modern architecture had percolated into remote corners of the world, encountering the infinite idiosyncrasies of locality, and, at the same time, Architects, feelings the limitations of their style and becoming intent upon extending their vocabulary, embarked upon a process of diffusion, assimilation and personalitation.The idea of a renewed period after British postwar, was shared for a new young architects generationto find a new way of modernity.While in his mid fifties housing projects, James Stirling approached to 'regionalism' and 'the functional tradition' to renew the modern language, he wouldn't reject the programmatic idea to understand architecture from a logic and formal consistency that combine 'a common synthesis of the recent past and a certain attitude toward the future'.

  19. James Bernoulli与《推测术》%James Bernoulli and Stochastics

    于忠义

    2003-01-01

    Two hundred and eighty-nine years ago, "Arts of conjecturing", the posthumous work of the great mathematician James Bernoulli, was finally produced in the eager wait of mathematicians, Ian Hacking, a famous historian of statistics, commented that the publication of the book signaled the beginning of the mathematical theory of probability and terminated man's long process in the forming of the probability concept By introducing James Bernoulli and his "Arts of conjecturing", this paper aims at providing the reader with the 18th century story of Bemoulli's work, and at making the reader know that even today Bemoulli's idea is very helpful and instructive in the research of modern statistics.

  20. Social and environmental impacts of the James Bay hydroelectric project

    Hornig, J.F.

    1999-01-01

    The book, which is an analysis and not an advocacy, examines the anatomy of the controversy that has swirled around the James Bay project - the La Grande and Great Whale projects combined - from the 1970s to the 1990s, and seeks, in the process, to determine whether there are lessons that can be learned from such an analysis that are applicable to other cases as well as to James Bay itself. The contributors are interested, at one and the same time, in finding ways to integrate the knowledge of natural scientists and social scientists to deepen the understanding of human/environment relations and to link science and policy to encourage a productive dialogue between practitioners and scholars in this increasingly important area of inquiry. The contributor's papers include the following: introduction to the issues; hydroelectric power development at James Bay: establishing a frame of reference; James Bay: environmental considerations for building large hydroelectric dams and reservoirs in Quebec; elevated mercury in fish as a result of the James Bay hydroelectric power development: perception and reality; the Cree people of James Bay: assessing the social impacts of hydroelectric dams and reservoirs; culture, social change, and Cree opposition to the James Bay hydroelectric development; and the impact of James Bay hydroelectric development on the art and craft of the James Bay Cree. The authors of the volume have attempted to stand back and examine just a few of these issues from the perspective of a variety of disciplines, and their purpose is to inform and stimulate thoughtful consideration by providing an overall perspective that might might serve to broaden the context in which specific issues can be debated. refs., 3 tabs., 5 figs

  1. Feed water control device in a reactor

    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.)

  2. The Mechanical Design of a Kinematic Mount for the Mid Infrared Instrument Focal Plane Module on the James Webb Space Telescope

    Thelen, Michael P.; Moore, Donald M.

    2009-01-01

    The detector assembly for the Mid Infrared Instrument (MIRI) of the James Webb Space Telescope (JWST) is mechanically supported in the Focal Plane Module (FPM) Assembly with an efficient hexapod design. The kinematic mount design allows for precision adjustment of the detector boresight to assembly alignment fiducials and maintains optical alignment requirements during flight conditions of launch and cryogenic operations below 7 Kelvin. This kinematic mounting technique is able to be implemented in a variety of optical-mechanical designs and is capable of micron level adjustment control and stability over wide dynamic and temperature ranges.

  3. 'A Speculative Idea': The Parallel Trajectories of Financial Speculation, Obstetrical Science, and Fiscal Management of Female Bodies in Henry James's Washington Square.

    Nixon, Kari

    2017-09-01

    This essay teases out the intimate connections between the scientific and fiscal realms in the context of American germ theory and obstetrics. By uncovering the economic and medical contexts of Henry James's Washington Square-set during the infancy of germ theory and the heyday of American obstetrics-this essay exposes a previously unexplored subtextual history of contagion in the text. Although this scientific history seems relegated to the novel's margins, understanding the changing scientific cosmologies and professional organizations in the context of the novel's setting and composition reveals that these tiny infectious particles and their vectors fundamentally shape the plot of the novel.

  4. Reactors

    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...

  5. RA Reactor applications, Annex A

    Martinc, R.; Cupac, S.; Stanic, A.

    1990-01-01

    RA reactor was not operated during the past five years due to the renewal and reconstruction of the reactor systems, which in underway. In the period from 1986-1990, reactor was operated only 144 MWh in 1986, for the need of testing the reactor systems and possibility of irradiating 125 I. Reactor will not be operated in 1991 because of the exchange of complete instrumentation which is planned to be finished by the end of 1991. It is expected to start operation in May 1992. That is why this annex includes the plan of reactor operation for period of nine months starting from from the moment of start-up. It is planned to operate the reactor at 0.02 MW power first three months, to increase the power gradually and reach 3.5 MW after 8 months of operation. It is foreseen to operate the reactor at 4.7 MW from the tenth month on [sr

  6. A nuclear reactor

    Kausz, I.; Stuenkel, H.; Wille, H.

    1974-01-01

    The primary cooling circuit of the PWR is a cooling water-cleaning system in parallel connection, through which 10-20% of the cycling cooling water flows. In the cleaning system there is a degasing device in which the cooling water is separated from hydrogen, nitrogen, and oxygen as well as krypton and xenon. The gases then go into a recombiner in which the oxygen is burnt and the resulting water is dropped into a drying device. The gas separating equipment which is connected to the recombiner works by condensation and intermittent evaporation of the single gas parts in heat exchangers corresponding to the liquidization temperatures of the gas parts. The noble gases are led off into a gas storer. The remaining hydrogen is then added again to the coolant circuit in order to ensure the desired excess in the latter. (DG) [de

  7. Reactor physics and thermodynamics of a gaseous core fission reactor

    Kuijper, J.C.; Van Dam, H.; Stekelenburg, A.J.C.; Hoogenboom, J.E.; Boersma-Klein, W.; Kistemaker, J.

    1990-01-01

    Neutron kinetics and thermodynamics of a Gaseous Core Fission Reactor with magnetical pumping are shown to have many unconventional aspects. Attention is focussed on the properties of the fuel gas, the stationary temperature distribution, the non-linear neutron kinetics and the energy balance in thermodynamical cycles

  8. The Book as a “Contact Zone” - Textualizing Orality in James Welch’s Fools Crow

    Tea Bartulović

    2011-12-01

    Full Text Available In the past four decades the U.S. cultural scene has witnessed a groundbreaking emergence of a number of Native American writers who have transformed the perception of minority literature, challenging Western audience to reconsider popular stereotypes and received assumptions of indigenous history, identity and culture. Today many of those writers hold prominent positions on popular bestseller and university reading lists, and interest in reading and studying their work is a mainstream trend. Committed to cultural and historical revisionism, they have also expanded the notion of a literary text, and the book as its traditional medium, turning it into a political weapon, a zone of conceptual contact, contestation and dialogue. With his third novel Fools Crow (1986 renowned Blackfeet author James Welch pointed his bow and pen in that direction as well.Set in the 1870s, the period of Indian wars, Fools Crow is a story about the tragedy of Native Americans caused by the coming of the Europeans. It captures the lives of Lone Eaters band of the Pikuni people, one of the bands belonging to the Blackfeet tribe, living on the border between American and Canadian Rocky Mountains. Told from Native American perspective, describing the time of dramatic transformation after encountering the Europeans, the plot of the novel centers around the life of the main character White Man’s Dog, later renamed Fools Crow because of his honorable performance in one of the battles. At the beginning he is just a young teenage boy, eager to finally set up his place as a successful warrior in his tribe. In spite of his initial insecurity and misfortune, he is growing into a successful warrior, hunter, leader, husband, and healer. Even though it seemingly follows Western tradition of the “identity narrative”, Fools Crow is not just a story about the experience and growth of an individual character illustrative of Western narrativity. This novel in many ways affirms

  9. A new MTR fuel for a new MTR reactor: UMo for the Jules Horowitz reactor

    Guigon, B.; Vacelet, H.; Dornbusch, D.

    2000-01-01

    Within some years, the Jules Horowitz Reactor will be the only working experimental reactor (material and fuel testing reactor) in France. It will have to provide facilities for a wide range of needs from activation analysis to power reactor fuel qualification. In this paper the main characteristics of the Jules Horowitz Reactor are presented. Safety criteria are explained. Finally, merits and disadvantages of UMo compared to the standard U 3 Si 2 fuel are discussed. (author)

  10. Nationalism in James Joyce's Ulysses

    Bahee Hadaegh

    2016-03-01

    Full Text Available In the present article, the role of nationalism and postcolonialism in James Joyce's Ulysses is explored. The novel is used to reveal the political and postcolonial layers of Joyce's work and represent how colonization works through politics. This helps the readers to realize more about political Joyce and to apprehend his political views as a fresh reading of his oeuvre. The significance of this article is to depict how an author from a colonized society is influenced by the colonizing forces and cultural invasions and to scrutinize the very psychology of a colonized nation. This task is done through Attridge and Howes's methodology as the theoretical framework containing key roles in analyzing the main discussion. Through analyzing Ulysses, this article clearly shows that Joyce was a part of nationalistic movements such as the Irish Revival; however he had major conflicts with some individuals and movements that claimed to be nationalists. Therefore, Joyce is concluded to be a 'semicolonial' writer who has his own specific mode of nationalism.

  11. NASA 3D Models: James Webb Space Telescope

    National Aeronautics and Space Administration — The James Webb Space Telescope (JWST) will be a large infrared telescope with a 6.5-meter primary mirror. The project is working to a 2018 launch date. The JWST will...

  12. Fuel assembly in a reactor

    Saito, Shozo; Kawahara, Akira.

    1975-01-01

    Object: To provide a fuel assembly in a reactor which can effectively prevent damage of the clad tube caused by mutual interference between pellets and the clad tube. Structure: A clad tube for a fuel element, which is located in the outer peripheral portion, among the fuel elements constituting fuel assemblies arranged in assembled and lattice fashion within a channel box, is increased in thickness by reducing the inside diameter thereof to be smaller than that of fuel elements internally located, thereby preventing damage of the clad tube resulting from rapid rise in output produced when control rods are removed. (Kamimura, M.)

  13. Reactor physics using a microcomputer

    Murray, R.L.

    1983-01-01

    The object of the work reported is to develop educational computer modules for all aspects of reactor physics. The modules consist of a description of the theory, mathematical method, computer program listing, sample calculations, and problems for the student, along with a card deck. Modules were first written in FORTRAN for an IBM 360/75, then later in BASIC for microcomputers. Problems include: limitation of equipment, choice of format for the program, the variety of dialects of BASIC used in the different microcomputer and peripherals brands, and knowing when to quit in the process of developing a program

  14. A method of installing a reactor container

    Hayashi, Kenji; Murakawa, Hisao.

    1975-01-01

    Object: To achieve exact installation of a reactor container at a site. Structure: A pole is set upright at the center of a cylindrical base portion, a plurality of beams are disposed around the pole in a radial fashion to form a cone, a plurality of steel plates are mounted successively around the cone through a ring, and the steel plates are welded to each other to assemble and install a reactor container at the same time. (Kamimura, M.)

  15. [Delocalizing the mind. Peirce, James, Wittgenstein, Descombes].

    Chauviré, Christiane

    2010-01-01

    The cognitive sciences have breathed fresh air into the old problem of localizing mental functions, which was often laughed off. Regarding the most philosophical form of the question on the localization of the mind, authors such as Peirce, James, Wittgenstein, and most recently Descombes have imagined delocalizing the mind in order to spread the conviction that the idea itself of a location of the mental is meaningless and to criticize the localisationism of today's cognitive scientists.

  16. William James and the Heidelberg fiasco.

    Gundlach, Horst

    2018-02-01

    Urged on by his father to become a physician instead of a painter, William James pursued 3 evasion stratagems. First, to avoid becoming a practitioner, he declared that he wanted to specialize in physiology. Based upon this premise, he left for Germany in the spring of 1867. The second step was giving up general physiology and announcing that he would specialize in the nervous system and psychology. Based upon this premise, he declared that he would go to Heidelberg and study with Helmholtz and Wundt. However, he then deferred going there. When, at last, he was urged by an influential friend of his father's to accompany him to Heidelberg, he employed his default stratagem: He simply fled. He returned home after 3 terms in Europe without enrolling at a single university. There is no evidence that he had learned anything there about psychology or experimental psychology, except, possibly, by reading books. James's "Heidelberg fiasco" was the apogee of his evasion of his father's directive. A dense fog of misinformation surrounds his stay in Heidelberg to this day. By analyzing circumstances and context, this article examines the fiasco and places it in the pattern of his behavior during his stay in Europe. Nevertheless, experiencing this fiasco potentially shaped James's ambivalent attitude toward experimental psychology on a long-term basis. (PsycINFO Database Record (c) 2018 APA, all rights reserved).

  17. Modernization of NASA's Johnson Space Center Chamber: A Payload Transport Rail System to Support Cryogenic Vacuum Optical Testing of the James Webb Space Telescope (JWST)

    Garcia, Sam; Homan, Jonathan; Speed, John

    2016-01-01

    NASA is the mission lead for the James Webb Space Telescope (JWST), the next of the "Great Observatories", scheduled for launch in 2018. It is directly responsible for the integration and test (I&T) program that will culminate in an end-to-end cryo vacuum optical test of the flight telescope and instrument module in Chamber A at NASA Johnson Space Center. Historic Chamber A is the largest thermal vacuum chamber at Johnson Space Center and one of the largest space simulation chambers in the world. Chamber A has undergone a major modernization effort to support the deep cryogenic, vacuum and cleanliness requirements for testing the JWST. This paper describe the challenges of developing, integrating and modifying new payload rails capable of transporting payloads within the thermal vacuum chamber up to 65,000 pounds. Ambient and Cryogenic Operations required to configure for testing will be explained. Lastly review historical payload configurations stretching from the Apollo program era to current James Webb Space Telescope testing.

  18. James Moir as Organic Chemist

    NICO

    James Moir (1874–1929) played an important role in the field of chemistry in South ... into the colour of organic compounds and the relationship be- tween colour ...... theory put forward by E.R.Watson,34 the depth of colour, or the displacement .... cover-glass, such as used in microscopy, to photograph absorp- tion bands ...

  19. Pressurized water reactor with a reactor pressure vessel

    Werres, L.

    1979-01-01

    The core barrel is suspended from a flange by means of a grid. The coolant enters the barrel from below through the grid. In order to get a uniform flow over the reactor core there is provided for a guiding device below the grid. It consists of a cylindrical shell with borings uniformly distributed around the shell as well as fins on the inner surface of the shell and slots at the bottom facing the pressure vessel. (GL) [de

  20. Young James Madison: His Character and Civic Values.

    Bennett, William J.

    1987-01-01

    Examines the life of James Madison, Founding Father and "theoretic statesman." Focuses specifically on Madison's education and character, his friendship with Thomas Jefferson, and his civic legacy: a selfless devotion to republican government and union. (JDH)

  1. Safety of research reactors - A regulator's perspective

    Rahman, M.S.

    2001-01-01

    Due to historical reasons research reactors have received less regulatory attention in the world than nuclear power plants. This has given rise to several safety issues which, if not addressed immediately, may result in an undesirable situation. However, in Pakistan, research reactors and power reactors have received due attention from the regulatory authority. The Pakistan Research Reactor-1 has been under regulatory surveillance since 1965, the year of its commissioning. The second reactor has also undergone all the safety reviews and checks mandated by the licensing procedures. A brief description of the regulatory framework, the several safety reviews carried out have been briefly described in this paper. Significant activities of the regulatory authority have also been described in verifying the safety of research reactors in Pakistan along with the future activities. The views of the Pakistani regulatory authority on the specific issues identified by the IAEA have been presented along with specific recommendations to the IAEA. We are of the opinion that there are more Member States operating nuclear research reactors than nuclear power plants. Therefore, there should be more emphasis on the research reactor safety, which somehow has not been the case. In several recommendations made to the IAEA on the specific safety issues the emphasis has been, in general, to have a similar documentation and approach for maintaining and verifying operational safety at research reactors as is currently available for nuclear power reactors and may be planned for nuclear fuel cycle facilities. (author)

  2. Considerations on the design of a helium circulator for a high temperature modular reactor system

    Dumm, K.; Donaldson, J.

    1988-01-01

    A modular helium cooled, high temperature reactor system with a thermal output of 200 MW per reactor has been developed by the KWU group for cogeneration of electricity and process steam. The flow of the reactor coolant - Helium at 60 bars and 250/700 deg. C is maintained by one circulator per reactor. The circulator is driven by a variable speed Siemens asynchronous motor and is submerged in the helium primary system. For operational reasons high reliability and availability of the circulator is required. The operational requirements for the circulator design are presented in this paper. The actual design has been carried out in close cooperation with the designer and manufacturer of all submerged circulators operating in AGR plants in Great Britain, James Howden Co. Renfrew, Scotland. Design solutions received so far and mainly based on sufficiently proven components - such as oil bath lubricated bearing systems - will be described. Special attention will be paid on the necessary test work; especially for the prototype to confirm the lay out. (author). 9 figs

  3. What are the dietary treatment research priorities for inflammatory bowel disease? A short report based on a priority setting partnership with the James Lind Alliance.

    Lomer, M C; Hart, A L; Verjee, A; Daly, A; Solomon, J; Mclaughlin, J

    2017-12-01

    Treatment of inflammatory bowel disease (IBD) involves a multidisciplinary approach comprising medical management and sometimes surgery. Although diet is central to IBD management, the optimal diet for patients with IBD is uncertain. A UK collaborative partnership within the James Lind Alliance was set up between patients, clinicians and other stakeholders to develop research priorities in IBD. The aim of this short report is to provide a comprehensive summary of the research priority findings relating to diet in the treatment of IBD. The James Lind Alliance Priority Setting Partnership process was used to develop research priorities in IBD. In brief, patients, clinicians and other stakeholders were invited to provide up to five treatment uncertainties in IBD. These uncertainties were collated, revised and ranked, leading to a final top 10 research questions in IBD. A total of 1671 uncertainties from 531 participants were collected and refined to exclude duplicates leaving 1253 uncertainties. Of these, 348 were categorised as diet-related and grouped according to topic. There were 206 uncertainties related to how diet can be used to treat IBD or alleviate symptoms. Seventy-two percent of diet-related questions came from patients. One broadly diet-related and two diet-specific treatment uncertainties were included in the top 10 research priorities for IBD. Dietary treatment options in the management of IBD are important research priorities. Almost three-quarters of diet related questions came from patients, who were particularly interested in how diet can impact disease activity and symptom control. © 2017 The British Dietetic Association Ltd.

  4. An internally illuminated monolith reactor: Pros and cons relative to a slurry reactor

    Carneiro, Joana T.; Carneiro, J.T.; Berger, Rob; Moulijn, Jacob A.; Mul, Guido

    2009-01-01

    In the present study, kinetic models for the photo-oxidation of cyclohexane in two different photoreactor systems are discussed: a top illumination reactor (TIR) representative of a slurry reactor, and the so-called internally illuminated monolith reactor (IIMR) representing a reactor containing

  5. Decommissioning of a small reactor (BR3 reactor, Belgium)

    Dadoumont, J.; Massaut, V.; Klein, M.; Demeulemeester, Y.

    2002-01-01

    Since 1989, SCK-CEN has been dismantling its PWR reactor BR3 (Belgian Reactor No. 3). After gaining a great deal of experience in remote dismantling of highly radioactive components during the actual dismantling of the two sets of internals, the BR3 team completed the cutting of its reactor pressure vessel (RPV). During the feasibility phase of the RPV dismantling, a decision was made to cut it under water in the refuelling pool of the plant, after having removed it from its cavity. The RPV was cut into segments using a milling cutter and a bandsaw machine. These mechanical techniques have shown their ability for this kind of operations. Prior to the segmentation, the thermal insulation situated around the RPV was remotely removed and disposed of. The paper will describe all these operations. The BR3 decommissioning activities also include the dismantling of contaminated loops and equipment. After a careful sorting of the pieces, optimized management routes are selected in order to minimize the final amount of radioactive waste to be disposed of. Some development of different methods of decontamination were carried out: abrasive blasting (or sand blasting), chemical decontamination (Oxidizing-Reducing process using Cerium). The main goal of the decontamination program is to recycle most of the metallic materials either in the nuclear world or in the industrial world by reaching the respective recycling or clearance level. Overall the decommissioning of the BR3 reactor has shown the feasibility of performing such a project in a safe and economical way. Moreover, BR3 has developed methodologies and decontamination processes to economically reduce the amount of radwaste produced. (author)

  6. Neutronics of a mixed-flow gas-core reactor

    Soran, P.D.; Hansen, G.E.

    1977-11-01

    The study was made to investigate the neutronic feasibility of a mixed-flow gas-core reactor. Three reactor concepts were studied: four- and seven-cell radial reactors and a seven-cell scallop reactor. The reactors were fueled with UF 6 (either U-233 or U-235) and various parameters were varied. A four-cell reactor is not practical nor is the U-235 fueled seven-cell radial reactor; however, the 7-cell U-233 radial and scallop reactors can satisfy all design criteria. The mixed flow gas core reactor is a very attractive reactor concept and warrants further investigation

  7. Plant with nuclear reactor, in particular a thermal reactor

    Straub, H.

    1988-01-01

    The reactor core of the plant has tubular and vertically movable control rods moved by a flow of coolant under pressure. Each control rod surrounds a similarly tubular guide rod, stationary relative to the reactor core, leaving an annular slot-like space therebetween. The inside of each guide rod forms a first pressure chamber supplied with the coolant under pressure. The upper end of each control rod is closed and has a vertical shaft that extends into the inside of the guide rod and forms therewith a second annular slot-like space. At least one first restriction is provided in the first annular slot-like space and at least one second restriction is provided in the second annular slot-like space. A second pressure chamber is formed between both restrictions. The coolant supplied to the guide rod thus returns to the pressure vessel surrounding the reactor core through the second annular slot-like space, the second pressure chamber and the first annular slot-like space. Controlling means are provided, with which pressure thrusts can be generated if necessary in the coolant within the first pressure chamber. (author) 5 refs., 10 figs

  8. Programming for a nuclear reactor instrument simulator

    Cohn, C.E.

    1989-01-01

    A new computerized control system for a transient test reactor incorporates a simulator for pre-operational testing of control programs. The part of the simulator pertinent to the discussion here consists of two microprocessors. An 8086/8087 reactor simulator calculates simulated reactor power by solving the reactor kinetics equations. An 8086 instrument simulator takes the most recent power value developed by the reactor simulator and simulates the appropriate reading on each of the eleven reactor instruments. Since the system is required to run on a one millisecond cycle, careful programming was required to take care of all eleven instruments in that short time. This note describes the special programming techniques used to attain the needed performance

  9. Calculation models for a nuclear reactor

    Tashanii, Ahmed Ali

    2010-01-01

    Determination of different parameters of nuclear reactors requires neutron transport calculations. Due to complicity of geometry and material composition of the reactor core, neutron calculations were performed for simplified models of the real arrangement. In frame of the present work two models were used for calculations. First, an elementary cell model was used to prepare cross section data set for a homogenized-core reactor model. The homogenized-core reactor model was then used to perform neutron transport calculation. The nuclear reactor is a tank-shaped thermal reactor. The semi-cylindrical core arrangement consists of aluminum made fuel bundles immersed in water which acts as a moderator as well as a coolant. Each fuel bundle consists of aluminum cladded fuel rods arranged in square lattices. (author)

  10. Experience in using a research reactor for the training of power reactor operators

    Blotcky, A.J.; Arsenaut, L.J.

    1972-01-01

    A research reactor facility such as the one at the Omaha Veterans Administration Hospital would have much to offer in the way of training reactor operators. Although most of the candidates for the course had either received previous training in the Westinghouse Reactor Operator Training Program, had operated nuclear submarine reactors or had operated power reactors, they were not offered the opportunity to perform the extensive manipulations of a reactor that a small research facility will allow. In addition the AEC recommends 10 research reactor startups per student as a prerequisite for a cold operator?s license and these can easily be obtained during the training period

  11. Fluidized bed nuclear reactor as a IV generation reactor

    Sefidvash, Farhang

    2002-01-01

    The object of this paper is to analyze the characteristics of the Fluidized Bed Nuclear Reactor (FBNR) concept under the light of the requirements set for the IV generation nuclear reactors. It is seen that FBNR generally meets the goals of providing sustainable energy generation that meets clean air objectives and promotes long-term availability of systems and effective fuel utilization for worldwide energy production; minimize and manage their nuclear waste and notably reduce the long term stewardship burden in the future, thereby improving protection for the public health and the environment; increase the assurance that it is a very unattractive and least desirable route for diversion or theft of weapons-usable materials; excel in safety and reliability; have a very low likelihood and degree of reactor core damage; eliminate the need for offsite emergency response; have a clear life-cycle cost advantage over other energy sources; have a level of financial risk comparable to other energy projects. The other advantages of the proposed design are being modular, low environmental impact, exclusion of severe accidents, short construction period, flexible adaptation to demand, excellent load following characteristics, and competitive economics. (author)

  12. Simulation of a pool type research reactor

    Oliveira, Andre Felipe da Silva de; Moreira, Maria de Lourdes

    2011-01-01

    Computational fluid dynamic is used to simulate natural circulation condition after a research reactor shutdown. A benchmark problem was used to test the viability of usage such code to simulate the reactor model. A model which contains the core, the pool, the reflector tank, the circulation pipes and chimney was simulated. The reactor core contained in the full scale model was represented by a porous media. The parameters of porous media were obtained from a separate CFD analysis of the full core model. Results demonstrate that such studies can be carried out for research and test of reactors design. (author)

  13. A new fluidized bed nuclear reactor

    Sefidvash, F.

    1986-01-01

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

  14. A glossary of terms for fast reactors

    Wheeler, R.C.

    1979-04-01

    The glossary aims to provide definitions of technical terms likely to be used in a fast reactor enquiry and to encourage the use of the same set of consistent terms in any documents intended for such an inquiry. In some cases definitions are formulated in the limited context of LMFBRS rather than applying to all types of reactors. A brief guide is presented to the different reactor types. (author)

  15. Reinforced confinement in a nuclear reactor

    Norman, H.

    1988-01-01

    The present invention concerns a nuclear reactor containing a reactor core, a swimming pool space that is filled and pressurized with a neutron-absorbing solution, a reactor tank, at least one heat exchanger, at least one inlet line, at least one return line and at least one circulation pump, where the said reactor tank is confined in the said swimming pool space and designed to be cooled with the aid of relatively pure water, which is fed by means of the said at least one circulating pump to the said reactor tank from the said heat exchanger via the said at least one inlet line and is returned to the heat exchanger via the said at least one return line. The problem that is to be solved by the invention is to design a reactor of the above type in such a way that a complete confinement of the primary circuit of the reactor is achieved at relatively low extra cost. This problem is solved by providing the reactor with a special confinement space that confines the heat exchanger, but not the reactor tank, with the confinement space and the swimming pool space being fashioned in the same concrete body

  16. Sulfide toxicity kinetics of a uasb reactor

    D. R. Paula Jr.

    2009-12-01

    Full Text Available The effect of sulfide toxicity on kinetic parameters of anaerobic organic matter removal in a UASB (up-flow anaerobic sludge blanket reactor is presented. Two lab-scale UASB reactors (10.5 L were operated continuously during 12 months. The reactors were fed with synthetic wastes prepared daily using glucose, ammonium acetate, methanol and nutrient solution. One of the reactors also received increasing concentrations of sodium sulfide. For both reactors, the flow rate of 16 L.d-1 was held constant throughout the experiment, corresponding to a hydraulic retention time of 15.6 hours. The classic model for non-competitive sulfide inhibition was applied to the experimental data for determining the overall kinetic parameter of specific substrate utilization (q and the sulfide inhibition coefficient (Ki. The application of the kinetic parameters determined allows prediction of methanogenesis inhibition and thus the adoption of operating parameters to minimize sulfide toxicity in UASB reactors.

  17. A Survey of the Origin and Evolution of Religion from the Points of View Edward Tylor and James Frazer

    Alireza khajegir

    2016-01-01

    Full Text Available As a universal human phenomenon, religion is rooted in human nature, and human beings instinctively require a superior and supreme power. Besides this internal need for religion, attention to the meaning, function, and interpretation of religion has always been prevalent in the history of human thought from West to East, and scholars have always tried to comment on and analyze this fundamental issue of human life .  From among the approaches that arose about the interpretation and explanation of religion, rationalism tendency—influenced by evolution—has stood up because in the establishment of religion, rationalism takes its genesis and evolution as manifestations of the evolution of human thought, and it takes the development and evolution of religion as equal. This approach considers religion as answer to the need of the cognitive need of human beings. In this anthropological approach, religion is the product of primitive human beings’ effort to identify objects and events in the surrounding environment. As a results, as the man’s knowledge of the world around him increases, the need for religion decreases .  Anthropologist like Edward Tylor and James Frazer have taken this view to the origin and evolution of religion. They emphasize on principles such as the bodily and cognitive unity of the mind, the survival principal, and the evolutionary intellectual pattern of human beings in order to interpret religion stages from animism and magic till monism and monotheism, which will eventually decline during the development of science .  Taylor regards anthropology as the best scientific method to achieve a universal theory to understand the origin of religion. Based on its psychological unity, religion in all times and places—despite its diversity—is a unique phenomenon and has an exclusive identity because the very existence of commonalities in all practices and customs of the people of the world is indicative of the basic

  18. A Survey of the Origin and Evolution of Religion from the Points of View Edward Tylor and James Frazer

    Alireza khajegir

    2015-12-01

    Full Text Available As a universal human phenomenon, religion is rooted in human nature, and human beings instinctively require a superior and supreme power. Besides this internal need for religion, attention to the meaning, function, and interpretation of religion has always been prevalent in the history of human thought from West to East, and scholars have always tried to comment on and analyze this fundamental issue of human life .  From among the approaches that arose about the interpretation and explanation of religion, rationalism tendency—influenced by evolution—has stood up because in the establishment of religion, rationalism takes its genesis and evolution as manifestations of the evolution of human thought, and it takes the development and evolution of religion as equal. This approach considers religion as answer to the need of the cognitive need of human beings. In this anthropological approach, religion is the product of primitive human beings’ effort to identify objects and events in the surrounding environment. As a results, as the man’s knowledge of the world around him increases, the need for religion decreases .  Anthropologist like Edward Tylor and James Frazer have taken this view to the origin and evolution of religion. They emphasize on principles such as the bodily and cognitive unity of the mind, the survival principal, and the evolutionary intellectual pattern of human beings in order to interpret religion stages from animism and magic till monism and monotheism, which will eventually decline during the development of science .  Taylor regards anthropology as the best scientific method to achieve a universal theory to understand the origin of religion. Based on its psychological unity, religion in all times and places—despite its diversity—is a unique phenomenon and has an exclusive identity because the very existence of commonalities in all practices and customs of the people of the world is indicative of the basic

  19. A new advanced safe nuclear reactor concept

    Sefidvash, Farhang

    1999-01-01

    The reactor design is based on fluidized bed concept and utilizes pressurized water reactor technology. The fuel is automatically removed from the reactor by gravity under any accident condition. The reactor demonstrates the characteristics of inherent safety and passive cooling. Here two options for modification to the original design are proposed in order to increase the stability and thermal efficiency of the reactor. A modified version of the reactor involves the choice of supercritical steam as the coolant to produce a plant thermal efficiency of about 40%. Another is to modify the shape of the reactor core to produce a non-fluctuating bed and consequently guarantee the dynamic stability of the reactor. The mixing of Tantalum in the fuel is also proposed as an additional inhibition to power excursion. The spent fuel pellets may not be considered nuclear waste since they are in the shape and size that can easily be used as a a radioactive source for food irradiation and industrial applications. The reactor can easily operate with any desired spectrum by varying the porosity in order to be a plutonium burner or utilize a thorium fuel cycle. (author)

  20. RSAS: a Reactor Safety Assessment System

    Sebo, D.E.; Dixon, B.W.; Bray, M.A.

    1985-01-01

    The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (NRC). RSAS is being developed for use at the NRC's Operations Center in the event of a serious incident at a licensed nuclear power plant. The system generates situation assessments for the NRC Reactor Safety Team based on a limited number of plant parameters, known operator actions, and plant status data. The RSAS rule base currently covers one reactor type. The extension of the rule base to other reactor types is also discussed

  1. James Bay Development Corporation annual report, 1986. Societe de Developpement de la Baie James et entites affiliees rapport annuel, 1986

    1986-01-01

    The James Bay Development Corporation is a paragovernmental body whose objective is to promote the development and exploitation of those natural resources, other than hydroelectric, which are found in the James Bay region of Quebec. It also oversees the administration and infrastructure management in the territory. This report reviews the year's activities of the Corporation and its affiliates involved in tourism, native development, mining, and municipal affairs. Most of the report consists of financial statements.

  2. Fusion reactors as a future energy source

    Seifritz, W.

    A detailed update of fusion research concepts is given. Discussions are given for the following areas: (1) the magnetic confinement principle, (2) UWMAK I: conceptual design for a fusion reactor, (3) the inertial confinement principle, (4) the laser fusion power plant, (5) electron-induced fusion, (6) the long-term development potential of fusion reactors, (7) the symbiosis between fusion and fission reactors, (8) fuel supply for fusion reactors, (9) safety and environmental impact, and (10) accidents, and (11) waste removal and storage

  3. SOLASE: a conceptual laser fusion reactor design

    Conn, R.W.; Abdel-Khalik, S.I.; Moses, G.A.

    1977-12-01

    The SOLASE conceptual laser fusion reactor has been designed to elucidate the technological problems posed by inertial confinement fusion reactors. This report contains a detailed description of all aspects of the study including the physics of pellet implosion and burn, optics and target illumination, last mirror design, laser system analysis, cavity design, pellet fabrication and delivery, vacuum system requirements, blanket design, thermal hydraulics, tritium analysis, neutronics calculations, radiation effects, stress analysis, shield design, reactor and plant building layout, maintenance procedures, and power cycle design. The reactor is designed as a 1000 MW/sub e/ unit for central station electric power generation

  4. Rotor for a pyrolysis centrifuge reactor

    2015-01-01

    The present invention relates to a rotor for a pyrolysis centrifuge reactor, said rotor comprising a rotor body having a longitudinal centre axis, and at least one pivotally mounted blade being adapted to pivot around a pivot axis under rotation of the rotor body around the longitudinal centre axis....... Moreover, the present invention relates to a pyrolysis centrifuge reactor applying such a rotor....

  5. Research reactor job analysis - A project description

    Yoder, John; Bessler, Nancy J.

    1988-01-01

    Addressing the need of the improved training in nuclear industry, nuclear utilities established training program guidelines based on Performance-Based Training (PBT) concepts. The comparison of commercial nuclear power facilities with research and test reactors owned by the U.S. Department of Energy (DOE), made in an independent review of personnel selection, training, and qualification requirements for DOE-owned reactors pointed out that the complexity of the most critical tasks in research reactors is less than that in power reactors. The U.S. Department of Energy (DOE) started a project by commissioning Oak Ridge Associated Universities (ORAU) to conduct a job analysis survey of representative research reactor facilities. The output of the project consists of two publications: Volume 1 - Research Reactor Job Analysis: Overview, which contains an Introduction, Project Description, Project Methodology,, and. An Overview of Performance-Based Training (PBT); and Volume 2 - Research Reactor Job Analysis: Implementation, which contains Guidelines for Application of Preliminary Task Lists and Preliminary Task Lists for Reactor Operators and Supervisory Reactor Operators

  6. The decommissioning of a small nuclear reactor

    Neset, K.; Christensen, G.C.; Lundby, J.E.; Roenneberg, G.A.

    1990-02-01

    The JEEP II reactor at Kjeller, Norway has been used as a model for a study of the decommissioning of a small research reactor. A radiological survey is given and a plan for volume reducing, packaging, certifying, classifying and shipping of the radioactive waste is described. 23 refs., 4 figs

  7. A nuclear power reactor concept for Brazil

    Sefidvash, F.

    1980-01-01

    For the purpose of developing an independent national nuclear technology and effective manner of transferring such a technology, as well as developing a modern reactor, a new nuclear power reactor concept is proposed which is considered as a suitable and viable project for Brazil to support its development and finally construct its prototype as an indigeneous venture. (Author) [pt

  8. Reactor

    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.)

  9. Method of operating a nuclear reactor

    Spurgin, A.J.; Schaefer, W.F.

    1978-01-01

    A method of controlling a nuclear power generting station in the event of a malfunction of particular operating components is described. Upon identification of a malfunction, preselected groups of control rods are fully inserted sequentially until a predetermined power level is approached. Additional control rods are then selectively inserted to quickly bring the reactor to a second given power level to be compatible with safe operation of the system with the malfunctioning component. At the time the thermal power output of the reactor is being reduced, the turbine is operated at a rate consistent with the output of the reactor. In the event of a malfunction, the power generating system is operated in a turbine following reactor mode, with the reactor power rapidly reduced, in a controlled manner, to a safe level compatible with the type of malfunction experienced

  10. Method for refuelling a nuclear reactor core

    Anon.

    1977-01-01

    This invention relates to an improved method for refuelling a nuclear reactor core inside a reactor vessel. The technique allows a substantial reduction in the refuelling time as compared with previously known methods and permits fewer out of core operations and smaller temporary storage space. (U.K.)

  11. Seismic attenuation system for a nuclear reactor

    Liszkai, Tamas; Cadell, Seth

    2018-01-30

    A system for attenuating seismic forces includes a reactor pressure vessel containing nuclear fuel and a containment vessel that houses the reactor pressure vessel. Both the reactor pressure vessel and the containment vessel include a bottom head. Additionally, the system includes a base support to contact a support surface on which the containment vessel is positioned in a substantially vertical orientation. An attenuation device is located between the bottom head of the reactor pressure vessel and the bottom head of the containment vessel. Seismic forces that travel from the base support to the reactor pressure vessel via the containment vessel are attenuated by the attenuation device in a direction that is substantially lateral to the vertical orientation of the containment vessel.

  12. The Design of a Nuclear Reactor

    The aim of this largely pedagogical article is toemploy pre-college physics to arrive at an understanding of a system as complex as a nuclear reactor. We focus on three key issues: the fuelpin, the moderator, and lastly the dimensions ofthe nuclear reactor.

  13. The Design of a Nuclear Reactor

    2016-08-26

    Aug 26, 2016 ... The aim of this largely pedagogical article is toemploy pre-college physics to arrive at an understanding of a system as complex as a nuclear reactor. We focus on three key issues: the fuelpin, the moderator, and lastly the dimensions ofthe nuclear reactor.

  14. A worldwide survey of fast breeder reactors

    Hennies, H.H.

    1986-01-01

    While the completion of the SNR 300 was accompanied by manifold discussions on questions relevant to safety and energy policies in the Federal Republic of Germany and as a result considerable scheduling delays and exceeding of budgets were recorded, breeder reactor technology has been progressing worldwide. The transition from the development phase with small trial reactors to the construction and operation of large performance reactors was completed systematically, in particular in France and the Soviet Union. Even though the uranium supply situation does not make a short-term and comprehensive employment of fast breeder reactors essential, technology has meanwhile been advanced to such a level and extensive operating experience is on hand to enable the construction and safe operation of fast breeder reactors. A positive answer has long been found to the question of the realization of a breeding rate to guarantee the breeding effect. There remain now the endeavors to achieve a reduction in investment and fuel cycle costs. (orig.) [de

  15. Method of fueling for a nuclear reactor

    Igarashi, Takao.

    1983-01-01

    Purpose: To enable the monitoring of reactor power with sufficient accuracy, upon starting even without existence of neutron source in case of a low average burnup degree in the reactor core. Constitution: Each of fuel assemblies is charged such that neutron source region monitors for the start-up system in a reactor core neutron instrumentation system having nuclear fuel assemblies and a neutron instrumentation system are surrounded with 4 or 16 fuel assemblies of a low burnup degree. Then, the average burnup degree of the fuel assemblies surrounding the neutron source region monitors are increased than the reactor core burnup degree, whereby neutrons released from the peripheral fuels are increased, sufficient number of neutron counts can be obtained even with no neutron sources upon start-up and the reactor power can be monitored at a sufficient accuracy. (Sekiya, K.)

  16. As novidades da psicopatologia estão no século XIX? O retorno a William James e à sua "teoria das emoções"

    Guilherme Gutman

    2008-12-01

    Full Text Available O autor apresenta alguns dos principais elementos presentes na "Teoria das emoções" de William James. Entre eles, destacam-se os seguintes: 1 Inversão da ordem concebida pelo senso comum em relação à percepção subjetiva das emoções. 2 Investigação das fronteiras entre o que habitualmente se estabelece como os domínios do físico e do mental. 3 Introdução de modo preliminar das questões relacionadas a uma teoria da mente. 4 Sugestão de um novo modo de classificação para emoções, de acordo com o método pragmático.

  17. REACTOR: a computer simulation for schools

    Squires, D.

    1985-01-01

    The paper concerns computer simulation of the operation of a nuclear reactor, for use in schools. The project was commissioned by UKAEA, and carried out by the Computers in the Curriculum Project, Chelsea College. The program, for an advanced gas cooled reactor, is briefly described. (U.K.)

  18. Intervjuu James Corneriga = Interview with James Corner / James Corner ; interv. Andres Sevtshuk

    Corner, James

    2006-01-01

    Büroo Field Operations maastikuarhitekt ning Pennsylvania Ülikooli maastikuarhitektuuri osakonna juhataja James Corner oma büroost, maastikust kui "instrumendist", postindustriaalsete aladega seotud projektidest (New Yorgi High Line'i muutmine pargiks ja promenaadiks), tööst suuremahuliste maastikega (Fresh Kills'i soo, endise prügila muutmine pargialaks), maastikuarhitektuurist ja linnakujundusest (maastiku urbanism), õpetamise tähtsusest oma töös ja maastikuarhitektuuri ideede arendamisel. Bibl. lk. 24

  19. Obituary: James Houck (1940 - 2015)

    Weedman, Daniel; Barry, Donald; Soifer, Thomas

    James R. Houck, the leading figure in developing infrared spectroscopy for astrophysics, died in Ithaca, NY, on September 18, 2015, at age 74 from complications of Alzheimer's Disease. He was born on October 5, 1940, in Mobile, Alabama, but lived much of his early life in Pittsburgh, Pennsylvania, where he received his undergraduate degree from Carnegie Institute of Technology. Jim spent his scientific career at Cornell University. He came to Cornell as a physics graduate student in 1962 and remained until his retirement as the Kenneth A. Wallace Professor of Astronomy in 2012. His only year away from Ithaca was as a Guggenheim Fellow at Caltech, and he declined job offers from other universities because of his opinion that Ithaca provided the best environment for raising his family. His passion for learning, doing, and teaching science by building instruments and understanding physics led to great benefits for his students and astronomy colleagues. After receiving his PhD in condensed matter physics, he changed fields to work in astronomy at Cornell. He first collaborated with colleague Martin Harwit to develop a rocket program at Cornell for infrared observations and made numerous treks to the White Sands Missile Range flying payloads on Aerobee sounding rockets. Jim emphasized building spectrographs and making pioneering observations with ground based, airborne, and rocket-borne infrared instrumentation. Jim flew on every airplane NASA provided for astronomy. Those were pioneering times. One of his survival stories was of the Learjet in which both engines flamed out over the Pacific when the pilot did a celebratory barrel role after successful completion of their observations. His observations with rockets and airplanes were primarily of a variety of Galactic objects, including planetary nebulae, HII regions, and stars. But the most notable was an observation on the Convair 990 that produced a prescient discovery paper in 1973 led by Jim which discovered bound

  20. Simulation of a marine nuclear reactor

    Kusunoki, Tsuyoshi; Kyouya, Masahiko; Kobayashi, Hideo; Ochiai, Masaaki

    1995-01-01

    A Nuclear-powered ship Engineering Simulation SYstem (NESSY) has been developed by the Japan Atomic Energy Research Institute as an advanced design tool for research and development of future marine reactors. A marine reactor must respond to changing loads and to the ship's motions because of the ship's maneuvering and its presence in a marine environment. The NESSY has combined programs for the reactor plant behavior calculations and the ship's motion calculations. Thus, it can simulate reactor power fluctuations caused by changing loads and the ship's motions. It can also simulate the behavior of water in the pressurizer and steam generators. This water sloshes in response to the ship's motions. The performance of NESSY has been verified by comparing the simulation calculations with the measured data obtained by experiments performed using the nuclear ship Mutsu. The effects of changing loads and the ship's motions on the reactor behavior can be accurately simulated by NESSY

  1. Actinides burnup in a sodium fast reactor

    Ramirez S, J. R.; Pineda A, R.; Martinez C, E.; Alonso, G., E-mail: ramon.ramirez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    The burnup of actinides in a nuclear reactor is been proposed as part of an advanced nuclear fuel cycle, this process would close the fuel cycle recycling some of the radioactive material produced in the open nuclear fuel cycle. These actinides are found in the spent nuclear fuel from nuclear power reactors at the end of their burnup in the reactor. Previous studies of actinides recycling in thermal reactors show that would be possible reduce the amounts of actinides at least in 50% of the recycled amounts. in this work, the amounts of actinides that can be burned in a fast reactor is calculated, very interesting results surge from the calculations, first, the amounts of actinides generated by the fuel is higher than for thermal fuel and the composition of the actinides vector is different as in fuel for thermal reactor the main isotope is the {sup 237}Np in the fuel for fast reactor the main isotope is the {sup 241}Am, finally it is concluded that the fast reactor, also generates important amounts of waste. (Author)

  2. Portrait of a pragmatic conservative: Senator James A. McClure of Idaho and the politics of United States energy and Middle Eastern affairs, 1967--1990

    Woods-Davis, Wilma

    This dissertation examines the political career of Senator James A. McClure as it relates to United States energy policy and Middle Eastern affairs, 1967-1990 and within the context of the modern (post-World War II) conservative movement. A pragmatic conservative, McClure sought a balance between the extremes of issues, especially as they related to energy and United States foreign policy toward the Arab-Israeli conflict in the Middle East. More often than not, this quiet senator from Idaho was the voice of reason and moderation, carefully analyzing all sides of the issue before submitting his views on the subject. His approach to energy policy represents his conservative expression of policy, while his approach to the Arab-Israeli conflict in the Middle East demonstrates his moderation, reason, and pragmatism. He called for a national energy plan that would promote domestic production of natural energy resources, energy conservation, and peace in the Middle East. He early warned that if the United States did not develop a comprehensive energy policy, the nation would soon face energy shortages. His cautionary statements went unnoticed until the first energy crisis in 1973 and 1974. Although McClure did not support reliance on imported oil to meet energy demand, he did advocate a change in direction in foreign policy. The United States must take a more even-handed approach to the Arab-Israeli conflict and consider the Arab position too in the historic debate. He continually urged a pro-Israeli congress to rethink its policies in this area. In addition to his senate duties, McClure acted as an unofficial goodwill ambassador to many of the Arab leaders in the Middle East. He made at least nine trips to the Middle East to discuss issues of energy, trade, peace, and war. He developed a working rapport with some Arab leaders, and did much to enhance the United States image in the region. He did this at a time in American history when Congress and the public were slow to

  3. Establishing a Radiation Protection Programme for a Research Reactor

    Abdallah, M. M.

    2014-04-01

    The nature and intensity of radiation from the operation of a research reactor depend on the type of reactor, its design features and its operational history. The protection of workers from the harmful effect of radiation must therefore be of paramount importance to any operating organization of a research reactor. This project report attempts to establish an operational radiation protection programme for a research reactor using the Ghana Research Reactor-1 as a case study. (au)

  4. A new MTR fuel for a new MTR reactor: UMo for the Jules Horowitz reactor

    Guigon, B. [CEA Cadarache, Dir. de l' Energie Nucleaire DEN, Reacteur Jules Horowitz, 13 - Saint-Paul-lez-Durance (France); Vacelet, H. [Compagnie pour l' Etude et la Realisation de Combustibles Atomiques, CERCA, Etablissement de Romans, 26 (France); Dornbusch, D. [Technicatome, Service d' Architecture Generale, 13 - Aix-en-Provence (France)

    2003-07-01

    Within some years, the Jules Horowitz Reactor will be the only working experimental reactor (material and fuel testing reactor) in France. It will have to provide facilities for a wide range of needs: from activation analysis to power reactor fuel qualification. In this paper will be presented the main characteristics of the Jules Horowitz Reactor: its total power, neutron flux, fuel element... Safety criteria will be explained. Finally merits and disadvantages of UMo compared to the standard U{sub 3}Si{sub 2} fuel will be discussed. (authors)

  5. Building up a reactor industry

    Mattick, W.

    1977-01-01

    The reactor industry has in common with any other industry the need to meet a requirement in a specific market with a specific product. However, it is distinguished from old established industries by its origins, its young age and by the fact that most of its development costs were paid by the governments in all developed countries. A comparison of the origins and the history of companies in this field in the United Kingdom , France and the Federal Republic of Germany should merit special interest. A historical survey of this kind is presented in this contribution. If a technological project acquires international ramifications in order to diminish the market risk, national goals frequently must give way to a common objective. Problems involving practical application must be solved by joint efforts of industrial consortia. In this way, these industries can both offer a commercially viable product and take into account national characteristics or habits in such a way as to improve the overall cost-benefit situation with all parties involved. (orig.) [de

  6. Preliminary design of a Binary Breeder Reactor

    Garcia C, E. Y.; Francois, J. L.; Lopez S, R. C.

    2014-10-01

    A binary breeder reactor (BBR) is a reactor that by means of the transmutation and fission process can operates through the depleted uranium burning with a small quantity of fissile material. The advantages of a BBR with relation to other nuclear reactor types are numerous, taking into account their capacity to operate for a long time without requiring fuel reload or re-arrangement. In this work four different simulations are shown carried out with the MCNPX code with libraries Jeff-3.1 to 1200 K. The objective of this study is to compare two different models of BBR: a spherical reactor and a cylindrical one, using two fuel cycles for each one of them (U-Pu and Th-U) and different reflectors for the two different geometries. For all the models a super-criticality state was obtained at least 10.9 years without carrying out some fuel re-arrangement or reload. The plutonium-239 production was achieved in the models where natural uranium was used in the breeding area, while the production of uranium-233 was observed in the cases where thorium was used in the fertile area. Finally, a behavior of stationary wave reactor was observed inside the models of spherical reactor when contemplating the power uniform increment in the breeding area, while inside the cylindrical models was observed the behavior of a traveling wave reactor when registering the displacement of the burnt wave along the cylindrical model. (Author)

  7. Design of a multipurpose research reactor

    Sanchez Rios, A.A.

    1990-01-01

    The availability of a research reactor is essential in any endeavor to improve the execution of a nuclear programme, since it is a very versatile tool which can make a decisive contribution to a country's scientific and technological development. Because of their design, however, many existing research reactors are poorly adapted to certain uses. In some nuclear research centres, especially in the advanced countries, changes have been made in the original designs or new research prototypes have been designed for specific purposes. These modifications have proven very costly and therefore beyond the reach of developing countries. For this reason, what the research institutes in such countries need is a single sufficiently versatile nuclear plant capable of meeting the requirements of a nuclear research programme at a reasonable cost. This is precisely what a multipurpose reactor does. The Mexican National Nuclear Research Institute (ININ) plans to design and build a multipurpose research reactor capable at the same time of being used for the development of reactor design skills and for testing nuclear materials and fuels, for radioisotopes production, for nuclear power studies and basic scientific research, for specialized training, and so on. For this design work on the ININ Multipurpose Research Reactor, collaborative relations have been established with various international organizations possessing experience in nuclear reactor design: Atomehnergoeksport of the USSR: Atomic Energy of Canada Limited (AECL); General Atomics (GA) of the USA; and Japan Atomic Energy Research Institute

  8. A trolley mounted magazine for reactor maintenance

    Brennan, P.J.; Madani, M.; Ridgway, G.H. [GE Hitachi Nuclear Energy Canada, Peterborough, Ontario (Canada)], E-mail: patrick1.brennan@ge.com, mehdi.madani@ge.com, guy.ridgway@ge.com; Lundy, E.; Knight, D. [IM and CS (Inspection, Maintenance and Commerical Services), Ontario Power Generation, Ajax, Ontario (Canada)], E-mail: erroll.lundy@opg.com, david.knight@opg.com

    2009-03-15

    This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

  9. A trolley mounted magazine for reactor maintenance

    Brennan, P.J.; Madani, M.; Ridgway, G.H., E-mail: patrick1.brennan@ge.com, E-mail: mehdi.madani@ge.com, E-mail: guy.ridgway@ge.com [GE Hitachi Nuclear Energy Canada, Peterborough, Ontario (Canada); Lundy, E.; Knight, D., E-mail: erroll.lundy@opg.com, E-mail: david.knight@opg.com [Ontario Power Generation, Inspection, Maintenance and Commercial Services, Ajax, Ontario (Canada)

    2008-07-01

    This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

  10. A trolley mounted magazine for reactor maintenance

    Brennan, P.J.; Madani, M.; Ridgway, G.H.; Lundy, E.; Knight, D.

    2009-01-01

    This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

  11. A trolley mounted magazine for reactor maintenance

    Brennan, P.J.; Madani, M.; Ridgway, G.H.; Lundy, E.; Knight, D.

    2008-01-01

    This paper describes the design of a mechanism incorporating a rotary magazine to be mounted on a fuelling machine transport trolley for use at a Darlington reactor during a feeder replacement or maintenance outage. The magazine stores reactor channel maintenance components, such as channel isolation plugs and vented closure plugs, in twelve available magazine channels. Use of the magazine rather than a fuelling machine reduces the time required to transfer such components between the Central Service Area and reactor channels. Component transfers are accomplished by locking the fuelling machine onto one of the magazine channels and using a local controller to execute commands received from the fuel handling control system. (author)

  12. Revisitando un clásico: James Burney y su Historia de los Bucaneros de América. Una definición del mundo a principios del S. XIX

    Juan Marchena

    2012-01-01

    Full Text Available Entre la literatura y la historia y sobre la base de los escritos del navegante inglés James Burney el presente trabajo hace un recorrido a lo largo del siglo XVIII por el proceso de conocimiento de la navegación en los mares del planeta haciendo especial énfasis en los viajes por el Caribe.

  13. Sampling system for a boiling reactor NPP

    Zabelin, A.I.; Yakovleva, E.D.; Solov'ev, Yu.A.

    1976-01-01

    Investigations and pilot running of the nuclear power plant with a VK-50 boiling reactor reveal the necessity of normalizing the design system of water sampling and of mandatory replacement of the needle-type throttle device by a helical one. A method for designing a helical throttle device has been worked out. The quantitative characteristics of depositions of corrosion products along the line of reactor water sampling are presented. Recommendations are given on the organizaton of the sampling system of a nuclear power plant with BWR type reactors

  14. A swivelling transfer device for nuclear reactors

    Allain, Albert; Mulot, Pierre; Filloleau, Etienne

    1974-01-01

    The invention relates to a swivelling transfer device for fuel-assemblies. According to the invention, the device comprises, within a protective enclosure, a swivelling system comprising two sets of rails rotatable about an axis and so arranged that the lower and thereof penetrates into the extensions of the extremities of ramps dipped into the reactor and into a storage enclosure. This can apply to the transfer of nuclear reactor fuel assemblies, in particular for reactors of the molten sodium fast neutron type [fr

  15. Neutronic parameters calculations of a CANDU reactor

    Zamonsky, G.

    1991-01-01

    Neutronic calculations that reproduce in a simplified way some aspects of a CANDU reactor design were performed. Starting from some prefixed reactor parameters, cylindrical and uniform iron adjuster rods were designed. An appropriate refueling scheme was established, defininig in a 2 zones model their dimensions and exit burnups. The calculations have been done using the codes WIMS-D4 (cell), SNOD (reactivity device simulations) and PUMA (reactor). Comparing with similar calculations done with codes and models usually employed for CANDU design, it is concluded that the models and methods used are appropriate. (Author) [es

  16. ADVANCED CONTROL FOR A ETHYLENE REACTOR

    Dumitru POPESCU

    2017-06-01

    Full Text Available The main objective of this work is the design and implementation of control solutions for petrochemical processes, namely the control and optimization of a pyrolysis reactor, the key-installation in the petrochemical industry. We present the technological characteristics of this petrochemical process and some aspects about the proposed control system solution for the ethylene plant. Finally, an optimal operating point for the reactor is found, considering that the process has a nonlinear multi-variable structure. The results have been implemented on an assembly of pyrolysis reactors on a petrochemical platform from Romania.

  17. Optimization of a sequence of reactors

    Vidal, Rene Victor Valqui

    1991-01-01

    Concerns the optimal production of sulphuric acid in a sequence of reactors. Using a suitable approximation to the objective function, this problem can easily be solved using the maximum principle. A numerical example documents the applicability of the suggested approach...

  18. The hunters of humanity: creatures of horror in M. R. James's ghost stories

    Oryshchuk, Nataliya

    2017-01-01

    In his ghost stories, M.R. James disclosed the most irrational and fearful aspects of archaic demonology still haunting the modern world. He turns humans into prey species, hunted and haunted by repulsive insect- and spider-like demons. This paper offers a closer look at the creatures of horror and the recurrent theme of the hunt in James's ghost stories, viewing them in the context of Victorian evolutionary theories as well as traditional medieval beliefs. James's protagonists, unimaginative...

  19. SOLASE: a conceptual laser fusion reactor design

    Conn, R.W.; Abdel-Khalik, S.I.; Moses, G.A.

    1977-12-01

    The SOLASE conceptual laser fusion reactor has been designed to elucidate the technological problems posed by inertial confinement fusion ractors. This report contains a detailed description of all aspects of the study including the physics of pellet implosion and burn, optics and target illumination, last mirror design, laser system analysis, cavity design, pellet fabrication and delivery, vacuum system requirements, blanket design, thermal hydraulics, tritium analysis, neutronics calculations, radiation effects, stress analysis, shield design, reactor and plant building layout, maintenance procedures, and power cycle design. The reactor is designed as a 1000 MW/sub e/ unit for central station electric power generation

  20. Sustainable development in the Hudson Bay/James Bay bioregion

    Anon.

    1991-01-01

    An overview is presented of projects planned for the James Bay/Hudson Bay region, and the expected environmental impacts of these projects. The watershed of James Bay and Hudson Bay covers well over one third of Canada, from southern Alberta to central Ontario to Baffin Island, as well as parts of north Dakota and Minnesota in the U.S.A. Hydroelectric power developments that change the timing and rate of flow of fresh water may cause changes in the nature and duration of ice cover, habitats of marine mammals, fish and migratory birds, currents into and out of Hudson Bay/James Bay, seasonal and annual loads of sediments and nutrients to marine ecosystems, and anadromous fish populations. Hydroelectric projects are proposed for the region by Quebec, Ontario and Manitoba. In January 1992, the Canadian Arctic Resources Committee (CARC), the Environmental Committee of Sanikuluaq, and the Rawson Academy of Arctic Science will launch the Hudson Bay/James Bay Bioregion Program, an independent initiative to apply an ecosystem approach to the region. Two main objectives are to provide a comprehensive assessment of the cumulative impacts of human activities on the marine and freshwater ecosystems of the Hudson Bay/James Bay bioregion, and to foster sustainable development by examining and proposing cooperative processes for decision making among governments, developers, aboriginal peoples and other stakeholders. 1 fig

  1. A study of reactor vessel integrity assessment

    Lee, Jae Hoon [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Kim, Jong Kyung; Shin, Chang Ho; Seo, Bo Kyun [Hanyang Univ., Seoul (Korea, Republic of)

    1999-02-15

    The fast neutron fluence at the Reactor Pressure Vessel(RPV) of KNGR designed for 60 years lifetime was calculated by full-scope Monte Carlo simulation for reactor vessel integrity assessment. KNGR core geometry was modeled on a three-dimensional representation of the one-sixteenth of the reactor in-vessel component. Each fuel assemblies were modeled explicitly, and each fuel pins were axially divided into 5 segments. The maximum flux of 4.3 x 10{sup 10} neutrons/cm{sup 2}. sec at the RPV was obtained by tallying neutrons crossing the beltline of inner surface of the RPV.

  2. Facility with a nuclear district heating reactor

    Straub, H.

    1988-01-01

    The district heating reactor has a pressure vessel which contains the reactor core and at least one coolant conducting primary heat carrier surrounded by a heat sink. The pressure vessel has two walls with a space between them. This space is connected with a container which contains air as heat isolating medium and water as heat conducting medium. During the normal reactor operation the space is filled by air from the container with the aid of a blower, whereas in the case of a break-down of the cooling system it is filled by water which flows out of the container by gravity after the blower has been switched off. The after-heat, generated in the reactor core during cooling break-down, is removed into the heat sink surrounding the pressure vessel in a safe and simple way. 6 figs

  3. Design of a nuclear reactor cooperative controller

    Alang-Rashid, N.K.; Heger, A.S.

    1991-01-01

    This paper describes the development of a fuzzy logic controller software package and explores the feasibility of its use in nuclear reactor operation. The controller complements reactor operator actions, and the operators can override the controller decisions. Techniques of providing learning capability to the controller are also being investigated to improve the reasoning and control skill of the controller. The fuzzy logic controller is implemented in C language and its overall structure is shown. The heart of the systems consists of a fuzzifier, a rule interpreter, and a defuzzifier. The controller is designed as a stand-alone package that can be interfaced to a simulated model of a nuclear reactor. Since no model is an accurate representation of the actual process being modeled, some tuning must be performed to use the controller in an actual reactor. This is accomplished using the learning feature of the controller

  4. Gas pollutant cleaning by a membrane reactor

    Kaldis Sotiris

    2006-01-01

    Full Text Available An alternative technology for the removal of gas pollutants at the integrated gasification combined cycle process for power generation is the use of a catalytic membrane reactor. In the present study, ammonia decomposition in a catalytic reactor, with a simultaneous removal of hydrogen through a ceramic membrane, was investigated. A Ni/Al2O3 catalyst was prepared by the dry and wet impregnation method and characterized by the inductively coupled plasma method, scanning electron microscopy, X-ray diffraction, and N2 adsorption before and after activation. Commercially available a-Al2O3 membranes were also characterized and the permeabilities and permselectivities of H2, N2, and CO2 were measured by the variable volume method. In parallel with the experimental analysis, the necessary mathematical models were developed to describe the operation of the catalytic membrane reactor and to compare its performance with the conventional reactor. .

  5. Fuel assembly for a nuclear reactor

    Gjertsen, R.K.; Tower, S.N.; Huckestein, E.A.

    1982-01-01

    A fuel assembly for a nuclear reactor comprises a 5x5 array of guide tubes in a generally 20x20 array of fuel elements, the guide tubes being arranged to accommodate either control rods or water displacer rods. The fuel assembly has top and bottom Inconel (Registered Trade Mark) grids and intermediate Zircaloy grids in engagement with the guide tubes and supporting the fuel elements and guide tubes while allowing flow of reactor coolant through the assembly. (author)

  6. Gas pollutant cleaning by a membrane reactor

    George E. Skodras; Sotiris Kaldis; Savas G. Topis; Dimitris Koutsonikolas; George P. Sakellaropoulos [Aristotle University of Thessaloniki, Thessaloniki (Greece). Chemical Process Engineering Laboratory, Dept. of Chemical Engineering

    2006-07-01

    An alternative technology for the removal of gas pollutants at the intergrated gasification combined cycle process for power generation is the use of a catalytic membrane reactor. In the present study, ammonia decomposition in a catalytic reactor, with a simultaneous removal of hydrogen through a ceramic membrane, was investigated. A Ni/Al{sub 2}O{sub 3} catalyst was prepared by the dry and wet impregnation method and characterized by ICP, SEM, XRD and N{sub 2} adsorption before and after activation. Commercially available {alpha}-Al{sub 2}O{sub 3} membranes were also characterized and the permeabilities and permselectivities of H{sub 2}, N{sub 2} and CO{sub 2} were measured by the variable volume method. In parallel with the experimental analysis, the necessary mathematical models were developed to describe the operation of the catalytic membrane reactor and to compare its performance with the conventional reactor. 9 refs., 6 figs., 1 tab.

  7. Gas pollutant cleaning by a membrane reactor

    Topis, S.; Koutsonikolas, D.; Kaldis, S. (and others) [Aristotle University of Thessaloniki, Thessaloniki (Greece). Dept. of Chemical Engineering

    2005-07-01

    An alternative technology for the removal of gas pollutants at the integrated gasification combined cycle process for power generation is the use of a catalytic membrane reactor. In the present study, ammonia decomposition in a catalytic reactor, with simultaneous removal of hydrogen through a ceramic membrane, was investigated. A Ni/Al{sub 2}O{sub 3} catalyst was prepared by the dry and wet impregnation method and characterized by ICP, SEM, XRD and N{sub 2} adsorption before and after activation. Commercially available {alpha}-Al{sub 2}O{sub 3} membranes were also characterized and the permeabilities and selectivities of H{sub 2}, N{sub 2} and CO{sub 2} were measured by the variable volume method. In parallel with the experimental analysis, the necessary mathematical models were developed to describe the operation of the catalytic membrane reactor and to compare its performance with the conventional reactor. 5 refs., 6 figs., 1 tab.

  8. Henry James – Modern Theoretician of Narration

    Alexandra - Denisa IGNA

    2013-01-01

    Full Text Available Henry James, properly named world writer, was one of the first modern novelists, with an exigent writing conscience. The American writer subverted the prejudgement of the omniscient author in favour of the narration which is centred on the characters’ point of view, thus modernising the novel before V. Woolf, Huxley, Thomas Mann, or in our case Camil Petrescu and G. Călinescu. Some bio-bibliographical information familiarises the reader with the life and work of this writer. The larger part of the article is dedicated to a case study of the novel with the metaphorical title: The Figure in the Carpet, where Henry James tries to illustrate in an artistic manner his conception regarding the profundity and ineffability of the literary creation. The conclusion which the author reaches, alternating the familiar plan of the relationship between a married couple with the esthetical plan, is that the relationship between writer and his work represents an act of fully intimacy, just like a ceremony that takes place in the wedding night

  9. Reactor refurbishment options for a changing climate

    McNeish, D. [Bruce Power, Tiverton, Ontario (Canada)

    2012-07-01

    As the industry looks ahead to another generation of reactor refurbishment, it is acknowledged that the traditional way of Retubing a reactor is a daunting prospect for our investors and stakeholders. Innovations are required to mitigate the long downtime and large one-time investment associated with previous reactor refurbishments. These can take the shape of improvements to the Retube processes or by fundamentally changing the approach, e.g., calandria/shield tank replacement or partial Retubes. This session presents technical challenges that utilities need help resolving to arrive at a more attractive reactor refurbishment model. This includes issues related to calandria vessel fitness-for-service, the fuel channel replacement process, the feeder replacement process, life extension of fuel channels and feeders and complexities involving interfacing systems. (author)

  10. Reactor refurbishment options for a changing climate

    McNeish, D.

    2012-01-01

    As the industry looks ahead to another generation of reactor refurbishment, it is acknowledged that the traditional way of Retubing a reactor is a daunting prospect for our investors and stakeholders. Innovations are required to mitigate the long downtime and large one-time investment associated with previous reactor refurbishments. These can take the shape of improvements to the Retube processes or by fundamentally changing the approach, e.g., calandria/shield tank replacement or partial Retubes. This session presents technical challenges that utilities need help resolving to arrive at a more attractive reactor refurbishment model. This includes issues related to calandria vessel fitness-for-service, the fuel channel replacement process, the feeder replacement process, life extension of fuel channels and feeders and complexities involving interfacing systems. (author)

  11. Mechanical design of a PERMCAT reactor module

    Tosti, S. [Associazione ENEA Euratom sulla Fusione, C.R. ENEA Frascati, Via E. Fermi 45, Frascati, Roma I-00044 (Italy)], E-mail: tosti@frascati.enea.it; Bettinali, L. [Associazione ENEA Euratom sulla Fusione, C.R. ENEA Frascati, Via E. Fermi 45, Frascati, Roma I-00044 (Italy); Borgognoni, F. [Tesi Sas, Via Bolzano 28, Rome (Italy); Murdoch, D.K. [EFDA CSU, Boltzmannstr. 2, D-85748 Garching bei Munchen (Germany)

    2007-02-15

    The PERMCAT is a membrane reactor proposed for processing fusion reactor plasma exhaust gas: tritium removal is obtained by isotopic swamping operating in counter-current mode. In this work, a membrane reactor using a permeator tube of length about 500 mm produced via diffusion welding of Pd-Ag thin foils is described. An appropriate mechanical design of the membrane module has been developed in order to avoid any significant compressive and bending stresses on the very long and thin wall permeator tube: two expanded bellows have been applied to the Pd-Ag tube, so that it has been pre-tensioned before operating. The elongation of the metal permeator under hydrogenation has been theoretically estimated and experimentally verified for properly designing the membrane reactor.

  12. Space reactors - What is a kilogram

    Buden, D.; Angelo, J.; Ek, D.; Voss, S.

    1984-01-01

    The use of nuclear electric propulsion can triple the payloads to GEO for a single Shuttle launch. Life orbits of 300 years can be used to allow most of the fission and activation products to decay before a reactor reenters the biosphere. Enough radioactive materials remain with very long lifetimes to make it desirable to design the reactor to disperse upon reentry and little additional risk to the biosphere is introduced by initiating NEP operations from 300 km

  13. Space reactors: What is a kilogram

    Buden, D.; Angelo, J. Jr.; Ek, D.; Voss, S.

    1984-01-01

    The use of nuclear electric propulsion can triple payloads to GEO for a single Shuttle launch. Life orbits of 300 years can be used to allow most of the fission and activation products to decay before a reactor reenters the biosphere. Enough radioactive materials remain with very long lifetimes to make it desirable to design the reactor to disperse upon reentry and little additional risk to the biosphere is introduced by initiating NEP operations from 300 km

  14. Reactor vessel nozzle cracks: a photoelastic study

    Smith, C.W.

    1979-01-01

    A method consisting of a marriage between the ''frozen stress'' photoelastic approach and the local stress field equations of linear elastic fracture mechanics for estimating stress intensity factor distributions in three dimensional, finite cracked body problems is reviewed and extensions of the method are indicated. The method is then applied to the nuclear reactor vessel nozzle corner crack problem for both Intermediate Test Vessel and Boiling Water Reactor geometries. Results are compared with those of other investigators. 35 refs

  15. Assessment of salinity intrusion in the James and Chickahominy Rivers as a result of simulated sea-level rise in Chesapeake Bay, East Coast, USA.

    Rice, Karen C; Hong, Bo; Shen, Jian

    2012-11-30

    Global sea level is rising, and the relative rate in the Chesapeake Bay region of the East Coast of the United States is greater than the worldwide rate. Sea-level rise can cause saline water to migrate upstream in estuaries and rivers, threatening freshwater habitat and drinking-water supplies. The effects of future sea-level rise on two tributaries of Chesapeake Bay, the James and Chickahominy (CHK) Rivers, were evaluated in order to quantify the salinity change with respect to the magnitude of sea-level rise. Such changes are critical to: 1) local floral and faunal habitats that have limited tolerance ranges to salinity; and 2) a drinking-water supply for the City of Newport News, Virginia. By using the three-dimensional Hydrodynamic-Eutrophication Model (HEM-3D), sea-level rise scenarios of 30, 50, and 100 cm, based on the U.S. Climate Change Science Program for the mid-Atlantic region for the 21st century, were evaluated. The model results indicate that salinity increases in the entire river as sea level rises and that the salinity increase in a dry year is greater than that in a typical year. In the James River, the salinity increase in the middle-to-upper river (from 25 to 50 km upstream of the mouth) is larger than that in the lower and upper parts of the river. The maximum mean salinity increase would be 2 and 4 ppt for a sea-level rise of 50 and 100 cm, respectively. The upstream movement of the 10 ppt isohaline is much larger than the 5 and 20 ppt isohalines. The volume of water with salinity between 10 and 20 ppt would increase greatly if sea level rises 100 cm. In the CHK River, with a sea-level rise of 100 cm, the mean salinity at the drinking-water intake 34 km upstream of the mouth would be about 3 ppt in a typical year and greater than 5 ppt in a dry year, both far in excess of the U.S. Environmental Protection Agency's secondary standard for total dissolved solids for drinking water. At the drinking-water intake, the number of days of salinity

  16. The inauguration of Robert-Bourassa Park at James Bay

    Valiquette, M.

    1997-01-01

    Robert Bourassa's contributions to the hydroelectric development at James Bay were acknowledged with the inauguration of a park in the ex-prime minister's name. Phase 1 of the James Bay hydroelectric project constituted the world's biggest construction site, employing more than 180,000 people from beginning to project completion. The James Bay project allowed Hydro-Quebec to gain one of the world's largest electric power utilities and to gain significant competitive edge over its competitors. The Robert Bourassa Park contains a picnic area and a visitor interpretation centre which describes the history of the project. A sequence of 5 signposts summarize the contributions that Robert Bourassa made to the megaproject which cost over $20.6 billion. The complex consists of 65 turbines which produce 15,235 megawatts of electricity. 1 fig

  17. Space reactors, a prospective for the future

    Wahlquist, E.; Voss, S.S.

    1989-01-01

    The power requirements for future space missions are increasing and alternate power systems will be required to meet these needs. Therefore, in the early 1980's a tri-agency space reactor program, the SP-100, was initiated that is capable of meeting the higher power requirements. To understand the current space reactor program, it is important to review it in the context of past space nuclear programs - including radioisotopes, nuclear rockets and reactors. Initial effort on these programs began in the mid-1950's. Radioisotope generators have been flown on a variety of missions and are continuing to be used. The space reactor and nuclear rocket programs were technically successful but were both terminated in 1973. The current SP-100 program builds on those earlier programs

  18. Performance of a multipurpose research electrochemical reactor

    Henquin, E.R.; Bisang, J.M.

    2011-01-01

    Highlights: → For this reactor configuration the current distribution is uniform. → For this reactor configuration with bipolar connection the leakage current is small. → The mass-transfer conditions are closely uniform along the electrode. → The fluidodynamic behaviour can be represented by the dispersion model. → This reactor represents a suitable device for laboratory trials. - Abstract: This paper reports on a multipurpose research electrochemical reactor with an innovative design feature, which is based on a filter press arrangement with inclined segmented electrodes and under a modular assembly. Under bipolar connection, the fraction of leakage current is lower than 4%, depending on the bipolar Wagner number, and the current distribution is closely uniform. When a turbulence promoter is used, the local mass-transfer coefficient shows a variation of ±10% with respect to its mean value. The fluidodynamics of the reactor responds to the dispersion model with a Peclet number higher than 10. It is concluded that this reactor is convenient for laboratory research.

  19. Between hermeneutics and datascapes: a critical appreciation of emergent landscape design theory and praxis through the writings of James Corner 1990-2000(Part One

    Richard Weller

    2001-03-01

    Full Text Available This two-part essay examines the theoretical work of James Corner across the 1990s. Part one begins with a polemical analysis of Corner's originating notion of a hermeneutic practice of design as published in Landscape Journal in 1991. The essay necessarily broaches themes of ecology, critical regionalism and the broader panoramas of landscape planning as they are encountered in Corner's writings. Part one identifies an emergent dialectic between landscape architecture as scenography or infrastructure in his writings. In order to appreciate Corner's work, part one establishes and discusses the philosophical grounding of his position. Part one is concerned with theory, part two with praxis. Part two, following Corner's lead, summarises and comments upon some emerging design methods and specific design projects so as to situate the issues raised in part one. Part two begins with the unbuilt Parc de la Villette of 1982 by Rem Koolhaas and discusses its ramifications. Part two revolves around arguments put forward by Corner in the late 1990s for the agency of landscape design as structuring development rather than symbolising culture and nature, arguments tor what landscape design does not only what it means. To facilitate this, the writings of Bart Lootsma and Alex Wall who, along with Corner, presented the most pertinent and provocative themes in Corner's latest book Recovering Landscape: Essays in Contemporary Landscape Architecture, are considered in some detail. Part two concludes with thoughts on datascaping - a new design methodology synonymous with current trends in Dutch urbanism and one that impresses Corner with its capacity to manage and manipulate complex design programmes. Taken as a whole the essay offers neither a set of findings nor feigns conclusion; rather, it goes to the co-ordinates Corner has set out and explores the field they demarcate. The essay does, however, seek to qualify the claim that James Corner is articulating a

  20. A model for nuclear research reactor dynamics

    Barati, Ramin, E-mail: Barati.ramin@aut.ac.ir; Setayeshi, Saeed, E-mail: setayesh@aut.ac.ir

    2013-09-15

    Highlights: • A thirty-fourth order model is used to simulate the dynamics of a research reactor. • We consider delayed neutrons fraction as a function of time. • Variable fuel and temperature reactivity coefficients are used. • WIMS, BORGES and CITVAP codes are used for initial condition calculations. • Results are in agreement with experimental data rather than common codes. -- Abstract: In this paper, a useful thirty-fourth order model is presented to simulate the kinetics and dynamics of a research reactor core. The model considers relevant physical phenomena that govern the core such as reactor kinetics, reactivity feedbacks due to coolant and fuel temperatures (Doppler effects) with variable reactivity coefficients, xenon, samarium, boron concentration, fuel burn up and thermal hydraulics. WIMS and CITVAP codes are used to extract neutron cross sections and calculate the initial neuron flux respectively. The purpose is to present a model with results similar to reality as much as possible with reducing common simplifications in reactor modeling to be used in different analyses such as reactor control, functional reliability and safety. The model predictions are qualified by comparing with experimental data, detailed simulations of reactivity insertion transients, and steady state for Tehran research reactor reported in the literature and satisfactory results have been obtained.

  1. SBWR: A simplified boiling water reactor

    Duncan, J.D.; Sawyer, C.D.; Lagache, M.P.

    1987-01-01

    An advanced light water reactor concept is being developed for possible application in the 1990's. The concept, known as SBWR is a boiling water reactor which uses natural circulation to provide flow to the reactor core. In an emergency, a gravity driven core cooling system is used. The reactor is depressurized and water from an elevated suppression pool flows by gravity to the reactor vessel to keep the reactor core covered. The concept also features a passive containment cooling system in which water flows by gravity to cool the suppression pool wall. No operator action is required for a period of at least three days. Use of these and other passive systems allows the elimination of emergency diesel generators, core cooling pumps and heat removal pumps which is expected to simplify the plant design, reduce costs and simplify licensing. The concept is being developed by General Electric, Bechtel and the Massachusetts Institute of Technology supported by the Electric Power Research Institute and the United States Department of Energy in the United States. In Japan, The Japan Atomic Power Company has a great interest in this concept

  2. Design options for a bunsen reactor.

    Moore, Robert Charles

    2013-10-01

    This work is being performed for Matt Channon Consulting as part of the Sandia National Laboratories New Mexico Small Business Assistance Program (NMSBA). Matt Channon Consulting has requested Sandia's assistance in the design of a chemical Bunsen reactor for the reaction of SO2, I2 and H2O to produce H2SO4 and HI with a SO2 feed rate to the reactor of 50 kg/hour. Based on this value, an assumed reactor efficiency of 33%, and kinetic data from the literature, a plug flow reactor approximately 1%E2%80%9D diameter and and 12 inches long would be needed to meet the specification of the project. Because the Bunsen reaction is exothermic, heat in the amount of approximately 128,000 kJ/hr would need to be removed using a cooling jacket placed around the tubular reactor. The available literature information on Bunsen reactor design and operation, certain support equipment needed for process operation and a design that meet the specification of Matt Channon Consulting are presented.

  3. Occupational health physics at a fusion reactor

    Shank, K.E.; Easterly, C.E.; Shoup, R.L.

    1975-01-01

    Future generation of electrical power using controlled thermonuclear reactors will involve both traditional and new concerns for health protection. A review of the problems associated with exposures to tritium and magnetic fields is presented with emphasis on the occupational worker. The radiological aspects of tritium, inventories and loss rates of tritium for fusion reactors, and protection of the occupational worker are discussed. Magnetic fields in which workers may be exposed routinely and possible biological effects are also discussed

  4. Dynamic behaviour of a CAREM type reactor

    Abbate, P.; Doval, A.

    1990-01-01

    As complement to CAREM reactor design studies, behaviour analysis were made in a non-stationary regime, with the aim of developing plant systems and determining process variables variation ranges, characteristic of normal operating conditions, specifying alarm values for different variables, as well as for operating policies. Transient accidental scenes analysis were made, concluding that reactor characteristics provide security, maintaining the core integrity. (Author) [es

  5. Choice of thermal reactor systems: a report

    1977-09-01

    This is a report by the UK National Nuclear Corporation published by the UK Secretary of State for Energy (Mr. Benn) on 29th July 1977. It is concerned with the advantages and disadvantages of three thermal reactor systems -the AGR (advanced gas cooled reactor), the PWR (pressurised water reactor), and the SGHWR (steam generating heavy water reactor). The object was to help in the future choice of a thermal system for the UK to cover the next 25 years. The matter of export potential is also considered. A programme of four stations of 1100 to 1300 MW each over six years starting from 1979 was assumed. It is emphasised that a decision must be taken now both about reactor systems and actual orders. Headings are as follows: Extract from conclusions reached; Summary of main features of assessment; General conclusions regarding the following - safety, security of the investment, operational characteristics, development and launching requirements, effect on industry, and capital and generation costs. It is stated that in order to make an overall judgement on reactor choice the technical, commercial and social issues involved must be weighed in conjunction with cost differentials.

  6. Henry S. Turner, The English Renaissance Stage. Geometry, Poetics, and the Practical Spatial Arts 1580-1630 - Tim Fitzpatrick, Playwright, Space and Place in Early Modern Performance

    Luigi Giuliani

    2013-05-01

    Full Text Available Review of Henry S. Turner, The English Renaissance Stage. Geometry, Poetics, and the Practical Spatial Arts 1580-1630, Oxford University Press, Oxford, 2006, reimpr. 2010, 326 pp. ISBN: 978-0-19-959545-7 y Tim Fitzpatrick, Playwright, Space and Place in Early Modern Performance, Ashgate, Franham, 2011, 314 pp. ISBN: 978-1-4094-2827-5.

  7. State space modeling of reactor core in a pressurized water reactor

    Ashaari, A.; Ahmad, T.; M, Wan Munirah W. [Department of Mathematical Science, Faculty of Science, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Shamsuddin, Mustaffa [Institute of Ibnu Sina, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Abdullah, M. Adib [Swinburne University of Technology, Faculty of Engineering, Computing and Science, Jalan Simpang Tiga, 93350 Kuching, Sarawak (Malaysia)

    2014-07-10

    The power control system of a nuclear reactor is the key system that ensures a safe operation for a nuclear power plant. However, a mathematical model of a nuclear power plant is in the form of nonlinear process and time dependent that give very hard to be described. One of the important components of a Pressurized Water Reactor is the Reactor core. The aim of this study is to analyze the performance of power produced from a reactor core using temperature of the moderator as an input. Mathematical representation of the state space model of the reactor core control system is presented and analyzed in this paper. The data and parameters are taken from a real time VVER-type Pressurized Water Reactor and will be verified using Matlab and Simulink. Based on the simulation conducted, the results show that the temperature of the moderator plays an important role in determining the power of reactor core.

  8. A Preliminary Analysis of Reactor Performance Test (LOEP) for a Research Reactor

    Kim, Hyeonil; Park, Su-Ki [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The final phase of commissioning is reactor performance test, which is to prove the integrated performance and safety of the research reactor at full power with fuel loaded such as neutron power calibration, Control Absorber Rod/Second Shutdown Rod drop time, InC function test, Criticality, Rod worth, Core heat removal with natural mechanism, and so forth. The last test will be safety-related one to assure the result of the safety analysis of the research reactor is marginal enough to be sure about the nuclear safety by showing the reactor satisfies the acceptance criteria of the safety functions such as for reactivity control, maintenance of auxiliaries, reactor pool water inventory control, core heat removal, and confinement isolation. After all, the fuel integrity will be ensured by verifying there is no meaningful change in the radiation levels. To confirm the performance of safety equipment, loss of normal electric power (LOEP), possibly categorized as Anticipated Operational Occurrence (AOO), is selected as a key experiment to figure out how safe the research reactor is before turning over the research reactor to the owner. This paper presents a preliminary analysis of the reactor performance test (LOEP) for a research reactor. The results showed how different the transient between conservative estimate and best estimate will look. Preliminary analyses have shown all probable thermal-hydraulic transient behavior of importance as to opening of flap valve, minimum critical heat flux ratio, the change of flow direction, and important values of thermal-hydraulic parameters.

  9. Modernization of NASA's Johnson Space Center Chamber: A Liquid Nitrogen System to Support Cryogenic Vacuum Optical Testing of the James Webb Space Telescope (JWST)

    Garcia, Sammy; Homan, Jonathan; Montz, Michael

    2016-01-01

    NASA is the mission lead for the James Webb Space Telescope (JWST), the next of the “Great Observatories”, scheduled for launch in 2018. It is directly responsible for the integration and test (I&T) program that will culminate in an end-to-end cryo vacuum optical test of the flight telescope and instrument module in Chamber A at NASA Johnson Space Center. Historic Chamber A is the largest thermal vacuum chamber at Johnson Space Center and one of the largest space simulation chambers in the world. Chamber A has undergone a major modernization effort to support the deep cryogenic, vacuum and cleanliness requirements for testing the JWST. This paper describes the steps performed in efforts to convert the existing the 60’s era Liquid Nitrogen System from a forced flow (pumped) process to a natural circulation (thermo-siphon) process. In addition, the paper will describe the dramatic conservation of liquid nitrogen to support the long duration thermal vacuum testing. Lastly, describe the simplistic and effective control system which results in zero to minimal human inputs during steady state conditions.

  10. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing

  11. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  12. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Chang, Y.I.

    1992-07-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  13. Daddy, What's a Nuclear Reactor?

    Reisenweaver, Dennis W.

    2008-01-01

    No matter what we think of the nuclear industry, it is part of mankind's heritage. The decommissioning process is slowly making facilities associated with this industry disappear and not enough is being done to preserve the information for future generations. This paper provides some food for thought and provides a possible way forward. Industrial archaeology is an ever expanding branch of archaeology that is dedicated to preserving, interpreting and documenting our industrial past and heritage. Normally it begins with analyzing an old building or ruins and trying to determine what was done, how it was done and what changes might have occurred during its operation. We have a unique opportunity to document all of these issues and provide them before the nuclear facility disappears. Entombment is an acceptable decommissioning strategy; however we would have to change our concept of entombment. It is proposed that a number of nuclear facilities be entombed or preserved for future generations to appreciate. This would include a number of different types of facilities such as different types of nuclear power and research reactors, a reprocessing plant, part of an enrichment plant and a fuel manufacturing plant. One of the main issues that would require resolution would be that of maintaining information of the location of the buried facility and the information about its operation and structure, and passing this information on to future generations. This can be done, but a system would have to be established prior to burial of the facility so that no information would be lost. In general, our current set of requirements and laws may need to be re-examined and modified to take into account these new situations. As an alternative, and to compliment the above proposal, it is recommended that a study and documentation of the nuclear industry be considered as part of twentieth century industrial archaeology. This study should not only include the power and fuel cycle

  14. Proceedings of a workshop on the potential cumulative impacts of development in the region of Hudson and James Bays, 17-19 June 1992

    Bunch, J.N.; Reeves, R.R.

    1992-01-01

    An interdepartmental scientific workshop was held to begin developing a response by the Canadian Department of Fisheries and Oceans to concerns about cumulative environmental effects of development in the region of Hudson Bay and James Bay. Discussions at the workshop centered on the major hydroelectric projects that are proposed or under way in that region. The main product of the workshop was a series of working hypotheses referring to potential cumulative effects under four headings: physics; inorganic nutrients, organic carbon, and suspended matter fluxes; mercury and other contaminants; and biological resources. Several of the hypotheses, such as those concerning the direction of physical changes due to modification of the timing and location of freshwater discharge, problems of mercury mobilization and contamination, and decreased productivity of anadromous fish populations, were considered well-supported by available data. Other hypotheses, such as those related to primary and secondary productivity in estuarine and marine environments, effects on isolated populations of harbor seals and Atlantic salmon, and the likely responses of fish and marine mammals to altered conditions in estuaries, were judged as needing more focused research. 27 refs., 2 figs

  15. Implementing a Systematic Process for Rapidly Embedding Sustainability within Chemical Engineering Education: A Case Study of James Cook University, Australia

    Sheehan, Madoc; Schneider, Phil; Desha, Cheryl

    2012-01-01

    Sustainability has emerged as a primary context for engineering education in the 21st Century, particularly the sub-discipline of chemical engineering. However, there is confusion over how to go about integrating sustainability knowledge and skills systemically within bachelor degrees. This paper addresses this challenge, using a case study of an…

  16. A review of the UK fast reactor programme

    Smith, R.D.

    1982-01-01

    A review of the United Kingdom Fast Reactor Programme is introduced. Operational experience with the Prototype Fast Reactor (PFR) is briefly summarized. The design concept of the Commercial Demonstration Fast Reactor (CDFR) is given in some detail. The emphasis is on materials development, chemical engineering/sodium technology, fuel reprocessing and fuel cycle, engineering component development and reactor safety

  17. Evaluation of Pressure Changes in HANARO Reactor Hall after a Reactor Shutdown

    Han, Geeyang; Han, Jaesam; Ahn, Gukhoon; Jung, Hoansung

    2013-01-01

    The major objective of this work is intended to evaluate the characteristics of the thermal behavior regarding how the decay heat will be affected by the reactor hall pressure change and the increase of pool water temperature induced in the primary coolant after a reactor shutdown. The particular reactor pool water temperature at the surface where it is evaporated owing to the decay heat resulting in the local heat transfer rate is related to the pressure change response in the reactor hall associated with the primary cooling system because of the reduction of the heat exchanger to remove the heat. The increase in the pool water temperature is proportional to the heat transfer rate in the reactor pool. Consequently, any limit on the reactor pool water temperature imposes a corresponding limit on the reactor hall pressure. At HANARO, the decay heat after a reactor shutdown is mainly removed by the natural circulation cooling in the reactor pool. This paper is written for the safety feature of the pressure change related leakage rate from the reactor hall. The calculation results show that the increase of pressure in the reactor hall will not cause any serious problems to the safety limits although the reactor hall pressure is slightly increased. Therefore, it was concluded that the pool water temperature increase is not so rapid as to cause the pressure to vary significantly in the reactor hall. Furthermore, the mathematical model developed in this work can be a useful analytical tool for scoping and parametric studies in the area of thermal transient analysis, with its proper representation of the interaction between the temperature and pressure in the reactor hall

  18. Power conditioning system for a nuclear reactor

    Higashigawa, Yuichi; Joge, Toshio.

    1981-01-01

    Purpose: To provide a power conditioning system for a BWR type reactor which has a function to be automatically operated within a range that the relationship between the heat power of the reactor and the electric power of an electric generator does not lose the safety of fuel by eliminating the unnecessary fluctuation of the power of the reactor. Constitution: A load request error signal fed from a conventional turbine control system to recirculation flow regulator is eliminated, and a reactor power conditioning system is newly provided, to which an electric generator power signal, a reactor average power area monitor signal and a load request signal are inputted. Thus, the load request signal is compared directly with the electric power of the electric generator, the recirculation flow rate is controlled by the compared result, and whether the correlation between the heat power of the reqctor and the electric power of the generator satisfies the correlation determined to prove the safety of fuel or not is checked. If this correlation is satisfied, the recirculation flow rate is merely automatically controlled. (Yoshino, Y.)

  19. Okhee Lee, Cory A. Buxton, James A. Banks (ed.), Diversity and equity in science education: research, policy, and practice

    Bannier, Betsy J.

    2015-06-01

    Highly relevant for academic study among K-12 educators and the higher education faculty who train pre-service teachers, Diversity and equity in science education highlights three interrelated issues impacting science education in the United States. First, complicated dynamics related to the large and increasing population of English language learning (ELL) students are discussed. Second, the realities of standardized test scores are comparatively explored, both within and beyond the United States. Third, the politics of accountability in education are vigorously discussed. Okhee Lee and Cory A. Buxton weave through the contexts of politics, education, science, and culture to expand existing discourse about how to best educate our nation's children.

  20. THE JAMES MADISON WOOD QUADRANGLE, STEPHENS COLLEGE, COLUMBIA, MISSOURI.

    MCBRIDE, WILMA

    THE JAMES MADISON WOOD QUADRANGLE AT STEPHENS COLLEGE IS A COMPLEX OF BUILDINGS DESIGNED TO MAKE POSSIBLE A FLEXIBLE EDUCATIONAL ENVIRONMENT. A LIBRARY HOUSES A GREAT VARIETY OF AUDIO-VISUAL RESOURCES AND BOOKS. A COMMUNICATION CENTER INCORPORATES TELEVISION AND RADIO FACILITIES, A FILM PRODUCTION STUDIO, AND AUDIO-VISUAL FACILITIES. THE LEARNING…

  1. Humidity control device in a reactor container

    Aizawa, Motohiro; Igarashi, Hiroo; Osumi, Katsumi; Kimura, Takashi.

    1986-01-01

    Purpose: To provide a device capable of maintaining the inside of a container under high humidity circumstantial conditions causing less atmospheric corrosions, in order to prevent injuries due to atmospheric corrosions to smaller diameter stainless steel pipeways in the reactor container. Constitution: Stress corrosion cracks (SCC) to the smaller diameter stainless steel pipeways are caused dependent on the relative humidity and it is effective as the countermeasure against SCC to maintain the relative humidity at a low level less than 30 % or high level greater than 60 %. Based on the above findings, a humidity control device is disposed so as to maintain the relative humidity for the atmosphere within a reactor core on a higher humidity region. The device is adapted such that recycling gas in the dry-well coolant circuit is passed through an orifice to atomize the water introduced from feedwater pipe and introduce into a reactor core or such that the recycling gases in the dry-well cooling circuit are bubbled into water to remove chlorine gas in the reactor container gas thereby increasing the humidity in the reactor container. (Kamimura, M.)

  2. Leak monitoring method for a reactor container

    Uehara, Toshio.

    1987-01-01

    Purpose: To confirm leakages from a container upon nuclear reactor operation. Method: Leakages from a nuclear reactor container has been prevented by lowering the inner pressure of the container relative to the external pressure. In the conventional method of calculating the leakage by applying an inner pressure to the container and measuring the pressure change, etc. after the elapse of a pre-determined time, the measurement has to be conducted at periodical inspection when the nuclear reactor is shut-down. In view of the above, the leak test is conducted in the present invention by applying a slight inner pressure to the inside of the reactor container by supplying gases from a gas supply system and detecting the flow rate of the gases in the gas supply system while maintaining the slight inner pressure constant by controlling the supply and discharge of the gases. By applying such a inner pressure as causing no effect to the reactor operation, it is possible to monitor the leaks during operation and to detect the flow rate value surely and continuously if the leak is resulted. (Kamimura, M.)

  3. Preliminary design of a tandem mirror reactor

    Strohmayer, J.N.

    1984-04-01

    The purpose of this thesis is to examine the TARA mirror experiment as a possible tandem mirror reactor configuration. This is a preliminary study to size the coil structure based on using the smallest end cell axial length that physics and engineering allow, zeroing the central cell parallel currents and having interchange stability. The input powers are estimated for the final reactor design so a Q value may be estimated. The Q value is defined as the fusion power divided by the total injected power absorbed by the plasma. A computer study was performed on the effect of the transition size, the transition vertical spacing and transition current. These parameters affect the central cell parallel currents, the recircularization of the flux tube and the ratio of central cell beta to anchor beta needed for marginal stability. Two designs were identified. The first uses 100 keV and 13 keV neutral beams to pump the ions that trap in the thermal barrier. The Q value of this reactor is 11.3. The second reactor uses a pump beam at 40 keV. This energy is chosen because there is a resonance for the charge exchange cross section between D 0 and He 2+ at this energy, thus the alpha ash will be pumped along with the deuterium and tritium. The Q value of this reactor is 11.6

  4. Power distribution monitor in a nuclear reactor

    Uematsu, Hitoshi

    1983-01-01

    Purpose: To enable accurate monitoring for the reactor power distribution within a short time in a case where abnormality occurs in in-core neutron monitors or in a case where the reactor core state changes after the calibration for the neutron monitors. Constitution: The power distribution monitor comprises a power distribution calculator adapted to be inputted counted values from a reactor core present state data instruments and calculate the neutron flux distribution in the reactor core and the power distribution based on previously incorporated physical models, an RCF calculator adapted to be inputted with the counted values from the in-core neutron monitors and the neutron flux distribution and the power distribution calculated in the power distribution calculator and compensate the counted errors included in the counted values form the in-core neutron monitors and the calculation errors included in the power distribution calculated in the power distribution calculator to thereby calculate the power distribution within the reactor core, and an input/output device for the input of the data required for said power distribution calculator and the display for the calculation result calculated in the RCF calculator. (Ikeda, J.)

  5. A tokamak reactor with servicing capability

    Mitchell, J.T.D.; Hollis, A.

    1976-01-01

    A conceptual design for a Tokamak reactor with practical facilities for the regular replacement of blanket components after the inevitable damage from neutron irradiation, and fatigue is described. This essential facility has been largely ignored in published fusion reactor designs. One exception is the inertially-confined Saturn proposal. Tokamak and other toroidal closed-line systems have very complex geometries and sub-system requirements, which result in blanket servicing being a very difficult problem. In the concept described the magnet shield is divided into two structures - an outer permanent one with access doors and an inner shield, part of and supporting the blanket inside. Servicing access is horizontally between the toroidal magnet coils, after moving some outer poloidal magnet coils. The reactor, reactor hall, workshops and remote-handling facilities are described, and the servicing requirements discussed. The important servicing operation is the remote replacement of radiation damaged blanket and shield - divided in this design into 20 sectors, each weighing 75-100 tons and 11-12 metres high. Analysis of the operation indicates that if one sector can be replaced during a single weekend - i.e. a period of low power demand - then the annual reactor-generator availability allowing as well for the general plant servicing should be >0.9. This level of availability should meet the requirements of generating authorities but the facilities, equipment and workshops necessary may be complex and expensive

  6. Ventilation air conditioner for a reactor container

    Ikegame, Noboru; Nakagawa, Takeshi.

    1980-01-01

    Purpose: To suppress the variations in the internal pressure of a reactor container and smoothly ventilate the reactor container. Constitution: The air conditioner provides an air-flow-rate-control damper, a purge-air supply fan, and a filter device in the air-supply pipe of a reactor container. Furthermore, it provides a pressure difference detector at a part of the container. The air-flow-rate-control damper is connected electrically through a position-modulator-comparison amplifier to the pressure difference detector. When the filtration becomes insufficient by clogging of the filter device and the internal pressure increased abruptly in the container, the pressure-difference detector can detect it, and the damper is operated by a pressure regulator and the comparator so as to control the air flow to the container. Thus, the internal pressure variation is controlled so as to easily ventilate the container. (J.P.N.)

  7. A compact reactor/ORC power source

    Meier, K.L.; Kirchner, W.L.; Willcutt, G.J.

    1986-01-01

    A compact power source that combines an organic Rankine cycle (ORC) electric generator with a nuclear reactor heat source is being designed and fabricated. Incorporating existing ORC technology with proven reactor technology, the compact reactor/ORC power source offers high reliability while minimizing the need for componenet development. Thermal power at 125 kWt is removed from the coated particle fueled, graphite moderated reactor by heat pipes operating at 500 0 C. Outside the reactor vessel and connected to the heat pipes are vaporizers in which the toluene ORC working fluid is heated to 370 0 C. In the turbine-alternator-pump (TAP) combined-rotating unit, the thermal energy of the toluene is converted to 25 kWe of electric power. Lumped parameter systems analyses combined with a finite element thermal analyses combined with a finite element thermal analysis have aided in the power source design. The analysis have provided assurance of reliable multiyear normal operation as well as full power operation with upset conditions, such as failed heat pipes and inoperative ORC vaporizers. Because of inherent high reliability, long life, and insensitivity to upset conditions, this power source is especially suited for use in remote, inaccessible locations where fuel delivery and maintenance costs are high

  8. Device for supporting a nuclear reactor core

    Costes, D.

    1976-01-01

    The core of a light-water reactor which is enclosed in a prestressed concrete pressure vessel and held within a diffuser basket is supported by a device consisting of a cylindrical shell which surrounds the basket and is rigidly fixed to a plurality of frusto-conical skirts having concurrent axes and located substantially at right angles to the axis of the reactor core. The small base of each skirt is rigidly fixed to the shell and the large base is anchored in openings formed in the reactor vessel for the penetration of coolant inlet and outlet pipes. The top portion of the shell is secured to the top portion of the diffuser basket, a flat surface being formed on the shell at the point of connection with each frusto-conical skirt so as to ensure rigid suspension while permitting thermal expansion

  9. Fuel assembly for a nuclear reactor

    Gjertsen, R.K.

    1982-01-01

    A fuel assembly in a nuclear reactor comprises a locking mechanism that is capable of locking the fuel assembly to the core plate of a nuclear reactor to prevent inadvertent movement of the fuel assembly. The locking mechanism comprises a ratchet mechanism 108 that allows the fuel assembly to be easily locked to the core plate but prevents unlocking except when the ratchet is disengaged. The ratchet mechanism is coupled to the locking mechanism by a rotatable guide tube for a control rod or water displacer rod. (author)

  10. Op zoek naar James Bond: media-pelgrimages, fans en masculiniteit

    Reijnders, S.

    2009-01-01

    Visiting the settings of popular films and tv series has become a growing niche in the tourist market. Little is known about what makes these visits so appealing. This question is explored on the basis of the case of James Bond. Twenty-three interviews were conducted with James Bond fans who had

  11. The Contributions of James Moir to Physical Chemistry | Loyson ...

    James Moir was a pioneering chemist in the early 1900s who played a leading role in various chemical societies in South Africa. Although he was mainly an organic chemist, he was a very good all-round chemist, whose analytical and organic activities have already been covered in this journal. This article examines his ...

  12. Rodded shutdown system for a nuclear reactor

    Golden, M.P.; Govi, A.R.

    1978-01-01

    A top mounted nuclear reactor diverse rodded shutdown system utilizing gas fed into a pressure bearing bellows region sealed at the upper extremity to an armature is described. The armature is attached to a neutron absorber assembly by a series of shafts and connecting means. The armature is held in an uppermost position by an electromagnet assembly or by pressurized gas in a second embodiment. Deenergizing the electromagnet assembly, or venting the pressurized gas, causes the armature to fall by the force of gravity, thereby lowering the attached absorber assembly into the reactor core

  13. How to replace a reactor pressure vessel

    Huber, R.

    1996-01-01

    A potential life extending procedure for a nuclear reactor after, say, 40 years of service life, might in some circumstances be the replacement of the reactor pressure vessel. Neutron induced degradation of the vessel might make replacement by one of a different material composition desirable, for example. Although the replacement of heavy components, such as steam generators, has been possible for many years, the pressure vessel presents a much more demanding task if only because it is highly irradiated. Some preliminary feasibility studies by Siemens are reported for the two removal strategies that might be considered. These are removal of the entire pressure vessel in one piece and dismantling it into sections. (UK)

  14. A Compact Quasi-axisymmetric Stellarator Reactor

    Ku, L.P.

    2003-01-01

    We report the progress made in assessing the potential of compact, quasi-axisymmetric stellarators as power-producing reactors. Using an aspect ratio A=4.5 configuration derived from NCSX and optimized with respect to the quasi-axisymmetry and MHD stability in the linear regime as an example, we show that a reactor of 1 GW(e) maybe realizable with a major radius *8 m. This is significantly smaller than the designs of stellarator reactors attempted before. We further show the design of modular coils and discuss the optimization of coil aspect ratios in order to accommodate the blanket for tritium breeding and radiation shielding for coil protection. In addition, we discuss the effects of coil aspect ratio on the peak magnetic field in the coils

  15. A plasma arc reactor for fullerene research

    Anderson, T. T.; Dyer, P. L.; Dykes, J. W.; Klavins, P.; Anderson, P. E.; Liu, J. Z.; Shelton, R. N.

    1994-12-01

    A modified Krätschmer-Huffman reactor for the mass production of fullerenes is presented. Fullerene mass production is fundamental for the synthesis of higher and endohedral fullerenes. The reactor employs mechanisms for continuous graphite-rod feeding and in situ slag removal. Soot collects into a Soxhlet extraction thimble which serves as a fore-line vacuum pump filter, thereby easing fullerene separation from soot. Thermal gravimetric analysis (TGA) for yield determination is reported. This TGA method is faster and uses smaller samples than Soxhlet extraction methods which rely on aromatic solvents. Production of 10 g of soot per hour is readily achieved utilizing this reactor. Fullerene yields of 20% are attained routinely.

  16. Successful pregnancy outcome in Swyer-James-Macleod syndrome

    Chopra Seema

    2008-01-01

    Full Text Available Swyer-James-MacLeod (SJM syndrome is a chronic, progressive lung disease as a result of infection and bronchial obstruction that ultimately leads to emphysema. It is associated with chronic cough, sputum production and recurrent chest infections and is occasionally seen in women of reproductive age. The radiological finding of unilateral hyperlucent lung is considered synonymous with the disease entity.

  17. James Van Allen and His Namesake NASA Mission

    Baker, D. N.; Hoxie, V. C.; Jaynes, A.; Kale, A.; Kanekal, S. G.; Li, X.; Reeves, G. D.; Spence, H. E.

    2013-12-01

    In many ways, James A. Van Allen defined and "invented" modern space research. His example showed the way for government-university partners to pursue basic research that also served important national and international goals. He was a tireless advocate for space exploration and for the role of space science in the spectrum of national priorities.

  18. Mode of operation of a nuclear reactor

    Morita, T.

    1976-01-01

    A method is proposed for the operation of a nuclear reactor guaranteeing an essentially symmetrical axial power distribution during normal operation by controlling the changes occuring in the reactor power partly by variation of the concentration of the neutron-absorbing element and partly by variation of the control rod positions. The representative parameters are recorded for the upper and lower half and adjusted to a predetermined reference value. In using this method, the axial power peals are reduced and power losses avoided. (RW) [de

  19. Discharges from a fast reactor reprocessing plant

    Barnes, D.S.

    1987-01-01

    The purpose of this paper is to assess the environmental impact of the calculated routine discharges from a fast reactor fuel reprocessing plant. These assessments have been carried out during the early stages of an evolving in-depth study which culminated in the design for a European demonstration reprocessing plant (EDRP). This plant would be capable of reprocessing irradiated fuel from a series of European fast reactors. Cost-benefit analysis has then been used to assess whether further reductions in the currently predicted routine discharges would be economically justified

  20. Fast breeder reactor safety : a perspective

    Kale, R.D.

    1992-01-01

    Taking into consideration India's limited reserves of natural and vast reserves of thorium, the fast reactor route holds a great promise for India's energy supply in future. The fast reactor fueled with 239 Pu/ 238 U (unused or depleted) produces (breeds) more fissionable fuel material 239 Pu than it consumes. Calculations show that a fast breeder reactor (FBR) increases energy potential of natural uranium by about 60 times. As the fast reactor can also convert 232 Th into 233 U which is a fissionable material, it can make India's thorium reserves a source of almost inexhaustible energy supply for a long time to come. Significant advantage of FBR plants cooled by sodium and their world-wide operating experience are reviewed. There are two main safety issues of FBR, one nuclear and the other non-nuclear. The nuclear issue concerns core disruptive accident and the non-nuclear one concerns the high chemical energy potential of sodium. These two issues are analysed and it is pointed that they are manageable by current design, construction and operational practices. Main findings of safety research during the last six to eight years in West European Countries and United States of America (US) are summarised. Three stage engineered safety provision incorporated into the design of the sodium cooled Fast Breeder Test Reactor (FBTR) commissioned at Kalpakkam are explained. The important design safety features of FBTR such as primary system containment, emergency core cooling, plant protection system, inherent safety features achieved through reactivity coefficients, and natural convection cooling are discussed. Theoretical analysis and experimental research in fast reactor safety carried out at the Indira Gandhi Centre for Atomic Research during the past some years are reviewed. (M.G.B.)

  1. Iodine chemistry in a reactor regulation

    Powers, D.A.

    1996-01-01

    Radioactive iodine has always been an important consideration in the regulation of nuclear power reactors to assure the health and safety of the public. Regulators adopted conservatively bounding predictions of iodine behavior in the earliest days of the development of nuclear power because there was so little known about either accidents or the chemistry of iodine. Today there is a flood of new information and understanding of the chemistry of iodine under reactor accident conditions. This paper offers some thoughts on how the community of scientists engaged in the study of iodine chemistry can present the results of their work so that it is more immediately adopted by the regulator. It is suggested that the scientific community consider the concept of consensus standards so effectively used within the engineering community to define the status of the study of radioactive iodine chemistry for reactor safety. (author) 9 refs

  2. Iodine chemistry in a reactor regulation

    Powers, D A [Nuclear Regulatory Commission, Washington, DC (United States). Advisory Committee on Reactor Safeguards

    1996-12-01

    Radioactive iodine has always been an important consideration in the regulation of nuclear power reactors to assure the health and safety of the public. Regulators adopted conservatively bounding predictions of iodine behavior in the earliest days of the development of nuclear power because there was so little known about either accidents or the chemistry of iodine. Today there is a flood of new information and understanding of the chemistry of iodine under reactor accident conditions. This paper offers some thoughts on how the community of scientists engaged in the study of iodine chemistry can present the results of their work so that it is more immediately adopted by the regulator. It is suggested that the scientific community consider the concept of consensus standards so effectively used within the engineering community to define the status of the study of radioactive iodine chemistry for reactor safety. (author) 9 refs.

  3. James Madison's Practical Ideals for the 1990s.

    Delattre, Edwin J.

    This paper examines recent behavior of public officials at various levels of government in the United States, finds a systemic failure to meet ethical standards, and concludes that the wisdom of James Madison has much applicability to current times. Given his keen perception of human nature, Madison would not be too surprised at today's poor…

  4. The James Madison College Student Handbook, 1970-71.

    Michigan State Univ., East Lansing. James Madison Coll.

    James Madison College of Michigan State University provides a 4-year, residentially-based program devoted to the study of major social, economic, and political policy problems. It offers 5 fields of concentration: (1) Ethnic and Religious Intergroup Relations Policy Problems; (2) International Relations Policy Problems; (3) Justice, Morality and…

  5. Astronaut James Lovell checks body temperature with oral temperature probe

    1965-01-01

    Gemini 7 pilot Astronaut James A. Lovell Jr. has temperature check with oral temperature probe attached to his space suit during final preflight preparations for the Gemini 7 space mission. The temperature probe allows doctors to monitor astronauts body temperature at any time during the mission.

  6. Setting the top 10 research priorities to improve the health of people with Type 2 diabetes: a Diabetes UK-James Lind Alliance Priority Setting Partnership.

    Finer, S; Robb, P; Cowan, K; Daly, A; Shah, K; Farmer, A

    2018-07-01

    To describe processes and outcomes of a priority setting partnership to identify the 'top 10 research priorities' in Type 2 diabetes, involving people living with the condition, their carers, and healthcare professionals. We followed the four-step James Lind Alliance Priority Setting Partnership process which involved: gathering uncertainties using a questionnaire survey distributed to 70 000 people living with Type 2 diabetes and their carers, and healthcare professionals; organizing the uncertainties; interim priority setting by resampling of participants with a second survey; and final priority setting in an independent group of participants, using the nominal group technique. At each step the steering group closely monitored and guided the process. In the first survey, 8227 uncertainties were proposed by 2587 participants, of whom 18% were from black, Asian and minority ethnic groups. Uncertainties were formatted and collated into 114 indicative questions. A total of 1506 people contributed to a second survey, generating a shortlist of 24 questions equally weighted to the contributions of people living with diabetes and their carers and those of healthcare professionals. In the final step the 'top 10 research priorities' were selected, including questions on cure and reversal, risk identification and prevention, and self-management approaches in Type 2 diabetes. Systematic and transparent methodology was used to identify research priorities in a large and genuine partnership of people with lived and professional experience of Type 2 diabetes. The top 10 questions represent consensus areas of research priority to guide future research, deliver responsive and strategic allocation of research resources, and improve the future health and well-being of people living with, and at risk of, Type 2 diabetes. © 2018 The Authors. Diabetic Medicine published by John Wiley & Sons Ltd on behalf of Diabetes UK.

  7. James Brown, Sample Culture and the Permanent Distance of Glory

    Steve Jones

    2009-12-01

    Full Text Available The James Brown song ‘I’m Real’ (1988 features lyrics regaled from James Brown’s back catalogue, alongside vocal samples extracted from his earlier hits. As one of the most sampled artists of the hip-hop era, James employed sampling in order to reclaim his position as the “Godfather of Soul” and express his disatisfaction at having his work overtly plundered. The central questions I pose here focus on what the choice to sample himself reveals about Brown’s status as a Soul legend, and whether the contemporaneous James could sincerely live up to the mythic status inherent to the message of ‘I’m Real’ given its self-conscious form. This confusion appears to be an extension of Walter Benjamin’s conception of déjà vu as an acoustic effect - ‘the cool tomb of long ago, from the vault of which the present seems to return only as an echo’ (Benjamin cited in Breyley, 2009: 145 - only here the slippage between past and present is quite literal, involving the discordant imbrication of two divergent temporal states. Via a detailed investigation of the song ‘I’m Real‘, I will probe Brown’s playful employment of his own past. His gambit, I will argue, may be read simultaneously as testament to his own glory, and as a signifier that the excesses of egotistic auto-projection were always more distant than they first appeared to be.

  8. Internal corium catcher of a nuclear reactor

    Anatolii S Vlasov; Vladimir N Mineev; Aleksandr S Sidorov; Yuri A Zeigarnik

    2005-01-01

    Full text of publication follows: A corium catcher is one of the main devices of a nuclear reactor that provides corium melt and fission products retention within a containment during severe accidents. Several studies and design developments have shown that corium retention within a reactor vessel can be attained with a moderate capacity of the latter (up to 600 - 650 MW el.). With a higher reactor capacity external corium catchers are applied both at Russian (VVER-1000) and European (EPR) reactors. In the external catcher of a VVER-1000 reactor, most technological problems are solved due to using sacrificial material. They are as follows: (a) endo-thermal interaction of corium and sacrificial material reduces a level of the temperatures in the final melt pool; (b) solution in the melt of a great amount of the sacrificial material reduces the specific heat release density and the heat flux density at the boundaries of a melt; (c) due to changing of the oxide-component density an inverse stratification of the metallic and oxide components of the corium takes place, thus excluding heat-flux focusing in the zone of the metallic layer and making it possible to supply water on the free surface of the corium without a danger of incipience of the vapor explosion; (d) final oxidation of zirconium occurs without hydrogen generation. The above principles have been realized in the external catcher of the VVER- 1000 reactor at Tyanvan NPS that is presently under construction in China. Successfully solving of the problems concerning to the external catcher makes it possible to return on the new conceptual and technological basis to the idea of retention of the corium melt inside the vessel of a nuclear reactor of large capacity, that is, to provide the reactor vessel to play a role of an internal catcher. For this purpose, a reactor vessel is elongated by approximately two meters. In the lower part of the vessel, on elliptical bottom, pieces of sacrificial material are arranged

  9. Discussion of the use of the Dragon reactor as a facility for integral reactor physics experiments

    Gutmann, H

    1972-06-05

    The purpose and use of the Dragon Reactor Experiment (DRE) has changed considerably during the years of its operation. The original purpose was to show that the principle of a High Temperature Reactor is sound and demonstrate its operation. After this achievement, the purpose of the Dragon reactor changed to the use as a fuel testing facility. During recent years, a new use of the DRE has been added to its use as a fuel testing facility, namely Fuel Element Design Testing. The current report covers reactor physics experiments aspects.

  10. Priorities for research in miscarriage: a priority setting partnership between people affected by miscarriage and professionals following the James Lind Alliance methodology.

    Prior, Matthew; Bagness, Carmel; Brewin, Jane; Coomarasamy, Arri; Easthope, Lucy; Hepworth-Jones, Barbara; Hinshaw, Kim; O'Toole, Emily; Orford, Julie; Regan, Lesley; Raine-Fenning, Nick; Shakespeare, Judy; Small, Rachel; Thornton, Jim; Metcalf, Leanne

    2017-08-23

    To identify and prioritise important research questions for miscarriage. A priority setting partnership using prospective surveys and consensus meetings following methods advocated by the James Lind Alliance. UK. Women and those affected by miscarriage working alongside healthcare professionals. In the initial survey, 1093 participants (932 women who have experienced miscarriage, 8 partners, 17 family members, friends or colleagues, 104 healthcare professionals and eight charitable organisations) submitted 3279 questions. A review of existing literature identified a further 64. Non-questions were removed, and the remaining questions were categorised and summarised into 58 questions. In an interim electronic survey, 2122 respondents chose their top 10 priorities from the 58 summary questions. The 25 highest ranked in the survey were prioritised at a final face-to-face workshop. In summary, the top 10 priorities were ranked as follows: research into preventative treatment, emotional aspects in general, investigation, relevance of pre-existing medical conditions, emotional support as a treatment, importance of lifestyle factors, importance of genetic and chromosomal causes, preconception tests, investigation after different numbers of miscarriage and male causal factors. These results should be the focus of future miscarriage research. Presently, studies are being conducted to address the top priority; however, many other priorities, especially psychological and emotional support, are less well researched areas. We hope our results will encourage both researchers and funders to focus on these priorities. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  11. Reactor core and passive safety systems descriptions of a next generation pressure tube reactor - mechanical aspects

    Yetisir, M.; Gaudet, M.; Rhodes, D.; Hamilton, H.; Pencer, J. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    Canada has been developing a channel-type supercritical water-cooled nuclear reactor concept, often called the Canadian SCWR. The objective of this reactor concept is to meet the technology goals of the Generation IV International Forum (GIF) for the next generation nuclear reactor development, which include enhanced safety features (inherent safe operation and deploying passive safety features), improved resource utilization, sustainable fuel cycle, and greater proliferation resistance than Generation III nuclear reactors. The Canadian SCWR core concept consists of a high-pressure inlet plenum, a separate low-pressure heavy water moderator contained in a calandria vessel, and 336 pressure tubes surrounded by the moderator. The reactor uses supercritical water as a coolant, and a direct steam power cycle to generate electricity. The reactor concept incorporates advanced safety features such as passive core cooling, long-term decay heat rejection to the environment and fuel melt prevention via passive moderator cooling. These features significantly reduce core damage frequency relative to existing nuclear reactors. This paper presents a description of the design concepts for the Canadian SCWR core, reactor building layout and the plant layout. Passive safety concepts are also described that address containment and core cooling following a loss-of coolant accident, as well as long term reactor heat removal at station blackout conditions. (author)

  12. Environmental Assessment on the leasing of the Strategic Petroleum Reserve, St. James Terminal, St. James Parish, Louisiana

    NONE

    1995-01-01

    The US Department of Energy (DOE) proposes to lease the Strategic Petroleum Reserve`s (SPR) St. James Terminal to private industry. The St. James Terminal consists of six storage tanks, a pumping station, two maine docks and ancillary facilities. DOE believes that the St. James Terminal presents an opportunity to establish a government- industry arrangement that could more effectively use this asset to serve the nations`s oil distribution needs, reduce the operational cost of the SPR, and provide a source of revenue for the Government. DOE solicited interest in leasing its distribution facilities in a notice published March 16, 1994. In response, industry has expressed interest in leasing the St. James Terminal, as well as several DOE pipelines, to enhance the operation of its own facilities or to avoid having to construct new ones. Under such a lease, industry use would be subordinate to DOE use in the event of a national energy emergency. This Environmental Assessment describes the proposed leasing operation, its alternatives, and potential environmental impacts. Based on this analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) OF 1969 and has issued the Finding of No Significant Impact (FONSI).

  13. Environmental Assessment on the leasing of the Strategic Petroleum Reserve, St. James Terminal, St. James Parish, Louisiana

    1995-01-01

    The US Department of Energy (DOE) proposes to lease the Strategic Petroleum Reserve's (SPR) St. James Terminal to private industry. The St. James Terminal consists of six storage tanks, a pumping station, two maine docks and ancillary facilities. DOE believes that the St. James Terminal presents an opportunity to establish a government- industry arrangement that could more effectively use this asset to serve the nations's oil distribution needs, reduce the operational cost of the SPR, and provide a source of revenue for the Government. DOE solicited interest in leasing its distribution facilities in a notice published March 16, 1994. In response, industry has expressed interest in leasing the St. James Terminal, as well as several DOE pipelines, to enhance the operation of its own facilities or to avoid having to construct new ones. Under such a lease, industry use would be subordinate to DOE use in the event of a national energy emergency. This Environmental Assessment describes the proposed leasing operation, its alternatives, and potential environmental impacts. Based on this analyses, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) OF 1969 and has issued the Finding of No Significant Impact (FONSI)

  14. Identifying potential areas for biofuel production and evaluating the environmental effects: a case study of the James River Basin in the Midwestern United States

    Wu, Yiping; Liu, Shu-Guang; Li, Zhengpeng

    2012-01-01

    Biofuels are now an important resource in the United States because of the Energy Independence and Security Act of 2007. Both increased corn growth for ethanol production and perennial dedicated energy crop growth for cellulosic feedstocks are potential sources to meet the rising demand for biofuels. However, these measures may cause adverse environmental consequences that are not yet fully understood. This study 1) evaluates the long-term impacts of increased frequency of corn in the crop rotation system on water quantity and quality as well as soil fertility in the James River Basin and 2) identifies potential grasslands for cultivating bioenergy crops (e.g. switchgrass), estimating the water quality impacts. We selected the soil and water assessment tool, a physically based multidisciplinary model, as the modeling approach to simulate a series of biofuel production scenarios involving crop rotation and land cover changes. The model simulations with different crop rotation scenarios indicate that decreases in water yield and soil nitrate nitrogen (NO3-N) concentration along with an increase in NO3-N load to stream water could justify serious concerns regarding increased corn rotations in this basin. Simulations with land cover change scenarios helped us spatially classify the grasslands in terms of biomass productivity and nitrogen loads, and we further derived the relationship of biomass production targets and the resulting nitrogen loads against switchgrass planting acreages. The suggested economically efficient (planting acreage) and environmentally friendly (water quality) planting locations and acreages can be a valuable guide for cultivating switchgrass in this basin. This information, along with the projected environmental costs (i.e. reduced water yield and increased nitrogen load), can contribute to decision support tools for land managers to seek the sustainability of biofuel development in this region.

  15. Fuel transfer system for a nuclear reactor

    Katz, L.R.; Marshall, J.R.; Desmarchais, W.E.

    1977-01-01

    Disclosed is a fuel transfer system for moving nuclear reactor fuel assemblies from a new fuel storage pit to a containment area containing the nuclear reactor, and for transferring spent fuel assemblies under water from the reactor to a spent fuel storage area. The system includes an underwater track which extends through a wall dividing the fuel building from the reactor containment and a car on the track serves as the vehicle for moving fuel assemblies between these two areas. The car is driven by a motor and linkage extending from an operating deck to a chain belt drive on the car. A housing pivotally mounted at its center on the car is hydraulically actuated to vertically receive a fuel assembly which then is rotated to a horizontal position to permit movement through the wall between the containment and fuel building areas. Return to the vertical position provides for fuel assembly removal and the reverse process is repeated when transferring an assembly in the opposite direction. Limit switches used in controlling operation of the system are designed to be replaced from the operating deck when necessary by tools designed for this purpose. 5 claims, 8 figures

  16. Method of dismantling a nuclear reactor

    Shirai, Masato; Hashimoto, Osamu.

    1984-01-01

    Purpose: To enable rapid and simple positioning for a plasma arc torch disposed to the inside of a nuclear reactor main body. Method: After removing the upper semi-spherical portion, fuel portion and control rod portion of a nuclear reactor, a rotary type girder is placed on the upper edge of a cylindrical portion remained after the removal of the upper semi-spherical portion. Then, the upper portion of a supporting rod provided with a swing arm having a plasma arc torch at the top end is situated at the center of the reactor main body. Then, the top end of the support rod is inserted to fix in the housing of control rod drives. Then, the swing arm is actuated to situate the plasma arc torch to a desired position to be cut, whereafter cutting is initiated while rotating the rotary type girder. Thus, plasma arc torch is moved horizontally along an arcuate trace, whereby pipeways, accessories or the likes disposed to the inside of the main body are at first cut and then the cylindrical portion constituting the main body is cut to dismantle the reactor. (Moriyama, K.)

  17. Coolant cleanup method in a nuclear reactor

    Kubota, Masayoshi; Nishimura, Shigeoki; Takahashi, Sankichi; Izumi, Kenkichi; Motojima, Kenji.

    1983-01-01

    Purpose : To effectively adsorb to remove low molecular weight organic substances from iron exchange resins for use in the removal of various radioactive nucleides contained in reactor coolants. Method : Reactor coolants are recycled by a main recyling pump in a nuclear reactor and a portion of the coolants is cooled and, thereafter, purified in a coolant desalter. While on the other hand, high pressure steams generated from the reactor are passed through a turbine, cooled in a condensator, eliminated with claddings or the likes by the passage through a filtration desalter using powderous ion exchange resins and then further passed through a desalter (filled with granular ion exchange resins). For instance, an adsorption and removing device for organic substances (resulted through the decomposition of ion exchange resins) precoated with activated carbon powder or filled with granular activated carbon is disposed at the downstream for each of the desalters. In this way, the organic substances in the coolants are eliminated to prevent the reduction in the desalting performance of the ion exchange resins caused by the formation of complexes between organic substances and cobalt in the coolants, etc. In this way, the coolant cleanup performance is increased and the amount of wasted ion exchange resins can be decreased. (Horiuchi, T.)

  18. Hermeneutic and Cultural Codes of S/Z: A Semiological Reading of James Joyce's "The Boarding House"

    Booryazadeh, Seyed Ali; Faghfori, Sohila; Shamsi, Habibe

    2014-01-01

    Roland Barthes as a fervent proponent of semiology believes that semiology is a branch of a comprehensive linguistics: it is the study of how language articulates the world. Semiotic codes, the paths of this articulation, accordingly underlie his attention. Barthes in a structural analysis of Balzac's "Sarrasine" in S/Z expounds five…

  19. A TRIGA reactor in an industrial laboratory

    Anders, Oswald U.

    1980-01-01

    The Dow TRIGA Reactor is a well established facility in its industrial environment. It is used extensively for internal Dow projects. The primary use of the TRIGA is as neutron source for NAA. It faces similar technical and organizational challenges as other TRIGA installations and over the years developed its own solutions

  20. Modeling a nuclear reactor for experimental purposes

    Berta, V.T.

    1980-01-01

    The Loss-of-Fluid Test (LOFT) Facility is a scale model of a commercial PWR and is as fully functional and operational as the generic commercial counterpart. LOFT was designed and built for experimental purposes as part of the overall NRC reactor safety research program. The purpose of LOFT is to assess the capability of reactor safety systems to perform their intended functions during occurrences of off-normal conditions in a commercial nuclear reactor. Off-normal conditions arising from large and small break loss-of-coolant accidents (LOCA), operational transients, and anticipated transients without scram (ATWS) were to be investigated. This paper describes the LOFT model of the generic PWR and summarizes the experiments that have been conducted in the context of the significant findings involving the complex transient thermal-hydraulics and the consequent effects on the commercial reactor analytical licensing techniques. Through these techniques the validity of the LOFT model as a scaled counterpart of the generic PWR is shown

  1. Charging machine for a fast production reactor

    Artem'ev, L.N.; Kurilkin, V.V.

    1971-01-01

    Charging machine for a fast production reactor is described. The machine contains charging mechanism, mechanism for positioning fresh fuel and spent fuel assemtlies, storage drums with sockets for control rod assemtlies and collet tongs for control rods. Recharging is conducted by means of ramp channel

  2. Historical Developments of Pyrolysis Reactors : A Review

    Garcia-Nunez, J. A.; Pelaez-Samaniego, M.R.; Garcia-Perez, M. E.; Fonts, I.; Abrego, J.; Westerhof, R. J.M.; Garcia Perez, M.

    2017-01-01

    This paper provides a review of pyrolysis technologies, focusing on reactor designs and companies commercializing these technologies. The renewed interest in pyrolysis is driven by the potential to convert lignocellulosic materials into bio-oil and biochar and the use of these intermediates for the

  3. Refueling machine for a nuclear reactor

    Kowalski, E.F.; Hornak, L.P.; Swidwa, K.J.

    1981-01-01

    An improved refuelling machine for inserting and removing fuel assemblies from a nuclear reactor is described which has been designed to increase the reliability of such machines. The system incorporates features which enable the refuelling operation to be performed more efficiently and economically. (U.K.)

  4. European blanket development for a demo reactor

    Giancarli, L.; Proust, E.; Anzidei, L.

    1994-01-01

    There are four breeding blanket concepts for a fusion DEMO reactor under development within the framework of the fusion technology programme of the European Union (EU). This paper describes the design of these concepts, the accompanying R + D programme and the status of the development. (authors). 8 figs., 1 tab

  5. A series of lectures on operational physics of power reactors

    Mohanakrishnan, P.; Rastogi, B.P.

    1982-01-01

    This report discusses certain aspects of operational physics of power reactors. These form a lecture series at the Winter College on Nuclear Physics and Reactors, Jan. - March 1980, conducted at the International Centre for Theoretical Physics, Trieste, Italy. The topics covered are (a) the reactor physics aspects of fuel burnup (b) theoretical methods applied for burnup prediction in power reactors (c) interpretation of neutron detector readings in terms of adjacent fuel assembly powers (d) refuelling schemes used in power reactors. The reactor types chosen for the discussion are BWR, PWR and PHWR. (author)

  6. A high temperature reactor for ship propulsion

    Lobet, P.; Seigel, R.; Thompson, A.C.; Beadnell, R.M.; Beeley, P.A.

    2002-01-01

    The initial thermal hydraulic and physics design of a high temperature gas cooled reactor for ship propulsion is described. The choice of thermodynamic cycle and thermal power is made to suit the marine application. Several configurations of a Helium cooled, Graphite moderated reactor are then analysed using the WIMS and MONK codes from AEA Technology. Two geometries of fuel elements formed using micro spheres in prismatic blocks, and various arrangements of control rods and poison rods are examined. Reactivity calculations through life are made and a pattern of rod insertion to flatten the flux is proposed and analysed. Thermal hydraulic calculations are made to find maximum fuel temperature under high power with optimized flow distribution. Maximum temperature after loss of flow and temperatures in the reactor vessel are also computed. The temperatures are significantly below the known limits for the type of fuel proposed. It is concluded that the reactor can provide the required power and lifetime between refueling within likely space and weight constraints. (author)

  7. A Survey of the Origin and Evolution of Religion from the Points of View Edward Tylor and James Frazer

    Alireza khajegir

    2015-01-01

    As a universal human phenomenon, religion is rooted in human nature, and human beings instinctively require a superior and supreme power. Besides this internal need for religion, attention to the meaning, function, and interpretation of religion has always been prevalent in the history of human thought from West to East, and scholars have always tried to comment on and analyze this fundamental issue of human life .  From among the approaches that arose about the interpretation and ex...

  8. Identifying primary care patient safety research priorities in the UK: a James Lind Alliance Priority Setting Partnership.

    Morris, Rebecca Lauren; Stocks, Susan Jill; Alam, Rahul; Taylor, Sian; Rolfe, Carly; Glover, Steven William; Whitcombe, Joanne; Campbell, Stephen M

    2018-02-28

    To identify the top 10 unanswered research questions for primary care patient safety research. A modified nominal group technique. UK. Anyone with experience of primary care including: patients, carers and healthcare professionals. 341 patients and 86 healthcare professionals submitted questions. A top 10, and top 30, future research questions for primary care patient safety. 443 research questions were submitted by 341 patients and 86 healthcare professionals, through a national survey. After checking for relevance and rephrasing, a total of 173 questions were collated into themes. The themes were largely focused on communication, team and system working, interfaces across primary and secondary care, medication, self-management support and technology. The questions were then prioritised through a national survey, the top 30 questions were taken forward to the final prioritisation workshop. The top 10 research questions focused on the most vulnerable in society, holistic whole-person care, safer communication and coordination between care providers, work intensity, continuity of care, suicide risk, complex care at home and confidentiality. This study was the first national prioritisation exercise to identify patient and healthcare professional priorities for primary care patient safety research. The research priorities identified a range of important gaps in the existing evidence to inform everyday practice to address primary care patient safety. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  9. A missiological exploration of Australian missionary James Noble Mackenzie�s ministry to lepers in South Korea

    Sang Pil Son

    2017-01-01

    Full Text Available The history of Australian Presbyterian Mission in Korea (APM is not comprehensive, nor the study of missiology that addresses the marginalised. This study of the ministry of APM missionary, J.N. Mackenzie, to lepers in Japanese-occupied Korea, adds significantly to both these areas. An understanding of the role and methods of Mackenzie�s missionary activities among the marginalised in Korea can encourage today�s Church to effectively restore the marginalised in society, moving from Church doctrine to practical reproduction of the example of Jesus recorded in Mark�s gospel. Using original and published sources, the study examines the social conditions in which Mackenzie found Korean lepers, their historic treatment and government policies and the growth of his holistic mission, with its methods and fruits. Mackenzie�s work is documented with recorded data included to demonstrate its Christ-like effectiveness both spiritually and physically. By tracing Mackenzie�s work with lepers, it is clear that holistic mission can helpfully impact the situation of the most marginalised. Mackenzie�s work expanded dramatically, churches were formed and it even created cured evangelists, making it a useful model for mission work among the marginalised. Mackenzie�s work played a significant part in the Church and National history of Korea and presented a new path in the mission work of APM. It has the potential to influence modern mission in being �as Christ� to the marginalised and thus to impact the society. This study has given a unique perspective on the history and theology of mission to the poor and traditionally powerless in society.Intradisciplinary and/or interdisciplinary implications: Traditional views of history, theology and missiology have focussed on the ruling classes and urban societies. A perspective of the marginalised encourages a shift in these as it can be seen that the rural poor responded to holistic ministry and affected

  10. Electron Paramagnetic Resonance: Elementary Theory and Practical Applications, Second Edition (John A. Weil and James R. Bolton)

    Williams, Ffrancon

    2009-01-01

    The detection of electron magnetic resonance by Zavoiskii in the mid 1940s (1) ushered in a golden age of physical and chemical applications. Perhaps no single book did more to stimulate this development of EPR spectroscopy than the classic text by Wertz and Bolton (2) , which appeared in 1972. A revised version, with John A. Weil added as a co-author, was published by Wiley in 1994. This 2007 text is formally described as the second edition of the 1994 version. Wertz died shortly after the publication of the 1994 edition leaving Weil and Bolton as authors. In noting that the senior author (JAW) takes most of the responsibility for the content of this 2007 version, the Preface refers to it at one point as the "third edition", which of course is precisely how older readers will regard it. The main thrust of the book is decidedly on the physical aspects of EPR, so that it nicely complements the more chemical emphasis provided in the recent comprehensive text by Gerson and Hüber (3) . As the authors remark, the 2007 edition does not differ dramatically from the 1994 version. The titles of the 13 chapters remain the same except for chapter 11, which now refers to the "Noncontinuous" instead of the "Time-Dependent" Excitation of Spins. Recent developments are generally accommodated by a few extra pages in each chapter. Thus, chapter 1 on Basic Principles of Paramagnetic Resonance has been expanded from 31 to 36 pages to introduce the topics of parallel-field EPR, time-resolved EPR, "computerology", and EPR imaging. Chapter 2 on Magnetic Interactions is essentially unchanged while chapter 3 on Isotropic Hyperfine Effects has been expanded to include new sections on Deviations from the Simple Multinomial Scheme (3.7) and Some Interesting π-Type Free Radicals (3.9). Section 3.9 provides a useful corrective to the notion that the EPR method can detect and characterize almost any type of radical species. This welcome touch of realism is nicely illustrated by mentioning

  11. Permanent cavity seal ring for a nuclear reactor containment arrangement

    Swidwa, K.J.; Salton, R.B.; Marshall, J.R.

    1990-01-01

    This patent describes a nuclear reactor containment arrangement. It comprises: a reactor pressure vessel which thermally expands and contracts during cyclic operation of the reactor, the vessel having a peripheral wall and a horizontally outwardly extending flange thereon; a containment wall having a shelf, the wall spaced from and surrounding the peripheral wall of the reactor pressure vessel defining an annular expansion gap therebetween, and an annular ring seal extending across the annular expansion gap to provide a water-tight seal therebetween

  12. Transmutation of actinide 237Np with a fusion reactor and a hybrid reactor

    Feng, K.M.; Huang, J.H.

    1994-01-01

    The use of fusion reactors to transmute fission reactor wastes to stable species is an attractive concept. In this paper, the feasibility of transmutation of the long-lived actinide radioactive waste Np-237 with a fusion reactor and a hybrid reactor has been investigated. A new waste management concept of burning HLW (High Level Waste), utilizing released energy and converting Np-237 into fissile fuel Pu-239 through transmutation has been adopted. The detailed neutronics and depletion calculation of waste inventories was carried out with a modified version of one-dimensional neutron transport and burnup calculation code system BISON1.5 in this study. The transmutation rate of Np with relationship to neutron wall loading, Pu and Np with relationship to neutron wall load, Pu and Np concentration in the transmutation zone have been explored as well as relevant results are also given

  13. Review of Feminist Bioethics At the Center, On the Margins, edited by Jackie Leach Scully, Laurel E. Baldwin-Ragaven, Petya Fitzpatrick

    Sander-Staudt Maureen

    2010-12-01

    Full Text Available Abstract The anthology, Feminist Bioethics, edited by Jackie Leach Scully, Laurel E. Baldwin-Ragaven, and Petya Fitzpatrick, examines how feminist bioethics theoretically and methodologically challenges mainstream bioethics, and whether these approaches are useful for exploring difference in other contexts. It offers critical conceptual analyses of "autonomy", "universality", and "trust", and covers topics such as testing for hereditary cancer, prenatal selection for sexual orientation, midwifery, public health, disability, Indigenous research reform in Australia, and China's one child policy.

  14. Method for filling a reactor with a catalyst

    2013-01-01

    The invention relates to a method for filling a reactor with a catalyst for the carbonylation of carbonylated compounds in the gas phase. According to said method, a SILP catalyst is covered with a filling agent which is liquid under normal conditions and is volatile under carbonylation reaction...... conditions, and a thus-treated catalyst is introduced into the reactor and the reactor is sealed....

  15. Modelling of a falling sludge bed reactor using AQUASIM | Ristow ...

    Modelling of a falling sludge bed reactor using AQUASIM. ... AFRICAN JOURNALS ONLINE (AJOL) · Journals · Advanced Search · USING AJOL · RESOURCES ... a system of mixed reactors connected by water flow and mass flux streams.

  16. A comparison of radioactive waste from first generation fusion reactors and fast fission reactors with actinide recycling

    Koch, M.; Kazimi, M.S.

    1991-04-01

    Limitations of the fission fuel resources will presumably mandate the replacement of thermal fission reactors by fast fission reactors that operate on a self-sufficient closed fuel cycle. This replacement might take place within the next one hundred years, so the direct competitors of fusion reactors will be fission reactors of the latter rather than the former type. Also, fast fission reactors, in contrast to thermal fission reactors, have the potential for transmuting long-lived actinides into short-lived fission products. The associated reduction of the long-term activation of radioactive waste due to actinides makes the comparison of radioactive waste from fast fission reactors to that from fusion reactors more rewarding than the comparison of radioactive waste from thermal fission reactors to that from fusion reactors. Radioactive waste from an experimental and a commercial fast fission reactor and an experimental and a commercial fusion reactor has been characterized. The fast fission reactors chosen for this study were the Experimental Breeder Reactor 2 and the Integral Fast Reactor. The fusion reactors chosen for this study were the International Thermonuclear Experimental Reactor and a Reduced Activation Ferrite Helium Tokamak. The comparison of radioactive waste parameters shows that radioactive waste from the experimental fast fission reactor may be less hazardous than that from the experimental fusion reactor. Inclusion of the actinides would reverse this conclusion only in the long-term. Radioactive waste from the commercial fusion reactor may always be less hazardous than that from the commercial fast fission reactor, irrespective of the inclusion or exclusion of the actinides. The fusion waste would even be far less hazardous, if advanced structural materials, like silicon carbide or vanadium alloy, were employed

  17. A comparison of radioactive waste from first generation fusion reactors and fast fission reactors with actinide recycling

    Koch, M.; Kazimi, M.S.

    1991-04-01

    Limitations of the fission fuel resources will presumably mandate the replacement of thermal fission reactors by fast fission reactors that operate on a self-sufficient closed fuel cycle. This replacement might take place within the next one hundred years, so the direct competitors of fusion reactors will be fission reactors of the latter rather than the former type. Also, fast fission reactors, in contrast to thermal fission reactors, have the potential for transmuting long-lived actinides into short-lived fission products. The associated reduction of the long-term activation of radioactive waste due to actinides makes the comparison of radioactive waste from fast fission reactors to that from fusion reactors more rewarding than the comparison of radioactive waste from thermal fission reactors to that from fusion reactors. Radioactive waste from an experimental and a commercial fast fission reactor and an experimental and a commercial fusion reactor has been characterized. The fast fission reactors chosen for this study were the Experimental Breeder Reactor 2 and the Integral Fast Reactor. The fusion reactors chosen for this study were the International Thermonuclear Experimental Reactor and a Reduced Activation Ferrite Helium Tokamak. The comparison of radioactive waste parameters shows that radioactive waste from the experimental fast fission reactor may be less hazardous than that from the experimental fusion reactor. Inclusion of the actinides would reverse this conclusion only in the long-term. Radioactive waste from the commercial fusion reactor may always be less hazardous than that from the commercial fast fission reactor, irrespective of the inclusion or exclusion of the actinides. The fusion waste would even be far less hazardous, if advanced structural materials, like silicon carbide or vanadium alloy, were employed.

  18. Reactor FaceMap Tool: A modern graphics tool for displaying reactor data

    Roberts, J.C.

    1991-01-01

    A prominent graphical user interface in reactor physics applications at the Savannah River Site is the reactor facemap display. This is a two dimensional view of a cross section of a reactor. In the past each application which needed a facemap implemented its own version. Thus, none of the code was reused, the facemap implementation was hardware dependent and the user interface was different for each facemap. The Reactor FaceMap Tool was built to solve these problems. Through the use of modern computing technologies such as X Windows, object-oriented programming and client/server technology the Reactor FaceMap Tool has the flexibility to work in many diverse applications and the portability to run on numerous types of hardware

  19. Containment vessel for a nuclear reactor

    Yamanari, Sh.; Horiuchi, T.; Sugisaki, T.; Tominaga, K.

    1985-01-01

    A containment vessel for a nuclear reactor having a dry well for mounting therein a pressure vessel for containing the nuclear reactor, a pressure suppressing chamber having a pool of coolant therein, and a vent pipe device for releasing therethrough into the pool of coolant within the pressure suppressing chamber steam which will be produced as a result of the occurrence of an accident and escape into the dry well. The vent pipe device includes a plurality of vent pipe members inserted in the pool of coolant within the pressure suppressing chamber and each having at least one exhaust port opening in the coolant. The vent pipe members are divided into a plurality of groups in such a manner that the vent pipe members of different groups differ from one another in the length of submerged portions of the vent pipe members interposed between the liquid of the coolant within the pressure suppressing chamber and the exhaust ports of the vent pipe members

  20. Control of PWR reactor energy supplied to a stream turbine

    Petetrot, J.F.; Parent, Pierre.

    1981-01-01

    This patent presents a process for regulating the power provided by a pressurized water nuclear reactor to a steam turbine, by moving the control rods absorbing the neutrons in the reactor core and by diverting a fraction of the steam produced by the reactor, outside the turbine circuit, by opening by-pass valves [fr

  1. Development of a system model for advanced small modular reactors.

    Lewis, Tom Goslee,; Holschuh, Thomas Vernon,

    2014-01-01

    This report describes a system model that can be used to analyze three advance small modular reactor (SMR) designs through their lifetime. Neutronics of these reactor designs were evaluated using Monte Carlo N-Particle eXtended (MCNPX/6). The system models were developed in Matlab and Simulink. A major thrust of this research was the initial scoping analysis of Sandias concept of a long-life fast reactor (LLFR). The inherent characteristic of this conceptual design is to minimize the change in reactivity over the lifetime of the reactor. This allows the reactor to operate substantially longer at full power than traditional light water reactors (LWRs) or other SMR designs (e.g. high temperature gas reactor (HTGR)). The system model has subroutines for lifetime reactor feedback and operation calculations, thermal hydraulic effects, load demand changes and a simplified SCO2 Brayton cycle for power conversion.

  2. Taking into account a reactivity accident in research reactors design

    Abou Yehia, H.; Berry, J.L.; Sinda, T.

    1989-11-01

    The particular studies realized in France for research reactors design at a Borax accident type are described. The cases of ORPHEE and RHF reactors are particularly developed. The evolution of the studies and the conservatism used are given [fr

  3. A parameter set for a double-null DEMO reactor

    Cooke, P.I.H.

    1987-01-01

    The present study is aimed at commenting on the reactor-relevance of the design principles and technology being proposed for NET. The authors propose that a double-null device serve as a basis for a NET-based demonstration reactor. Calculations are carried out to determine the parameter set for reactors based on the double-null NET design, and the results are presented in tabular form. (U.K.)

  4. Closure head for a nuclear reactor

    Wade, E.E.

    1980-01-01

    A closure head for a nuclear reactor includes a stationary outer ring integral with the reactor vessel with a first rotatable plug disposed within the stationary outer ring and supported from the stationary outer ring by a bearing assembly. A sealing system is associated with the bearing assembly to seal the annulus defined between the first rotatable plug and the stationary outer ring. The sealing system comprises tubular seal elements disposed in the annulus with load springs contacting the tubular seal elements so as to force the tubular seal elements against the annulus in a manner to seal the annulus. The sealing system also comprises a sealing fluid which is pumped through the annulus and over the tubular seal elements causing the load springs to compress thereby reducing the friction between the tubular seal elements and the rotatable components while maintaining a gas-tight seal therebetween

  5. Density variations in a reactor during liquid full dimerization

    Golombok, M.; Bruijn, J.

    2000-01-01

    In a liquid full plug flow reactor during lower olefin dimerization, the assumption of constant density is not valid—the volume of a plug changes as it proceeds along the reactor. The observed kinetics depend on the density variation in the reactor as the conversion proceeds towards a distribution

  6. Identifying trial recruitment uncertainties using a James Lind Alliance Priority Setting Partnership - the PRioRiTy (Prioritising Recruitment in Randomised Trials) study.

    Healy, Patricia; Galvin, Sandra; Williamson, Paula R; Treweek, Shaun; Whiting, Caroline; Maeso, Beccy; Bray, Christopher; Brocklehurst, Peter; Moloney, Mary Clarke; Douiri, Abdel; Gamble, Carrol; Gardner, Heidi R; Mitchell, Derick; Stewart, Derek; Jordan, Joan; O'Donnell, Martin; Clarke, Mike; Pavitt, Sue H; Guegan, Eleanor Woodford; Blatch-Jones, Amanda; Smith, Valerie; Reay, Hannah; Devane, Declan

    2018-03-01

    Despite the problem of inadequate recruitment to randomised trials, there is little evidence to guide researchers on decisions about how people are effectively recruited to take part in trials. The PRioRiTy study aimed to identify and prioritise important unanswered trial recruitment questions for research. The PRioRiTy study - Priority Setting Partnership (PSP) included members of the public approached to take part in a randomised trial or who have represented participants on randomised trial steering committees, health professionals and research staff with experience of recruiting to randomised trials, people who have designed, conducted, analysed or reported on randomised trials and people with experience of randomised trials methodology. This partnership was aided by the James Lind Alliance and involved eight stages: (i) identifying a unique, relevant prioritisation area within trial methodology; (ii) establishing a steering group (iii) identifying and engaging with partners and stakeholders; (iv) formulating an initial list of uncertainties; (v) collating the uncertainties into research questions; (vi) confirming that the questions for research are a current recruitment challenge; (vii) shortlisting questions and (viii) final prioritisation through a face-to-face workshop. A total of 790 survey respondents yielded 1693 open-text answers to 6 questions, from which 1880 potential questions for research were identified. After merging duplicates, the number of questions was reduced to 496. Questions were combined further, and those that were submitted by fewer than 15 people and/or fewer than 6 of the 7 stakeholder groups were excluded from the next round of prioritisation resulting in 31 unique questions for research. All 31 questions were confirmed as being unanswered after checking relevant, up-to-date research evidence. The 10 highest priority questions were ranked at a face-to-face workshop. The number 1 ranked question was "How can randomised trials become

  7. Refueling system for a nuclear reactor

    Koschkin, J.N.; Ordynskij, G.V.; Schchijan, C.G.; Schapkin, A.F.; Fadeev, A.I.; Laptev, F.V.; Batjukov, V.I.; Korolkov, K.I.; Borodin, I.V.; Tschernomordik, E.N.

    1979-01-01

    With the refueling system fuel elements are transferred from the intermediate distributing chamber within the fast breeder reactor vessel to the storage tanks for new and irradiated fuel elements outside of the reactor vessel and vice versa. It consists of a hermetic chamber, filled with inert gas, within which the refueling machine, having got a vertical swing pipe, is placed. On the swing pipe there is mounted by means of a bracket a hanging support tube for a tube manipulator that can be moved over the openings to the fuel elements. At the end of the tube manipulator there is a gripping device whose drive mechanism is arranged within the support tube. The swing pipe is moved by means of a drive mechanism outside of the chamber. (DG) [de

  8. Setting research priorities to improve the health of children and young people with neurodisability: a British Academy of Childhood Disability-James Lind Alliance Research Priority Setting Partnership.

    Morris, Christopher; Simkiss, Doug; Busk, Mary; Morris, Maureen; Allard, Amanda; Denness, Jacob; Janssens, Astrid; Stimson, Anna; Coghill, Joanna; Robinson, Kelly; Fenton, Mark; Cowan, Katherine

    2015-01-28

    To engage young people, parent carers and clinicians in a systematic process to identify and prioritise research questions regarding ways to improve the health and well-being of children and young people with neurodisability. British Academy of Childhood Disability (BACD)-James Lind Alliance research priority setting partnership bringing together patients, carers and clinicians as equal stakeholders. UK health service and community. The BACD Strategic Research Group formed the partnership. A Steering Group was established; charity and professional partner organisations were recruited. Suggestions were gathered in an open survey and from research recommendations for statutory guidance. Items were aggregated to formulate indicative research questions and verified as uncertainties from research evidence. An interim survey was used to rank the questions to shortlist topics. A mixed group of stakeholders discussed the top 25 questions at the final priority setting workshop agreeing a final rank order and the top 10 research priorities. Partner organisations were 13 charities and 8 professional societies. 369 people submitted suggestions (40% non-clinicians). 76 people participated in the interim prioritisation (26 parents, 1 young person, 10 charity representatives, 39 clinicians); 22 took part in the final workshop (3 young people, 7 parents, 3 charity representatives, 9 professionals). The top three research priorities related to (1) establishing the optimal frequency and intensity (dose) for mainstream therapies, (2) means for selecting and encouraging use of communication strategies and (3) ways to improve children's attitudes towards disability. The top 10 included evaluating interventions to promote mobility, self-efficacy, mental health, continence, physical fitness, educational inclusion and reduce impacts of sleep disturbance. The methodology provided a systematic and transparent process to identify research priorities that included stakeholders that have

  9. A fast spectrum dual path flow cermet reactor

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

    1993-01-01

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

  10. A small research reactor for the 1980's

    Baglin, C.; Collis-Smith, J.A.; Mitchell, B.; Roskilly, T.

    1978-01-01

    In 1960, GEC together with Imperial College, designed and built the Consort reactor which is still in daily use at the London University Reactor Centre, Silwood Park. In 1977, GEC-REL chose the Consort reactor as a prototype for the development of a modern swimming pool research reactor, designed to meet the needs of countries or organisations starting in the field of Nuclear Technology. This paper outlines some of the topics which arose in the course of this project. (author)

  11. RSMASS: A simple model for estimating reactor and shield masses

    Marshall, A.C.; Aragon, J.; Gallup, D.

    1987-01-01

    A simple mathematical model (RSMASS) has been developed to provide rapid estimates of reactor and shield masses for space-based reactor power systems. Approximations are used rather than correlations or detailed calculations to estimate the reactor fuel mass and the masses of the moderator, structure, reflector, pressure vessel, miscellaneous components, and the reactor shield. The fuel mass is determined either by neutronics limits, thermal/hydraulic limits, or fuel damage limits, whichever yields the largest mass. RSMASS requires the reactor power and energy, 24 reactor parameters, and 20 shield parameters to be specified. This parametric approach should be applicable to a very broad range of reactor types. Reactor and shield masses calculated by RSMASS were found to be in good agreement with the masses obtained from detailed calculations

  12. Dynamic simulation platform to verify the performance of the reactor regulating system for a research reactor

    NONE

    2015-07-01

    Digital instrumentation and controls system technique is being introduced in new constructed research reactor or life extension of older research reactor. Digital systems are easy to change and optimize but the validated process for them is required. Also, to reduce project risk or cost, we have to make it sure that configuration and control functions is right before the commissioning phase on research reactor. For this purpose, simulators have been widely used in developing control systems in automotive and aerospace industries. In these literatures, however, very few of these can be found regarding test on the control system of research reactor with simulator. Therefore, this paper proposes a simulation platform to verify the performance of RRS (Reactor Regulating System) for research reactor. This simulation platform consists of the reactor simulation model and the interface module. This simulation platform is applied to I and C upgrade project of TRIGA reactor, and many problems of RRS configuration were found and solved. And it proved that the dynamic performance testing based on simulator enables significant time saving and improves economics and quality for RRS in the system test phase. (authors)

  13. Space perception and William James's metaphysical presuppositions.

    Farrell, Martin J

    2011-05-01

    William James's overtly philosophical work may be more continuous with his psychological work than is sometimes thought. His Essays in Radical Empiricism can be understood as an explicit statement of the absolute presupposition that formed the basis of Jamesian psychology: that direct experience is primary and has to be taken at face value. An examination of James's theory of space perception suggests that, even in his early work, he presupposed the primacy of direct experience, and that later changes in his account of space perception can be understood as making his view more consistent with this presupposition. In his earlier view of space perception, James argued that sensations were directly experienced as spatial, though he accepted that spatial relations between sensations may be constructed by higher order thought. In his later view, however, James argued that spatial relations were just as directly experienced as sensations. The work of T. H. Green may have prompted James to recognize the full consequence of his ideas and to realize that taking experience at face value required that spatial relations be thought of as intrinsic to experience rather than the result of intellectual construction.

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

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

    1975-01-01

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

  15. Apparatus for simulating a reactor core

    Yokomizo, Osamu; Kiguchi, Takashi; Motoda, Hiroshi; Takeda, Renzo.

    1975-01-01

    Object: To facilitate searching of input and output of information and to efficiently perform trial-and-error in a short time. Structure: Kinds of necessary input information are stored in an input information converter and are displayed by an image display through an image control. An operator operates an information input device to input information. This input information is converted by the input information converter into a form used in a reactor core simulation counter. The reactor core simulation counter simulates a state of the core to the input information converted, and outputs it as an output information. An output information converter converts output information into a form that may be displayed as an image and feeds it to the image control. The operator may correct the input information while viewing the output information displayed on the image display to immediately perform succeeding calculation. (Kamimura, M.)

  16. Analysis of a molten salt reactor benchmark

    Ghosh, Biplab; Bajpai, Anil; Degweker, S.B.

    2013-01-01

    This paper discusses results of our studies of an IAEA molten salt reactor (MSR) benchmark. The benchmark, proposed by Japan, involves burnup calculations of a single lattice cell of a MSR for burning plutonium and other minor actinides. We have analyzed this cell with in-house developed burnup codes BURNTRAN and McBURN. This paper also presents a comparison of the results of our codes and those obtained by the proposers of the benchmark. (author)

  17. Dynamic model for a boiling water reactor

    Muscettola, M.

    1963-07-01

    A theoretical formulation is derived for the dynamics of a boiling water reactor of the pressure tube and forced circulation type. Attention is concentrated on neutron kinetics, fuel element heat transfer dynamics, and the primary circuit - that is the boiling channel, riser, steam drum, downcomer and recirculating pump of a conventional La Mont loop. Models for the steam and feedwater plant are not derived. (author)

  18. Radiation protection in a university TRIGA reactor

    Tschurlovits, M. . Author

    2004-01-01

    Radiation protection in a university institute operating a research reactor and other installations has different constraints as a larger facility. This is because the legal requirements apply in full, but the potential of exposure is low, and accesses has to be made available for students, but also for temporary workers. Some of the problems in practical radiation protection are addressed and solutions are discussed. In addition, experience with national radiation protection legislation recently to be issued is addressed and discussed. (author)

  19. Control unit of a nuclear reactor

    Desfontaines, Guy; Le Helloco, Michel.

    1981-01-01

    Control unit comprising multiple leak-tight vessels, in communication with the inside of the reactor vessel, extending this vessel above its cover, in the vertical direction and each one enclosing a mechanism for moving a cluster of material absorbing the neutrons in the reactor core, actuated by a motor. This control unit is of reduced height above the vessel cover and provides efficient protection of the leak tight containments and the mechanisms in the event of earthquakes, easy removal and refitting of the vessel cover, good ventilation of the power devices of the mechanisms without the use of a complex ventilation system, efficient thermal insulation of the leak-tight containments assembly, as well as easy access to the motors and mechanism located in the leak-tight containment for carrying out any maintenance and repairs that might be required [fr

  20. A resting bottom sodium cooled fast reactor

    Costes, D.

    2012-01-01

    This follows ICAPP 2011 paper 11059 'Fast Reactor with a Cold Bottom Vessel', on sodium cooled reactor vessels in thermal gradient, resting on soil. Sodium is frozen on vessel bottom plate, temperature increasing to the top. The vault cover rests on the safety vessel, the core diagrid welded to a toric collector forms a slab, supported by skirts resting on the bottom plate. Intermediate exchangers and pumps, fixed on the cover, plunge on the collector. At the vessel top, a skirt hanging from the cover plunges into sodium, leaving a thin circular slit partially filled by sodium covered by argon, providing leak-tightness and allowing vessel dilatation, as well as a radial relative holding due to sodium inertia. No 'air conditioning' at 400 deg. C is needed as for hanging vessels, and this allows a large economy. The sodium volume below the slab contains isolating refractory elements, stopping a hypothetical corium flow. The small gas volume around the vessel limits any LOCA. The liner cooling system of the concrete safety vessel may contribute to reactor cooling. The cold resting bottom vessel, proposed by the author for many years, could avoid the complete visual inspection required for hanging vessels. However, a double vessel, containing support skirts, would allow introduction of inspecting devices. Stress limiting thermal gradient is obtained by filling secondary sodium in the intermediate space. (authors)

  1. Coolant cleanup system for a nuclear reactor

    Shiina, Atsushi; Usui, Naoshi; Yamamoto, Michiyoshi; Osumi, Katsumi.

    1983-01-01

    Purpose: To maintain the electric conductivity of reactor water lower and to minimize the heat loss in the cleanup system by providing a low temperature cleanup system and a high temperature cleanup system together. Constitution: A low temperature cleanup system using ion exchange resins as filter aids and a high temperature cleanup system using inorganic ion exchange materials as filter aids are provided in combination. A part of the reactor water in a reactor pressure vessel is passed through a conductivity meter, one portion of which flows into the high temperature cleanup system having no heat exchanger and filled with inorganic ion exchange materials by way of a first flow rate control valve and the other portion of which flows into the low temperature cleanup system having heat exchangers and filled with the ion exchange materials by way of a second control valve. The first control valve is adjusted so as to flow, for example, about more than 15% of the feedwater flow rate to the high temperature cleanup system and the second control valve is adjusted with its valve opening degree depending on the indication of the conductivity meter so as to flow about 2 - 7 % of the feedwater flow rate into the low temperature cleanup system, to thereby control the electric conductivity to between 0.055 - 0.3 μS/cm. (Moriyama, K.)

  2. A low cost liquid metal reactor design

    Arnold, W.H.; Anderson, C.A.; Mangus, J.D.

    1984-01-01

    A new, compact Liquid Metal Reactor (LMR) plant arrangement designed by Westinghouse, featuring factory-fabricated modules and an integrated fuel cycle facility, has made it possible to project a commercially competitive LMR plant for the near future. This innovative liquid metal-cooled plant design will allow a combination of capital, fuel, operation and maintenance costs that could be lower than today's fossil-fueled or light water reactor plant costs, and incorporate features which enhance public safety even beyond current high standards. Following early core loadings, the plant feeds only on depleted uranium. No shipment of fuel is required. And the plant can be tailored to produce enough plutonium to meet its need or to provide fuel for other nuclear plants

  3. WRAP: a water reactor analysis package

    Anderson, M.M.

    1977-06-01

    The modular computational system known as the Water Reactor Analysis Package (WRAP) has been developed at the Savannah River Laboratory. WRAP is essentially a reprogrammed version of the RELAP4 computer code with an extensively restructured input format, a dynamic dimensioning capability and additional computational capabilities such as an automatic steady-state option for pressurized water reactors and an automatic restart capability with provision for renodalization. The report describes the capabilities of WRAP at its current stage of development. The addition of new capabilities (e.g., a BWR steady-state capability), the inclusion of improved models (e.g., models in RELAP4/M0D8) and the development of improved numerical techniques to reduce execution time are being planned at this time

  4. Muon trackers for imaging a nuclear reactor

    Kume, N.; Miyadera, H.; Morris, C. L.; Bacon, J.; Borozdin, K. N.; Durham, J. M.; Fuzita, K.; Guardincerri, E.; Izumi, M.; Nakayama, K.; Saltus, M.; Sugita, T.; Takakura, K.; Yoshioka, K.

    2016-09-01

    A detector system for assessing damage to the cores of the Fukushima Daiichi nuclear reactors by using cosmic-ray muon tomography was developed. The system consists of a pair of drift-tube tracking detectors of 7.2× 7.2-m2 area. Each muon tracker consists of 6 x-layer and 6 y-layer drift-tube detectors. Each tracker is capable of measuring muon tracks with 12 mrad angular resolutions, and is capable of operating under 50-μ Sv/h radiation environment by removing gamma induced background with a novel time-coincidence logic. An estimated resolution to observe nuclear fuel debris at Fukushima Daiichi is 0.3 m when the core is imaged from outside the reactor building.

  5. A nuclear reactor for district heating

    Bancroft, A.R.; Fenton, N.

    1989-07-01

    Global energy requirements are expected to double over the next 40 years. In the northern hemisphere, many countries consume in excess of 25 percent of their primary energy supply for building heating. Satisfying this need, within the constraints now being acknowledged for sustainable global development, provides an important opportunity for district heating. Fuel-use flexibility, energy and resource conservation, and reduced atmospheric pollution from acid gases and greenhouse gases, are important features offered by district heating systems. Among the major fuel options, only hydro-electricity and nuclear heat completely avoid emissions of combustion gases. To fill the need for an economical nuclear heat source, Atomic Energy of Canada Limited has designed a 10 MW plant that is suitable as a heat source within a network or as the main supply to large individual users. Producing hot water at temperatures below 100 degrees C, it incorporates a small pool-type reactor based on AECL's successful SLOWPOKE Research Reactor. A 2 MW prototype for the commercial unit is now being tested at the Whiteshell Nuclear Research Establishment in Manitoba. With capital costs of $7 million (Canadian), unit energy costs are projected to be $0.02/kWh for a 10 MW unit operating in a heating grid over a 30-year period. By keeping the reactor power low and the water temperature below 100 degrees C, much of the complexity of the large nuclear power plants can be avoided, thus allowing these small, safe nuclear heating systems to be economically viable

  6. Programming for a nuclear reactor instrument simulation

    Cohn, C.

    1988-01-01

    This note discusses 8086/8087 machine-language programming for simulation of nuclear reactor instrument current inputs by means of a digital-analog converter (DAC) feeding a bank of series input resistors. It also shows FORTRAN programming for generating the parameter tales used in the simulation. These techniques would be generally useful for high-speed simulation of quantities varying over many orders of magnitude

  7. COMPRESS - a computerized reactor safety system

    Vegh, E.

    1986-01-01

    The computerized reactor safety system, called COMPRESS, provides the following services: scram initiation; safety interlockings; event recording. The paper describes the architecture of the system and deals with reliability problems. A self-testing unit checks permanently the correct operation of the independent decision units. Moreover the decision units are tested by short pulses whether they can initiate a scram. The self-testing is described in detail

  8. A review of the UK fast reactor programme

    Picker, C.; Ainsworth, K.F.

    1996-01-01

    The general position with regard to nuclear power and fast reactors in UK during 1995 is described. The status of fast reactor studies made in UK is outlined and a description and statement regarding the conclusions of the programme of studies associated with the closure of the Prototype Fast Reactor is included. (author)

  9. A review of the UK fast reactor programme

    Picker, C [AEA Technolgy plc, Risley, Warrington, Cheshire (United Kingdom); Ainsworth, K F [British Nuclear Fuels plc, Sellafield, Cumbria (United Kingdom)

    1996-07-01

    The general position with regard to nuclear power and fast reactors in UK during 1995 is described. The status of fast reactor studies made in UK is outlined and a description and statement regarding the conclusions of the programme of studies associated with the closure of the Prototype Fast Reactor is included. (author)

  10. The fast reactor and electricity supply, a utility view

    Wright, J.K.; Hall, R.S.; Kemmish, W.B.; Thorne, R.T.

    1982-01-01

    The significance of the fast reactor is discussed from the viewpoint of the Central Electricity Generating Board. The need for the fast reactor and a possible timescale for its introduction are examined. It is emphasised that demonstration of the commercial and environmental acceptability of the fuel cycle will be needed before any commitment can be made to fast reactors. (U.K.)

  11. PERFORMANCE IMPROVEMENT OF A CHEMICAL REACTOR BY NONLINEAR NATURAL OSCILLATIONS

    RAY, AK

    1995-01-01

    The dynamic behaviour of two coupled continuous stirred tank reactors in sequence is studied when the first reactor is being operated under limit cycle regimes producing self-sustained natural oscillations. The periodic output from the first reactor is then used as a forced input into the second

  12. How much does a tokamak reactor cost?

    Freidberg, J.; Cerfon, A.; Ballinger, S.; Barber, J.; Dogra, A.; McCarthy, W.; Milanese, L.; Mouratidis, T.; Redman, W.; Sandberg, A.; Segal, D.; Simpson, R.; Sorensen, C.; Zhou, M.

    2017-10-01

    The cost of a fusion reactor is of critical importance to its ultimate acceptability as a commercial source of electricity. While there are general rules of thumb for scaling both overnight cost and levelized cost of electricity the corresponding relations are not very accurate or universally agreed upon. We have carried out a series of scaling studies of tokamak reactor costs based on reasonably sophisticated plasma and engineering models. The analysis is largely analytic, requiring only a simple numerical code, thus allowing a very large number of designs. Importantly, the studies are aimed at plasma physicists rather than fusion engineers. The goals are to assess the pros and cons of steady state burning plasma experiments and reactors. One specific set of results discusses the benefits of higher magnetic fields, now possible because of the recent development of high T rare earth superconductors (REBCO); with this goal in mind, we calculate quantitative expressions, including both scaling and multiplicative constants, for cost and major radius as a function of central magnetic field.

  13. A new high performance research reactor

    Abbate, Pablo M.

    2002-01-01

    A contract for the design, construction and commissioning of the Replacement Research Reactor was signed in July 2000 between Australia authorities and INVAP from Argentina. Since then the detailed design has been completed, an application for a construction license was made in May 2001 and the construction authorisation was issued on 4 th April 2002. This paper explains the safety philosophy embedded into the design together with the approach taken for main elements of the design and their relation to the proposed applications of the reactor. Also information is provided on the suit of neutron beam facilities and irradiation facilities being constructed. Finally it is presented an outline of the project management organisation, project planing and schedule. (author)

  14. A stereoscopic television system for reactor inspection

    Friend, D.B.; Jones, A.

    1980-03-01

    A stereoscopic television system suitable for reactor inspection has been developed. Right and left eye views, obtained from two conventional black and white cameras, are displayed by the anaglyph technique and observers wear appropriately coloured viewing spectacles. All camera functions, such as zoom, focus and toe-in are remotely controlled. A laboratory experiment is described which demonstrates the increase in spatial awareness afforded by the use of stereo television and illustrates its potential in the supervision of remote handling tasks. Typical depth resolutions of 3mm at 1m and 10mm at 2m have been achieved with the reactor instrument. Trials undertaken during routine inspection at Oldbury Power Station in June 1978 are described. They demonstrate that stereoscopic television can indeed improve the convenience of remote handling and that the added display realism is beneficial in visual inspection. (author)

  15. Fault tree analysis of a research reactor

    Hall, J.A.; O'Dacre, D.F.; Chenier, R.J.; Arbique, G.M.

    1986-08-01

    Fault Tree Analysis Techniques have been used to assess the safety system of the ZED-2 Research Reactor at the Chalk River Nuclear Laboratories. This turned out to be a strong test of the techniques involved. The resulting fault tree was large and because of inter-links in the system structure the tree was not modularized. In addition, comprehensive documentation was required. After a brief overview of the reactor and the analysis, this paper concentrates on the computer tools that made the job work. Two types of tools were needed; text editing and forms management capability for large volumes of component and system data, and the fault tree codes themselves. The solutions (and failures) are discussed along with the tools we are already developing for the next analysis

  16. Shield structure for a nuclear reactor

    Rouse, C.A.; Simnad, M.T.

    1979-01-01

    An improved nuclear reactor shield structure is described for use where there are significant amounts of fast neutron flux above an energy level of approximately 70 keV. The shield includes structural supports and neutron moderator and absorber systems. A portion at least of the neutron moderator material is magnesium oxide either alone or in combination with other moderator materials such as graphite and iron. (U.K.)

  17. Borax accident in a nuclear reactor

    Carvalho, E.C.

    1978-05-01

    The basic equations of fluid mechanics were used to describe the propagation of a shock wave in the fluid. Using the linear theory of pertubation the pressure distributions were obtained and consequently stress and strain were determined in the wall of the cylindrical tank, and also the expansion of the vapour sphire generated at the explosions in the core of the reactor was obtained [pt

  18. Neutrinos oscillations researches near a nuclear reactor

    Laiman, M.

    1999-01-01

    This thesis deals with the research of neutrinos oscillations near the Chooz B nuclear power plant in the Ardennes. The first part presents the framework of the researches and the chosen detector. The second part details the antineutrinos flux calculus from the reactors and the calculus of the expected events. The analysis procedure is detailed in the last part from the calibration to the events selection. (A.L.B.)

  19. Cable handling system for use in a nuclear reactor

    Crosgrove, R.O.; Larson, E.M.; Moody, E.

    1982-01-01

    A cable handling system for use in an installation such as a nuclear reactor is disclosed herein along with relevant portions of the reactor which, in a preferred embodiment, is a liquid metal fast breeder reactor. The cable handling system provides a specific way of interconnecting certain internal reactor components with certain external components, through an assembly of rotatable plugs. Moreover, this is done without having to disconnect these components from one another during rotation of the plugs and yet without interfering with other reactor components in the vicinity of the rotating plugs and cable handling system

  20. Permanent seal ring for a nuclear reactor cavity

    Hankinson, M.F.; Marshall, J.R.

    1988-01-01

    A nuclear reactor containment arrangement is described including: a. a reactor vessel which thermally expands and contracts during cyclic operation of the reactor and which has a peripheral wall; b. a containment wall spaced apart from and surrounding the peripheral wall of the reactor vessel and defining an annular thermal expansion gap therebetween for accommodating thermal expansion; and c. an annular ring seal which sealingly engages and is affixed to and extends between the peripheral wall of the reactor vessel and the containment wall

  1. Bacterial pathogens in a reactor cooling reservoir

    Kasweck, K.L.; Fliermans, C.B.

    1978-01-01

    The results of the sampling in both Par Pond and Clark Hill Reservoir are given. The frequency of isolation is a qualitative parameter which indicates how often the specified bacterium was isolated from each habitat. Initial scoping experiments demonstrated that a wider variety of pathogenic bacteria occur in Par Pond than in Clark Hill Reservoir. Such findings are interesting because Par Pond does not receive any human wastes directly, yet bacteria generally associated with human wastes are more frequently isolated from Par Pond. Previous studies have demonstrated that certain non-spore-forming enteric bacteria do not survive the intense heat associated with the cooling water when the reactor is operating. However, even when the reactor is not operating, cooling water, consisting of 10% makeup water from Savannah River, continues to flow into Par Pond. This flow provides a source of bacteria which inoculate Par Pond. Once the reactor is again operating, these same bacteria appear to be able to survive and grow within the Par Pond system. Thus, Par Pond and the associated lakes and canals of the Par Pond system provide a pool of pathogens that normally would not survive in natural waters

  2. Medical Radioisotopes Production Without A Nuclear Reactor

    Van der Keur, H.

    2010-05-15

    This report is answering the key question: Is it possible to ban the use of research reactors for the production of medical radioisotopes? Chapter 2 offers a summarized overview on the history of nuclear medicine. Chapter 3 gives an overview of the basic principles and understandings of nuclear medicine. The production of radioisotopes and its use in radiopharmaceuticals as a tracer for imaging particular parts of the inside of the human body (diagnosis) or as an agent in radiotherapy. Chapter 4 lists the use of popular medical radioisotopes used in nuclear imaging techniques and radiotherapy. Chapter 5 analyses reactor-based radioisotopes that can be produced by particle accelerators on commercial scale, other alternatives and the advantages of the cyclotron. Chapter 6 gives an overview of recent developments and prospects in worldwide radioisotopes production. Chapter 7 presents discussion, conclusions and recommendations, and is answering the abovementioned key question of this report: Is it possible to ban the use of a nuclear reactor for the production of radiopharmaceuticals? Is a safe and secure production of radioisotopes possible?.

  3. Knowing More by Knowing Less? A Reading of Give Me Everything You Have. On Being Stalked by James Lasdun, London: Jonathan Cape, 2013.

    Armstrong, Neil

    2017-09-01

    James Lasdun's memoir of being stalked, Give Me Everything You Have, has provoked considerable controversy. Whilst the quality of the writing is widely praised, some critics object to the way Lasdun documents in unsparing detail his experiences without taking any account of the stalker's apparent mental health problems. There are ethical and conceptual problems with Lasdun's approach, but side-stepping medical knowledge and relying on what we might call common sense help Lasdun to find ways to interpret his stalker's actions as meaningful and human. I suggest three interlinked implications concerning: medicalization, stigma, and the relationship between ethics and scientific knowledge.

  4. Method of operating a nuclear reactor

    Gyorey, G.L.; Parkos, G.R.; Roupe, G.A.; Thomson, O.A.; Crowther, R.L.

    1979-01-01

    The invention concerns the configuration of control rods in the lattice of the reactor core, as well as an instruction on the sequence of with drawal for the control rods, arranged in groups, in order to achieve for the control rod reactivity of the control rods remaining in the reactor core to adopt the lowest possible value. The rods are combined in several 3 x 3 matrices which in their turn are grouped into two networks. The groups are moved successively according to a specified schedule. There can be achieved maximum control rod reactivities between 0.025 and 0.035 (referred to the totally withdrawn state). (RW) 891 RW/RW 892 MKO [de

  5. Reactor safety-a New Approach

    Machiels, A.J.; Marston, T.U.; Taylor, J.J.

    1993-01-01

    Since 1982, the U.S. utilities have been leading to an industry-wide effort to establish a technical foundation for the design of the next generation of light water reactors (LWRs) in the United States. Since 1985, the utility initiative has been effected through a major technical program managed by the Electric Power Research Institute (EPRI): the Advanced Light Water Reactor (ALWR) Program. In addition to the U.S. utility leadership and sponsorship, the ALWR Program has also greatly benefitted from the participation and sponsorship of numerous international utility companies and from the close cooperation with the U.S. Department of Energy (DOE). One of the main goals of the ALWR Program has been to develop a comprehensive set of design requirements for the advanced LWRs. The Utility Requirement Document (URD) defines the technical basis for improved and standardized future LWR designs. The URD covers the entire plant up to the grid interface. Therefore, it is the basis for an integrated plant design, i.e., nuclear steam supply system and balance of plant. It emphasizes those areas which are most important to the objective of achieving an advanced LWR that is excellent with respect to safety, performance, constructibility, and economics. There are numerous basic design policies underlying the ALWR URD. Of particular interest is the treatment of reactor safety

  6. James Joyce's Ulysses: The Search for Value

    Aouda Aljohani

    2014-01-01

    Full Text Available Two chapters, "Scylla and Charybdis" and "Penelope," in James Joyce's Ulysses are crucial to an understanding of the novel as a whole. "Scylla and Charybdis" stands midway in the novel, the ninth of eighteen chapters, and is designed to serve as a kind of exegesis of the writer's methods and intentions. An analysis of that chapter helps to explain the meaning of the controversial final chapter, "Penelope," and to clarify its thematic and stylistic relation to the text as a whole. Ulysses is the story of a quest, actually of many quests that all coalesce into a single goal: the search for value in a modern world that is somehow diminished and constructed in comparison with the Homeric world where mortals strode the universe in company with gods and goddesses. How, in this dwarfed setting, can men and women redefine heroism in secular humanistic terms relevant to twentieth-century life? Almost by definition a quest narrative culminates in the attainment of the goal or in the potential for its attainment; Joyce's Ulysses affirms this possibility in "Penelope."

  7. In conversation with: Professor Richard James

    John Clarke

    2014-03-01

    Full Text Available In 2011, Richard James wrote in the Foreword to Nelson, Clarke, Kift, and Creagh’s (2012 monograph on Australasian literature on the First Year Experience that:The trend towards universal participation will usher in dramatic changes in the character of the first year in higher education. … (p. iiiIn an interview at the University of Melbourne, Australia in July 2013 between Richard James and John Clarke, Co-editor of the International Journal of the First Year in Higher Education, these and related issues were explored.  The interview picks up where the Foreword left off:  focussing on universal participation.

  8. Device for removing a spent reactor core instrument tube

    Watanabe, Shigeru; Tsuji, Teruaki.

    1980-01-01

    Purpose: To easily and exactly execute works for removing a used reactor core instrument tube to be mounted in a reactor core from the lattice space of the core or for charging the tube into the lattice of the core. Constitution: When fuel assembly is pulled out of a reactor core and a spent reactor core instrument tube is then bent and removed from the core at periodical inspection time, a lower gripping unit integral with an upper gripping unit and a bending unit is provided at the lower end of a hanging rope of a winch, and lowered to the reactor core. Then, the spent reactor core instrument tube is gripped by the upper and lower gripping units, the bending unit is operated, the spent reactor core instrument tube is bent, and the tube is then pulled upwardly by the winch to remove the tube. (Aizawa, K.)

  9. A Novel Dual-Stage Hydrothermal Flow Reactor

    Hellstern, Henrik Christian; Becker, Jacob; Hald, Peter

    2015-01-01

    The dual-stage reactor is a novel continuous flow reactor with two reactors connected in series. It is designed for hydrothermal flow synthesis of nanocomposites, in which a single particle consists of multiple materials. The secondary material may protect the core nanoparticle from oxidation....... The dual-stage reactor combines the ability to produce advanced materials with an upscaled capacity in excess of 10 g/hour (dry mass). TiO2 was synthesized in the primary reactor and reproduced previous results. The dual-stage capability was succesfully demonstrated with a series of nanocomposites incl. Ti...

  10. James Moores Ball: Ophthalmologist, medical historian, bibliophile.

    Feibel, Robert M

    2016-08-01

    James Moores Ball (1862-1929) was an ophthalmologist in St. Louis, Missouri, who excelled as a medical historian and collector of rare and historic books about the history of anatomy. During his lifetime, he was best known as the author of a comprehensive, authoritative, and popular textbook titled Modern Ophthalmology First published in 1904, there were five further editions. Ball was very interested in the history of anatomy and wrote two books on this subject, the first being a biography of Andreas Vesalius, one of the earliest in English, and the second a history of the resurrection men or grave robbers who sold corpses to professors of anatomy and surgery for teaching purposes. His legacy today is the 470 volumes of his personal library, which are now in the Archives and Rare Books department of the Becker Medical Library of the Washington University School of Medicine. These texts are one of their major collections, concentrating on the history of anatomy, beginning with a first edition of Vesalius's De Humani Corporis Fabrica and holding many important and beautiful landmark volumes of anatomical atlases. © The Author(s) 2016.

  11. James F. T. Bugental (1915-2008).

    Schneider, Kirk J; Greening, Tom

    2009-01-01

    James F. T. Bugental died peacefully at age 92 at his Petaluma, California, home on September 18, 2008. Jim was a leading psychotherapist and a founding father, with Abraham Maslow and others, of humanistic psychology, or the "third force" (in contrast to psychoanalysis and behaviorism). Jim was also the creator, along with Rollo May, of existential-humanistic psychotherapy. Jim was born in Fort Wayne, Indiana, on Christmas Day in 1915. Jim earned his doctorate in 1948 from Ohio State University, where he was influenced by Victor Raimy and George Kelly. After a brief time on the University of California, Los Angeles (UCLA) faculty in psychology, Jim resigned in 1953 to found the first group practice of psychotherapy, Psychological Service Associates, with Alvin Lasko. With Abraham Maslow and others, Jim was a cofounder of the Journal of Humanistic Psychology (JHP) and the Association for Humanistic Psychology in 1961. Jim also wrote many books on the topic of psychotherapy during his lifetime. Jim was a great and bold spirit--his many writings and teachings are cherished today widely, and the field of psychology is much richer for his efforts. 2009 APA, all rights reserved

  12. The James Webb Space Telescope Mission

    Sonneborn, George

    2010-01-01

    The James Webb Space Telescope (JWST) is a large aperture, cryogenic, infrared-optimized space observatory under development by NASA for launch in 2014. The European and Canadian Space Agencies are mission partners. JWST will find and study the first galaxies that formed in the early universe, peer through dusty clouds to see AGN environments and stars forming planetary systems at high spatial resolution. The breakthrough capabilities of JWST will enable new studies of star formation and evolution in the Milky Way, including the Galactic Center, nearby galaxies, and the early universe. JWST's instruments are designed to work primarily in the infrared range of 1 - 28 microns, with some capability in the visible. JWST will have a segmented primary mirror, approximately 6.5 meters in diameter, and will be diffraction-limited at wavelength of 2 microns (0.1 arcsec resolution). The JWST observatory will be placed in a L2 orbit by an Ariane 5 launch vehicle provided by ESA. The observatory is designed for a 5-year prime science mission, with propellant for 10 years of science operations. The instruments will provide broad- and narrow-band imaging, coronography, and multi-object and integral-field spectroscopy (spectral resolution of 100 to 3,000) across the 1 - 28 micron wavelength range. Science and mission operations will be conducted from the Space Telescope Science Institute in Baltimore, Maryland.

  13. A WIMS-NESTLE reactor physics model for an RBMK reactor

    Perry, R.T.; Meriwether, G.H.

    1996-01-01

    This work describes the static neutronic calculations made for a three-dimensional model of an RBMK (Russian) reactor. Future work will involve the use of this neutronic model and a thermal-hydraulic model in coupled calculations. The lattice code, WIMS-D, was used to obtain the cross sections for the static neutronic calculations. The static reactor neutronic calculations were made with NESTLE, a three-dimensional nodal diffusion code. The methods used to establish an RBMK reactor model for use in these codes are discussed, and the cross sections calculated are given

  14. A WIMS-NESTLE reactor physics model for an RBMK reactor

    Perry, R.T.; Meriwether, G.H.

    1996-01-01

    This work describes the static neutronic calculations made for a three-dimensional model of an RBMK (Russian) reactor. Future work will involve the use of this neutronic model and a thermal-hydraulic model in coupled calculations. The lattice code, WIMS-D, was used to obtain the cross sections for the static neutronic calculations. The static reactor neutronic calculations were made with NESTLE, a three-dimensional nodal diffusion code. The methods used to establish an RBMK reactor model for use in these codes are discussed, and the cross sections calculated are given. (author)

  15. The "Very Cool" James Webb Space Telescope!

    Teague, Peter J. B.

    2018-01-01

    For over twenty years, scientists, engineers, technicians, and other personnel have been working on the next generation space telescope. As a partnership between NASA (National Aeronautics and Space Administration), CSA (Canadian Space Agency), and ESA (European Space Angency), the James Webb Space Telescope will complement the previous research performed by the Hubble by utilizing a larger primary mirror, which will also be optimized for infrared wavelengths. This combination will allow JWST to collect data and take images of light having traveled over 13.7 billion light years. This presentation will focus on the mission, as well as the contamination control challenges during the integration and testing in the NASA Goddard Spacecraft Systems Development and Integration Facility (SSDIF), one of the largest cleanrooms in the world. Additional information will be presented regarding space simulation testing down to a cool 20 degrees Kelvin [-424 degrees Fahrenheit] that will occur at Johnson Space Center in Houston, TX, and more testing and integration to happen at Northrop Grumman Corp., in Redondo Beach, CA. Launch of the JWST is currently scheduled for the spring of 2019 at Ariane Spaceport in French Guiana, South America.

  16. Watching Time: James Baldwin and Malcolm X

    Mikko Tuhkanen

    2016-12-01

    Full Text Available Taking its cue from recent scholarly work on the concept of time in African American literature, this essay argues that, while both James Baldwin and Malcolm X refuse gradualism and insist on “the now” as the moment of civil rights’ fulfillment, Baldwin also remains troubled by the narrowness assumed by a life, politics, or ethics limited to the present moment. In his engagement with Malcolm’s life and legacy—most notably in One Day, When I Was Lost, his screen adaptation of Malcolm’s autobiography—he works toward a temporal mode that would be both punctual and expansive. What he proposes as the operative time of chronoethics is an “untimely now”: he seeks to replace Malcolm’s unyielding punctuality with a different nowness, one that rejects both calls for “patience,” endemic to any politics that rests on the Enlightenment notion of “perfectibility,” and the breathless urgency that prevents the subject from seeing anything beyond the oppressive system he wants overthrown. Both thinkers find the promise of such untimeliness in their sojourns beyond the United States.

  17. Designing a mini subcritical nuclear reactor

    Escobedo G, C. R.; Vega C, H. R.; Davila H, V. M.

    2015-10-01

    In this work the design of a mini subcritical nuclear reactor formed by means of light water moderator, uranium as fuel, and isotopic neutron source of 239 PuBe was carried out. The design was done by Monte Carlo methods with the code MCNP5 in which uranium was modeled in an array of concentric holes cylinders of 8.5, 14.5, 20.5, 26.5, 32.5 cm of internal radius and 3 cm of thickness, 36 cm of height. Different models were made from a single fuel cylinder (natural uranium) to five. The neutron source of 239 PuBe was situated in the center of the mini reactor; in each arrangement was used water as moderator. Cross sections libraries Endf/Vi were used and the number of stories was large enough to ensure less uncertainty than 3%. For each case the effective multiplication factor k e -f f , the amplification factor and the power was calculated. Outside the mini reactor the ambient dose equivalent H (10) was calculated for different cases. The value of k eff , the amplification factor and power are directly related to the number of cylinders of uranium as fuel. Although the average energy of the neutrons 239 PuBe is between 4.5 and 5 MeV in the case of the mini reactor for a cylinder, in the neutron spectrum the presence of thermal neutrons does not exist, so that produced fissions are generated with fast neutrons, and in designs of two and three rings the neutron spectra shows the presence of thermal neutrons, however the fissions are being generated with fast neutrons. Finally in the four and five cases the amount of moderator is enough to thermalized the neutrons and thereby produce the fission. The maximum value for k eff was 0.82; this value is very close to the assembly of Universidad Autonoma de Zacatecas generating a k eff of 0.86. According to the safety and radiation protection standards for the design of mini reactor of one, two and three cylinders they comply with the established safety, while designs of four and five cylinders not met. (Author)

  18. A personal computer based console monitor for a TRIGA reactor

    Rieke, Phillip E.; Hood, William E.; Razvi, Junaid

    1990-01-01

    Numerous improvements have been made to the Mark F facility to provide a minimum reactor down time, giving a high reactor availability. A program was undertaken to enhance the monitoring capabilities of the instrumentation and control system on this reactor. To that end, a personal computer based console monitoring system has been developed, installed in the control room and is operational to provide real-time monitoring and display of a variety of reactor operating parameters. This system is based on commercially available hardware and an applications software package developed internally at the GA facility. It has (a) assisted the operator in controlling reactor parameters to maintain the high degree of power stability required during extended runs with thermionic devices in-core, and (b) provided data trending and archiving capabilities on all monitored channels to allow a post-mortem analysis to be performed on any of the monitored parameters

  19. Solar System Observations with the James Webb Space Telescope

    Norwood, James; Hammel, Heidi; Milam, Stefanie; Stansberry, John; Lunine, Jonathan; Chanover, Nancy; Hines, Dean; Sonneborn, George; Tiscareno, Matthew; Brown, Michael; Ferruit, Pierre

    2014-01-01

    The James Webb Space Telescope will enable a wealth of new scientific investigations in the near- and mid-infrared, with sensitivity and spatial/spectral resolution greatly surpassing its predecessors. In this paper, we focus upon Solar System science facilitated by JWST, discussing the most current information available concerning JWST instrument properties and observing techniques relevant to planetary science. We also present numerous example observing scenarios for a wide variety of Solar...

  20. Die Another Day, James Bond's smoking over six decades.

    Wilson, Nick; Tucker, Anne

    2016-09-01

    We aimed to examine smoking-related content in all 24 James Bond movies in the Eon Productions series from 1962 to 2015. There were favourable downward trends for any smoking by James Bond (p=0.015 for trend), and for tobacco-related spy-gadgetry (p=0.009). Around 20% of Bond's 60 sexual partners smoked in each decade, and most recently in 2012. There were regular mentions of smoking risks to health (starting from 1967) and product placement of branded packs was present in two movies. Overall, the persisting smoking content remains problematic from a public health perspective, especially given the popularity of this movie series. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

  1. Core configuration of a gas-cooled reactor as a tritium production device for fusion reactor

    Nakaya, H., E-mail: nakaya@nucl.kyushu-u.ac.jp [Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 8190395 (Japan); Matsuura, H.; Nakao, Y. [Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, 744 Motooka, Fukuoka 8190395 (Japan); Shimakawa, S.; Goto, M.; Nakagawa, S. [Japan Atomic Energy Agency, 4002 Oarai, Ibaraki (Japan); Nishikawa, M. [Malaysia-Japan International Institute of Technology, UTM, Kuala Lumpur 54100 (Malaysia)

    2014-05-01

    The performance of a high-temperature gas-cooled reactor as a tritium production device is examined, assuming the compound LiAlO{sub 2} as the tritium-producing material. A gas turbine high-temperature reactor of 300 MWe nominal capacity (GTHTR300) is assumed as the calculation target, and using the continuous-energy Monte Carlo transport code MVP-BURN, burn-up simulations are carried out. To load sufficient Li into the core, LiAlO{sub 2} is loaded into the removable reflectors that surround the ring-shaped fuel blocks in addition to the burnable poison insertion holes. It is shown that module high-temperature gas-cooled reactors with a total thermal output power of 3 GW can produce almost 8 kg of tritium in a year.

  2. Control rod for a reactor

    Natori, Hisahide.

    1975-01-01

    Object: To change arrangement and density of each layer of neutron absorber in the control rod and to render rotation by each layer possible, whereby the neutron absorber may be rotated to readily flatten power distribution. Structure: Neutron absorbers such as boron and carbide are filled into stainless steel pipes, which are peripherally arranged in a multi-layer fashion. Arrangement and density of the neutron absorber by each layer are changed and rotation by each layer is made possible, whereby surface area of the absorber or the like is changed to flatten power distribution. (Furukawa, Y.)

  3. Safety requirements, facility user needs, and reactor concepts for a new Broad Application Test Reactor

    Ryskamp, J.M.; Liebenthal, J.L.; Denison, A.B.; Fletcher, C.D.

    1992-07-01

    This report describes the EG ampersand G Laboratory Directed Research and Development Program (LDRD) Broad Application Test Reactor (BATR) Project that was conducted in fiscal year 1991. The scope of this project was divided into three phases: a project process definition phase, a requirements development phase, and a preconceptual reactor design and evaluation phase. Multidisciplinary teams of experts conducted each phase. This report presents the need for a new test reactor, the project process definition, a set of current and projected regulatory compliance and safety requirements, a set of facility user needs for a broad range of projected testing missions, and descriptions of reactor concepts capable of meeting these requirements. This information can be applied to strategic planning to provide the Department of Energy with management options

  4. "Attacking the Citadel": James Moncreiff's Proposals to Reform Scottish Education, 1851-69.

    Bain, Wilson H.

    1978-01-01

    A review of the parliamentary actions of Lord Advocate James Moncreiff to create a fully national Scottish educational system against the opposition by church groups reluctant to lose control over parish schools and schoolmasters. (SJL)

  5. Sir James Paget: Paget's disease of the nipple, Paget's disease of bone.

    Ellis, Harold

    2013-04-01

    Sir James Paget was one of the 'great' Victorians. Eminent as a surgeon, pathologist and teacher, his nobility of character and application to his work made him a leader in his profession in that age of great men.

  6. The wounded male persona and the mysterious feminine in the poetry of James Wright: a study in the transformation of the self.

    Graves, M; Schermer, V L

    1998-12-01

    James Wright's work is multilayered. Taken as a whole, which Annie Wright's beautiful compilation, Above the River, allows one to do, Wright's poems (as well as his masterful "prose poems") have a pattern akin to a mythic cycle. "Mythemes" (Lévi-Strauss, 1979) recur as dialectic opposites from one poem to another, whether the abandoned male and mysterious woman, humankind and nature, blindness and seeing, secrets and revelation. Suggestive and symbolic forms such as birds, horses, earth, sky, the destitute, rivers, and adolescence weave themselves throughout in inner and outer "landscapes" of images and experiential moments. There is a frequent shift of "gestalts" between the inner world and external reality. Such a "blooming, buzzing confusion" of internal and external referents might appear to be psychotic and imply a loss of "reality testing." Chassaguet-Smirgel (1988), citing Oscar Wilde's The Picture of Dorian Gray as an example, contended that the artist narrowly averts psychosis by transforming it into a work of art. Surrealists, for whom the psychoanalyst Jacques Lacan was an important figure (cf. Sarup, 1992, pp. 17-27), elevated psychosis to the status of art, and Wright has been considered to be a surrealistic poet, although he himself denied such an affiliation. Hall (Wright, 1990, Introduction, pp. xxiii-xxxvii) suggests that Wright, in addition to an extensive history of alcoholism, from which he seemed to recover towards the end of his life, suffered from a major mental illness, which included episodes of severe depression, hospitalizations, and at least one suicide attempt. The severity of the asceticism and the extreme damage to the self in some Wright's work suggests their roots in early traumatic experiences. (A terribly damaged yet heroic personage, whose disfigurement perhaps symbolizes the poet's trauma, is "Hook" [ATR, pp. 315-316], about a man who gives his last few cents to the poet with a hook replacing his amputated hand.) Not enough is

  7. Thermodynamic analysis of a supercritical water reactor

    Edwards, M.

    2007-01-01

    A thermodynamic model has been developed for a hypothetical design of a Supercritical Water Reactor, with emphasis on Canadian design criteria. The model solves for cycle efficiency, mass flows and physical conditions throughout the plant based on input parameters of operating pressures and efficiencies of components. The model includes eight feedwater heaters, three feedwater pumps, a deaerator, a condenser, the core, three turbines and two reheaters. To perform the calculations, Microsoft Excel was used in conjunction with FLUIDCAL-IAPWS95 and VBA code. The calculations show that a thermal efficiency of 47.5% can be achieved with a core outlet temperature of 625 o C. (author)

  8. Hybrid simulation of reactor kinetics in CANDU reactors using a modal approach

    Monaghan, B.M.; McDonnell, F.N.; Hinds, H.W.T.; m.

    1980-01-01

    A hybrid computer model for simulating the behaviour of large CANDU (Canada Deuterium Uranium) reactor cores is presented. The main dynamic variables are expressed in terms of weighted sums of a base set of spatial natural-mode functions with time-varying co-efficients. This technique, known as the modal or synthesis approach, permits good three-dimensional representation of reactor dynamics and is well suited to hybrid simulation. The hybrid model provides improved man-machine interaction and real-time capability. The model was used in two applications. The first studies the transient that follows a loss of primary coolant and reactor shutdown; the second is a simulation of the dynamics of xenon, a fission product which has a high absorption cross-section for neutrons and thus has an important effect on reactor behaviour. Comparison of the results of the hybrid computer simulation with those of an all-digital one is good, within 1% to 2%

  9. Petroleum possibilities of the James Bay Lowland area: Drilling in the James Bay Lowland

    Martison, N W

    1954-12-31

    Interest in the possible occurrence of petroleum and natural gas in the James Bay lowland arises from the presence there of Palaeozoic sedimentary formations resembling those in south-western Ontario. The first part of this report reviews earlier geologic surveys conducted in the lowland and reports results of field work and drill core studies 1946-51. It describes the area`s topography, climate, stratigraphy and palaeontology (Ordovician to Lower Cretaceous, plus Pleistocene and recent glacial deposits), structural geology, and evidence of petroleum. Lists of fossils and correlations are included. The appendices include a list of fossil locations and drill logs. The second part details the drilling programs carried out in the lowland by the Ontario Dept. of Mines, including detailed logs, as well as drilling carried out by some other organisations.

  10. La racionalidad imperialista en la monumental obra de James Mill

    Homero Cuevas

    2011-06-01

    Full Text Available Este ensayo, parte de un trabajo más extenso sobre la dominación internacional en la economía mundial, revisa los procesos más relevantes para el análisis teórico tomando como referencia La historia de la India británica de James Mill, obra que es un hito en este campo y es la base de todas las teorías posteriores

  11. How power is generated in a nuclear reactor

    Swaminathan, V.

    1978-01-01

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

  12. James Madison University Survey of Faculty Activities.

    James Madison Univ., Harrisonburg, VA.

    The activities of the faculty at James Madison University during the fall term of the academic year 1978-79 are described. Full-time instructional faculty, part-time faculty involved in resident instruction, administrators and classified employees who taught at least one course, and graduate teaching assistants were surveyed. Information was…

  13. "Restructuring" Stirs Outcry at James Madison.

    Magner, Denise K.

    1995-01-01

    An administration plan to discontinue the physics major at James Madison University (Virginia) has raised concerns about the president's leadership and management style, and the role of faculty in institutional decision making. Faculty were notified of the plan only after student leaders were told. (MSE)

  14. James Madison and the Constitutional Convention.

    Scanlon, Thomas M.

    1987-01-01

    Part 1 of this three-part article traces James Madison's life and focuses primarily on those events that prepared him for leadership in the U.S. Constitutional Convention of 1787. It describes his early love of learning, education, and public service efforts. Part 2 chronicles Madison's devotion to study and preparation prior to the Constitutional…

  15. James Bernard Russell: Scholar, collaborator, mentor

    At the time of his untimely death in 2009, ARS scientist Dr. James B. Russell had established himself as the premier rumen microbiologist of his generation. Dr. Russell’s many contributions to the field, including much of the early work on the Cornell Net Carbohydrate System model, were the product ...

  16. Reactor antineutrino monitoring with a plastic scintillator array as a new safeguards method

    Oguri, S.; Kuroda, Y.; Kato, Y.; Nakata, R.; Inoue, Y.; Ito, C.; Minowa, M.

    2014-01-01

    We developed a segmented reactor-antineutrino detector made of plastic scintillators for application as a tool in nuclear safeguards inspection and performed mostly unmanned field operations at a commercial power plant reactor. At a position outside the reactor building, we measured the difference in reactor antineutrino flux above the ground when the reactor was active and inactive.

  17. Characteristics of Sediments in the James River Estuary, Virginia, 1968 (NODC Accession 7001081)

    National Oceanic and Atmospheric Administration, Department of Commerce — This report presents data on the physical and chemical characteristics of bottom sediments in the James River estuary, Virgina. The data were generated as part of a...

  18. Data collection and evaluation of continuity detail for John James Audubon Bridge No. 61390613004101.

    2014-10-01

    This report summarizes findings from monitoring data that was collected over a two-year period from Bridge No. : 61390613004101 in the John James Audubon Project, which was formerly designated as Bridge #2 prior to : construction completion. The brid...

  19. Paluel: the production of James Bay on the Cliffs of the Pays de Caux

    Fridman, G.

    1983-01-01

    The main characteristics concerning the confinement enclosure, the reactor vessel, the fuel used, the primary pumps, the steam generator and the first 1300 MW turbogenerator are reviewed; some comparisons with the 900 MW reactors are made. The design of the cooling system constitutes one of the original features of the installations. A glimpse of the work site, the largest in the world at the present time, is given. Concurrently, the EDF is preparing the infrastructures for training the operational personnel of the new 1300 MW unit. The Paluel site is one of the first where the procedure called''large site'' has been applied in order to build in good time the equipment making it possible to provide the site workers and their families with living conditions as close as possible to those of the remainder of the population. To conclude the question of the investment is tackled. By the end of 1985, the 5200 MW of Paluel (4 units of 1300 MW) will be generating from 30 to 35 billion kWh, as much as James bay [fr

  20. Collective control of a nuclear reactor

    Rognin, L

    1995-06-01

    Nowadays, mainly related to the increasing complexity of working environments, working activities become more and collective. The present research on the paradoxical nature of working teams, considered from a reliability point of view. This document is composed of four Sections. The first Section introduces the context of the research, its objectives and the underlying assumptions. In the second Section, we describe a working situation, which is the control of a nuclear reactor. Relations between cooperative work and reliability are discussed in the third Section. Finally, in the fourth Section, a synthesis of the research and some perspectives are proposed. (authors). 7 refs.

  1. Collective control of a nuclear reactor

    Rognin, L.

    1995-06-01

    Nowadays, mainly related to the increasing complexity of working environments, working activities become more and collective. The present research on the paradoxical nature of working teams, considered from a reliability point of view. This document is composed of four Sections. The first Section introduces the context of the research, its objectives and the underlying assumptions. In the second Section, we describe a working situation, which is the control of a nuclear reactor. Relations between cooperative work and reliability are discussed in the third Section. Finally, in the fourth Section, a synthesis of the research and some perspectives are proposed. (authors). 7 refs

  2. A numerical technique for reactor subchannel analysis

    Fath, Hassan E.S.

    1983-01-01

    A numerical technique is developed for the solution of the transient boundary layer equations with a moving liquid-vapour interface boundary. The technique uses the finite difference method with the velocity components defined over an Eulerian mesh. A system of interface massless markers is defined where the markers move with the flow field according to a simple kinematic relation between the interface geometry and the fluid velocity. Different applications of nuclear engineering interest are reported with some available results. The present technique is capable of predicting the interface profile near the wall which is important in the reactor subchannel analysis

  3. Alfven wave heating in a tokamak reactor

    Borg, G.G.; Appert, K.; Knight, A.J.; Lister, J.B.; Vaclavik, J.

    1990-01-01

    A number of features of Alfven wave heating make it potentially attractive for use in large tokamak reactors. Among them are the availability and relativity low cost of the power supplies, the potential ability to act selectively on the current profile, and the probable absence of operational limits in size, fields or density. The physics of Alfven wave heating in a large tokamak is assessed. Present theoretical understanding of mode coupling and antenna loading is extrapolated to a large machine. The problem of a recessed antenna is analysed. Calculations of loading and discussion of various heating scenarios for the particular case of NET are also presented. (author). 23 refs, 18 figs, 4 tabs

  4. Fuel element for a nuclear reactor

    Rau, P.

    1981-01-01

    Fuel elements which consist of parallel longitudinal fuel rods of circular crossection, can be provided with spiral distance pieces, by which the fuel rods support one another, if they are collected together by an outer enclosure. According to the invention, the enclosure includes several strips extending over a small fraction of the rod length, which are connected together by a skeleton rod instead of a fuel rod. The strips can be composed of flat parts which are connected together by the skeleton rod acting as a hinge. The invention is particularly suitable for breeder or converter reactors. (orig.) [de

  5. Neutronics and mass transport in a chemical reactor associated with controlled thermonuclear fusion reactor

    Dang, V.D.; Steinberg, M.; Lazareth, O.W.; Powell, J.R.

    1976-05-01

    The formation of ozone from oxygen and the dissociation carbon dioxide to carbon monoxide and oxygen is studied in a gamma-neutron chemical process blanket associated with a controlled thermonuclear reactor. Materials used for reactor tube wall will affect the efficiency of the energy absorption by the reactants and consequently the yield of reaction products. Three kinds of materials, aluminum, stainless steel and fiber (Al 2 O 3 )-aluminium are investigated for the tube wall material in the study

  6. Aerial photographic water color variations from pollution in the James River

    Bressette, W. E.

    1978-01-01

    A photographic flight was made over the James River on May 17, 1977. The data show that, in general, James River water has very high sunlight reflectance. In the Bailey Bay area this reflectance is drastically reduced. Also shown is a technique for normalizing off-axis variations in radiance film exposure from camera falloff and uneven sunlight conditions to the nadir value. After data normalization, a spectral analysis is performed that identifies Bailey Creek water in James River water. The spectral results when compared with laboratory spectrometer data indicate that reflectance from James River water is dominated by suspended matter, while the substance most likely responsible for reduced reflectance in Bailey Creek water is dissolved organic carbon.

  7. Methodology for the integral comparison of nuclear reactors: selecting a reactor for Mexico

    Reyes R, R.; Martin del Campo M, C.

    2006-01-01

    In this work it was built a methodology to compare nuclear reactors of third generation that can be contemplated for future electric planning in Mexico. This methodology understands the selection of the reactors to evaluate eliminating the reactors that still are not sufficiently mature at this time of the study. A general description of each reactor together with their main ones characteristic is made. It was carried out a study for to select the group of parameters that can serve as evaluation indicators, which are the characteristics of the reactors with specific values for each considered technology, and it was elaborated an evaluation matrix indicators including the reactors in the columns and those indicators in the lines. Since that none reactor is the best in all the indicators were necessary to use a methodology for multi criteria taking decisions that we are presented. It was used the 'Fuzzy Logic' technique, the which is based in those denominated diffuse groups and in a system of diffuse inference based on heuristic rules in the way 'If Then consequence> ', where the linguistic values of the condition and of the consequence is defined by diffuse groups, it is as well as the rules always they transform a diffuse group into another. Later on they combine all the diffuse outputs to create a single output and an inverse transformation is made that it transfers the output from the diffuse domain to the real one. They were carried out two studies one with the entirety of the indicators and another in which the indicators were classified in three approaches: the first one refers to indicators related with the planning of the plants inside the context of the general electric sector, the second approach includes indicators related with the characteristics of the fuel and the third it considers indicators related with the acting of the plant in safety and environmental impact. This second study allowed us to know the qualities of each reactor in each one of the

  8. Pressure suppression system for a nuclear reactor

    Jost, N.

    1977-01-01

    The invention pertains to a pressure suppression system for PWR reactors where the parts enclosing the primary coolant are contained in two pressure-tight separate chambers. According to the invention, these chambers are partly filled with water and are connected with each other below the water surface. This way, gases cannot escape from the containment, not even if a valve and a line are damaged at the same time, as the vapours released condensate in the water of at least one of the other chambers. (HP) [de

  9. Reactors

    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.)

  10. Photocatalytic reactors for treating water pollution with solar illumination. I: a simplified analysis for batch reactors

    Sagawe, G.; Bahnemann, D. [Inst. fuer Technische Chemie, Univ. Hannover, Hannover (Germany); Brandi, R.J.; Cassano, A.E. [INTEC (Univ. Nacional del Litoral and CONICET), Santa Fe (Argentina)

    2003-07-01

    Usual applications of photocatalytic reactors for treating wastewater exhibit the difficulty of handling fluids having varying composition and/or concentrations; thus, a detailed kinetic representation may not be possible. When the catalyst activation is obtained employing solar illumination an additional complexity always coexists: solar fluxes are permanently changing with time. For comparing different reacting systems under similar operating conditions and to provide approximate estimations for scaling up purposes, simplified models may be useful. For these approximations the model parameters should be restricted as much as possible to initial physical and boundary conditions such as: initial concentrations (expressed as such or as TOC measurements), flow rate or reactor volume, irradiated reactor area, incident radiation fluxes and a fairly simple experimental observation such as the photonic efficiency. A combination of a new concept: the ''actual observed photonic efficiency'' with ideal reactor models and empirical kinetic rate expressions can be used to provide rather simple working equations that can be efficiently used to describe the performance of practical reactors. In this paper, the method has been developed for the case of a photocatalytic batch reactor (PBR). (orig.)

  11. A generalized perturbation program for CANDU reactor

    Kim, Do Heon; Kim, Jong Kyung [Hanyang University, Seoul (Korea, Republic of); Choi, Hang Bok; Roh, Gyu Hong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Yang, Won Sik [Chosun University, Kwangju (Korea, Republic of)

    1999-12-31

    A generalized perturbation program has been developed for the purpose of estimating zonal power variation of a CANDU reactor upon refueling operation. The forward and adjoint calculation modules of RFSP code were used to construct the generalized perturbation program. The numerical algorithm for the generalized adjoint flux calculation was verified by comparing the zone power estimates upon refueling with those of forward calculation. It was, however, noticed that the truncation error from the iteration process of the generalized adjoint flux is not negligible. 2 refs., 1 figs., 1 tab. (Author)

  12. Physics: A New Reactor Physics Analysis Toolkit

    Rabiti, C.; Wang, Y.; Palmiotti, G.; Hiruta, H.; Cogliati, J.; Alfonsi, A.

    2011-01-01

    In the last year INL has internally pursued the development of a new reactor analysis tool: PHISICS. The software is built in a modular approach to simplify the independent development of modules by different teams and future maintenance. Most of the modules at the time of this summary are still under development (time dependent transport driver, depletion, cross section I/O and interpolation, generalized perturbation theory), while the transport solver INSTANT (Intelligent Nodal and Semi-structured Treatment for Advanced Neutron Transport) has already been widely used1, 2, 3, 4. For this reason we will focus mainly on the presentation of the transport solver INSTANT

  13. Afterheat assessment of a conceptual fusion reactor

    Jayatissa, S.P.; Goddard, A.J.H.

    1987-01-01

    Structural activation and decay heat deposition calculations have been undertaken for the DEMO fusion reactor design. The DEMO design was based on an earlier conceptual design of a blanket sector which could breed tritium and generate electricity. These calculations have taken account of the redistribution of energy by the transport of γ radiation. Calculated heat deposition patterns have been used as data for simplified heat transfer calculations to judge temperature rises in relation to materials limits in a severe accident involving complete coolant flow failure. (author)

  14. A generalized perturbation program for CANDU reactor

    Kim, Do Heon; Kim, Jong Kyung [Hanyang University, Seoul (Korea, Republic of); Choi, Hang Bok; Roh, Gyu Hong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Yang, Won Sik [Chosun University, Kwangju (Korea, Republic of)

    1998-12-31

    A generalized perturbation program has been developed for the purpose of estimating zonal power variation of a CANDU reactor upon refueling operation. The forward and adjoint calculation modules of RFSP code were used to construct the generalized perturbation program. The numerical algorithm for the generalized adjoint flux calculation was verified by comparing the zone power estimates upon refueling with those of forward calculation. It was, however, noticed that the truncation error from the iteration process of the generalized adjoint flux is not negligible. 2 refs., 1 figs., 1 tab. (Author)

  15. Konstruksi Realitas Pengguna Ponsel Cerdas Berdasarkan Pesan Penempatan Merek dalam Film James Bond: Spectre

    Hafiz, M. Faisal

    2016-01-01

    This study entitled "Construction of Reality of Smartphone User Based on Branding Placement Message in James Bond: Spectre Film". The research is going to examine the relations between the process of branding placement of Sony Xperia Z5 to the movie-viewer who use smartphone from a variety of backgrounds. Researcher focus on how smartphone users adapt to their social needs, how subjective meaning of Sony Xperia Z5 upon the branding placement message in James Bond: Spectre, a...

  16. TOF powder diffractometer on a reactor source

    Bleif, H.J.; Wechsler, D.; Mezei, F.

    1999-01-01

    Complete text of publication follows. The performance of time-of-flight (TOF) methods on Long Pulse Spallation Sources can be studied at a reactor source. For this purpose a prototype TOF monochromator instrument will be installed at the KFKI reactor in Budapest. The initial setup will be a powder diffractometer with a resolution of δd/d down to 2 x 10 -3 at a wavelength of 1 A. The instrument uses choppers to produce neutron pulses of down to 10 μs FWHM. The optimal neutron source for a chopper instrument is a Long Pulse Spallation Source, but even on a continuous source simulations have shown that this instrument outperforms a conventional crystal monochromator powder diffractometer at high resolution. The main components of the TOF instrument are one double chopper defining the time resolution and two single choppers to select the wavelength range and to prevent frame overlap. For inelastic experiments a further chopper can be added in front of the sample. The neutron guide has a super-mirror coating and a curvature of 3500m. The total flight path is 20m and there are 24 single detectors in backscattering geometry. (author)

  17. A review of the UKAEA interest in heavy water reactors

    Symes, R.J.

    1983-01-01

    The chapter commences with a brief account of the history of heavy water production and then begins the story of the British use of this moderator in power reactors. This is equated with the introduction and development of the tube reactor as a distinct and important form of reactor construction in contrast with the perhaps better known vessel design that has tended to dominate reactor engineering to date. The account thus includes a succession of reactor designs including the gas and steam cooled heavy water systems in addition to the steam-generating heavy water reactor. The SGHWR was demonstrated by the construction of a substantial prototype, which continues in operation as a flexible and reliable electricity-generating plant. It was also, for a time, identified as the system to be used for Britain's third reactor programme. Today the successful Canadian CANDU power reactors represent the only penetration of heavy water reactor technology into large scale electricity generation. The range of research and experimental reactors using heavy water in their cores is reviewed. (author)

  18. Deposition reactors for solar grade silicon: A comparative thermal analysis of a Siemens reactor and a fluidized bed reactor

    Ramos, A.; Filtvedt, W. O.; Lindholm, D.; Ramachandran, P. A.; Rodríguez, A.; del Cañizo, C.

    2015-12-01

    Polysilicon production costs contribute approximately to 25-33% of the overall cost of the solar panels and a similar fraction of the total energy invested in their fabrication. Understanding the energy losses and the behaviour of process temperature is an essential requirement as one moves forward to design and build large scale polysilicon manufacturing plants. In this paper we present thermal models for two processes for poly production, viz., the Siemens process using trichlorosilane (TCS) as precursor and the fluid bed process using silane (monosilane, MS). We validate the models with some experimental measurements on prototype laboratory reactors relating the temperature profiles to product quality. A model sensitivity analysis is also performed, and the effects of some key parameters such as reactor wall emissivity and gas distributor temperature, on temperature distribution and product quality are examined. The information presented in this paper is useful for further understanding of the strengths and weaknesses of both deposition technologies, and will help in optimal temperature profiling of these systems aiming at lowering production costs without compromising the solar cell quality.

  19. A brief history of design studies on innovative nuclear reactors

    Sekimoto, Hiroshi, E-mail: hsekimot@gmail.com [Emeritus Professor, Tokyo Institute of Technology (Japan)

    2014-09-30

    In a short period after the success of CP1, many types of nuclear reactors were proposed and investigated. However, soon only a small number of reactors were selected for practical use. Around 1970, only LWRs with small number of CANDUs were operated in the western world, and FBRs were under development. It was about the time when Apollo moon landing was accomplished. However, at the same time, the future of human being was widely considered pessimistic and Limits to Growth was published. In the end of 1970’s the TMI accident occurred and many nuclear reactor contracts were cancelled in USA and any more contracts had not been concluded until recent years. From the reflection of this accident, many Inherent Safe Reactors (ISRs) were proposed, though none of them were constructed. A common idea of ISRs is smallness of their size. Tokyo Institute of Technology (TokyoTech) held a symposium on small reactors, SR/TIT, in 1991, where many types of small ISRs were presented. Recently small reactors attract interest again. The most ideas employed in these reactors were the same discussed in SR/TIT. In 1980’s the radioactive wastes from fuel cycle became a severe problem around the world. In TokyoTech, this issue was discussed mainly from the viewpoint of nuclear transmutations. The neutron economy became inevitable for these innovative nuclear reactors especially small long-life reactors and transmutation reactors.

  20. A brief history of design studies on innovative nuclear reactors

    Sekimoto, Hiroshi

    2014-01-01

    In a short period after the success of CP1, many types of nuclear reactors were proposed and investigated. However, soon only a small number of reactors were selected for practical use. Around 1970, only LWRs with small number of CANDUs were operated in the western world, and FBRs were under development. It was about the time when Apollo moon landing was accomplished. However, at the same time, the future of human being was widely considered pessimistic and Limits to Growth was published. In the end of 1970’s the TMI accident occurred and many nuclear reactor contracts were cancelled in USA and any more contracts had not been concluded until recent years. From the reflection of this accident, many Inherent Safe Reactors (ISRs) were proposed, though none of them were constructed. A common idea of ISRs is smallness of their size. Tokyo Institute of Technology (TokyoTech) held a symposium on small reactors, SR/TIT, in 1991, where many types of small ISRs were presented. Recently small reactors attract interest again. The most ideas employed in these reactors were the same discussed in SR/TIT. In 1980’s the radioactive wastes from fuel cycle became a severe problem around the world. In TokyoTech, this issue was discussed mainly from the viewpoint of nuclear transmutations. The neutron economy became inevitable for these innovative nuclear reactors especially small long-life reactors and transmutation reactors

  1. Some local dilution transient in a pressurized water reactor

    Jacobson, S.

    1989-01-01

    Reactivity accidents are important in the safety analysis of a pressurized water reactor. In this anlysis ejected control rod, steam line break, start of in-active loop and boron dilution accidents are usually dealt with. However, in the analysis is not included what reactivity excursions might happen when a zone,depleted of boron passes the reactor core. This thesis investigates during what operation and emergency conditions diluted zones might exist in a pressurized water reactor and what should be the maximum volumes for then. The limiting transport means are also established in terms of reactivty addition, for the depleted zones. In order to describe the complicated mixing process in the reactor vessel during such a transportation, a typical 3-loop reactor vessel has been modulated by means of TRAC-PF1's VESSEL component. Three cases have been analysed. In the first case the reactor is in a cold condition and the ractor coolant has boron concentration of 2000 ppm. To the reactor vessel is injected an clean water colume of 14 m 3 . In the two other cases the reactor is close to hot shutdown and borated to 850 ppm. To the reactor vessel is added 41 and 13 m 3 clean water, respectively. In the thesis is shown what spatial distribution the depleted zone gets when passing through the reactor vessel in the three cases. The boron concentration in the first case did not decrease the values which would bring the reactor to critical condition. For case two was shown by means of TRAC's point kinetics model that the reactor reaches prompt criticality after 16.03 seconds after starting of the reactor coolant pump. Another prompt criticality occured two seconds later. The total energy developed during the two power escalations were about 55 GJ. A comparision with the criteria used to evaluate the ejected control rod reactivity transient showed that none of these criteria were exceeded. (64 figs.)

  2. A five MW nuclear heating reactor

    Zhang Dafang; Don Duo; Su Quingshan

    1997-01-01

    The 5 MW Nuclear Heating Reactor (NHR-5) developed and designed by the Institute of Nuclear Energy and Technology (INET) and has been operated for four winter seasons since 1989. During the time of commissioning and operation a number of experiments including self-stability, self-regulation and simulation of ATWS etc. were carried out. Some operating experiences such as water chemistry, radiation protection, and environmental impacts and so on, were also obtained at the same time. All of these demonstrate that the design of NHR-5 is successful. (author)

  3. Core of a fast neutron nuclear reactor

    Giacometti, Christian; Mougniot, J.-C.; Ravier, Jean.

    1974-01-01

    The fast neutron nuclear reactor described includes an internal area in fissile material completely enclosed in an area of fertile material forming the outside blanket. The internal fissile area is provided with housings exclusively filled with fertile material forming one or more inside blankets. In this core the internal blankets are shaped like rings vertically separating superimposed rings of fissile material. The blanket of material nearest to the periphery is circumscribed externally by a contour having an indented shape on its straight section so as to increase the contact area between this blanket and the external blanket [fr

  4. Tribute to the legend Mr. Veterinary Public Health, Professor James ...

    The author was also destined during his Sabbatical Leave to have an interactive interview session with Prof James Steele after attending the 20th Annual James Steele lecture/ 99th birthday Dinner of Professor James Steele 4th and 6th April 2012 at the Texas School of Public Health, Houston, Texas, USA. The interview ...

  5. Fail-safe reactivity compensation method for a nuclear reactor

    Nygaard, Erik T.; Angelo, Peter L.; Aase, Scott B.

    2018-01-23

    The present invention relates generally to the field of compensation methods for nuclear reactors and, in particular to a method for fail-safe reactivity compensation in solution-type nuclear reactors. In one embodiment, the fail-safe reactivity compensation method of the present invention augments other control methods for a nuclear reactor. In still another embodiment, the fail-safe reactivity compensation method of the present invention permits one to control a nuclear reaction in a nuclear reactor through a method that does not rely on moving components into or out of a reactor core, nor does the method of the present invention rely on the constant repositioning of control rods within a nuclear reactor in order to maintain a critical state.

  6. Some scoping experiments for a space reactor

    Alexander, C.A.; Ogden, J.S.

    1983-01-01

    Some scoping experiments were performed to evaluate fuel performance in a lithium heat pipe reactor operating at a nominal 1500K heat pipe temperature. Fuel-coolant and fuel-coolant-clad relationships showed that once a failed heat pipe occurs temperatures can rise high enough so that large concentrations of uranium can be transported by the vapor phase. Upon condensation this uranium would be capable of penetrating heat pipes adjacent to the failed pipe. The potential for propagation of failure exists with UO 2 and a lithium heat pipe. Changing the composition of the metal of the heat pipe would have only a second order effect on the kinetics of the failure mechanism. Uranium carbide and nitride were considered as potential fuels which are nonreactive in a lithium environment. At high temperatures the nitride would be favored because of its better compatibility with potential cladding materials. Compositions of UN with small additions of YN appear to offer very attractive properties for a compact high temperature high power density reactor

  7. Hydrodynamic impact of reactor components - a review

    Krajcinovic, D.

    1977-01-01

    A variety of components belonging to a nuclear reactor are by virtue of their design exposed to a mass of fluid which is either in motion or can be set into motion under certain conditions. While the reactor is in its operational mode, the excitations of the structure by the fluid are generally of moderate intensities. In the case of a well designed component, these pressure fluctuations should not cause the failure of the structure. Problems of this type, generally known as vibrations of structures immersed into fluid (under either periodic or random excitations) have been studied in the past rather extensively. In an upset or emergency condition, a pressure pulse is usually generated and propagated through the fluid. While this hypothetical event is an occurrence of low probability the associated pressures are, as a rule, of intensities sufficiently large to cause extensive damage or even the failure of the component. This type of transient interaction problem is much less studied and the aim of this review is to offer a brief discussion of some of the more interesting results. (Auth.)

  8. A Numerical Model for Trickle Bed Reactors

    Propp, Richard M.; Colella, Phillip; Crutchfield, William Y.; Day, Marcus S.

    2000-12-01

    Trickle bed reactors are governed by equations of flow in porous media such as Darcy's law and the conservation of mass. Our numerical method for solving these equations is based on a total-velocity splitting, sequential formulation which leads to an implicit pressure equation and a semi-implicit mass conservation equation. We use high-resolution finite-difference methods to discretize these equations. Our solution scheme extends previous work in modeling porous media flows in two ways. First, we incorporate physical effects due to capillary pressure, a nonlinear inlet boundary condition, spatial porosity variations, and inertial effects on phase mobilities. In particular, capillary forces introduce a parabolic component into the recast evolution equation, and the inertial effects give rise to hyperbolic nonconvexity. Second, we introduce a modification of the slope-limiting algorithm to prevent our numerical method from producing spurious shocks. We present a numerical algorithm for accommodating these difficulties, show the algorithm is second-order accurate, and demonstrate its performance on a number of simplified problems relevant to trickle bed reactor modeling.

  9. Methodology for the integral comparison of nuclear reactors: selecting a reactor for Mexico; Metodologia para la comparacion integral de reactores nucleares: seleccion de un reactor para Mexico

    Reyes R, R.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)]. e-mail: ricarera@yahoo.com.mx

    2006-07-01

    In this work it was built a methodology to compare nuclear reactors of third generation that can be contemplated for future electric planning in Mexico. This methodology understands the selection of the reactors to evaluate eliminating the reactors that still are not sufficiently mature at this time of the study. A general description of each reactor together with their main ones characteristic is made. It was carried out a study for to select the group of parameters that can serve as evaluation indicators, which are the characteristics of the reactors with specific values for each considered technology, and it was elaborated an evaluation matrix indicators including the reactors in the columns and those indicators in the lines. Since that none reactor is the best in all the indicators were necessary to use a methodology for multi criteria taking decisions that we are presented. It was used the 'Fuzzy Logic' technique, the which is based in those denominated diffuse groups and in a system of diffuse inference based on heuristic rules in the way 'If Then consequence> ', where the linguistic values of the condition and of the consequence is defined by diffuse groups, it is as well as the rules always they transform a diffuse group into another. Later on they combine all the diffuse outputs to create a single output and an inverse transformation is made that it transfers the output from the diffuse domain to the real one. They were carried out two studies one with the entirety of the indicators and another in which the indicators were classified in three approaches: the first one refers to indicators related with the planning of the plants inside the context of the general electric sector, the second approach includes indicators related with the characteristics of the fuel and the third it considers indicators related with the acting of the plant in safety and environmental impact. This second study allowed us to know the qualities of

  10. Burn up calculations for the Iranian miniature reactor: A reliable and safe research reactor

    Faghihi, F.; Mirvakili, S.M.

    2009-01-01

    Presenting neutronic calculations pertaining to the Iranian miniature research reactor is the main goal of this article. This is a key to maintaining safe and reliable core operation. The following reactor core neutronic parameters were calculated: clean cold core excess reactivity (ρ ex ), control rod and shim worth, shut down margin (SDM), neutron flux distribution of the reactor core components, and reactivity feedback coefficients. Calculations for the fuel burnup and radionuclide inventory of the Iranian miniature neutron source reactor (MNSR), after 13 years of operational time, are carried out. Moreover, the amount of uranium burnup and produced plutonium, the concentrations and activities of the most important fission products, the actinide radionuclides accumulated, and the total radioactivity of the core are estimated. Flux distribution for both water and fuel temperature increases are calculated and changes of the central control rod position are investigated as well. Standard neutronic simulation codes WIMS-D4 and CITATION are employed for these studies. The input model was validated by the experimental data according to the final safety analysis report (FSAR) of the reactor. The total activity of the MNSR core is calculated including all radionuclides at the end of the core life and it is found to be equal to 1.3 x 10 3 Ci. Our investigation shows that the reactor is operating under safe and reliable conditions.

  11. Burn up calculations for the Iranian miniature reactor: A reliable and safe research reactor

    Faghihi, F. [Department of Nuclear Engineering, School of Engineering, Shiraz University, Shiraz 71345 (Iran, Islamic Republic of); Research Center for Radiation Protection, Shiraz University, Shiraz (Iran, Islamic Republic of)], E-mail: faghihif@shirazu.ac.ir; Mirvakili, S.M. [Department of Nuclear Engineering, School of Engineering, Shiraz University, Shiraz 71345 (Iran, Islamic Republic of)

    2009-06-15

    Presenting neutronic calculations pertaining to the Iranian miniature research reactor is the main goal of this article. This is a key to maintaining safe and reliable core operation. The following reactor core neutronic parameters were calculated: clean cold core excess reactivity ({rho}{sub ex}), control rod and shim worth, shut down margin (SDM), neutron flux distribution of the reactor core components, and reactivity feedback coefficients. Calculations for the fuel burnup and radionuclide inventory of the Iranian miniature neutron source reactor (MNSR), after 13 years of operational time, are carried out. Moreover, the amount of uranium burnup and produced plutonium, the concentrations and activities of the most important fission products, the actinide radionuclides accumulated, and the total radioactivity of the core are estimated. Flux distribution for both water and fuel temperature increases are calculated and changes of the central control rod position are investigated as well. Standard neutronic simulation codes WIMS-D4 and CITATION are employed for these studies. The input model was validated by the experimental data according to the final safety analysis report (FSAR) of the reactor. The total activity of the MNSR core is calculated including all radionuclides at the end of the core life and it is found to be equal to 1.3 x 10{sup 3}Ci. Our investigation shows that the reactor is operating under safe and reliable conditions.

  12. On the definition of a DEMO (demonstration) reactor

    Cole, H.C.; Challender, R.S.

    1987-01-01

    The paper is an appendix to a study of the reactor relevance of the NET design concept. The latter study examines whether the technologies and design principles proposed for NET can be directly extrapolated to a demonstration (DEMO) reactor. The authors have suggested a definition of a DEMO, and listed what they considered to be the most important implications of this definition. A table of parameters is included comparing published DEMO's with typical commercial reactor and 'pre-DEMO' studies. (U.K.)

  13. Safety-related parameters for the MAPLE research reactor and a comparison with the IAEA generic 10-MW research reactor

    Carlson, P.A.; Lee, A.G.; Smith, H.J.; Ellis, R.J.

    1989-07-01

    A summary is presented of some of the principle safety-related physics parameters for the MAPLE Research Reactor, and a comparison with the IAEA Generic 10-MW Reactor is given. This provides a means to assess the operating conditions and fuelling requirements for safe operation of the MAPLE Research Reactor under accepted standards

  14. Pyrolysis of Rubber in a Screw Reactor

    Lozhechnik, A. V.; Savchin, V. V.

    2016-11-01

    On the basis of an analysis of thermal methods described in the literature and from the results of experimental investigations of steam conversion, the authors have developed and created a facility for thermal processing of rubber waste. Rubber crumb was used as the raw material; the temperature in the reactor was 500°C; nitrogen, steam, and a mixture of light hydrocarbons (noncondensable part of pyrolysis products) represented the working medium. The pyrolysis yielded 36-38% of a solid fraction, 54-56% of a liquid hydrocarbon fraction, and 6-9% of noncondensable gases. Changes in the composition of the gas mixture have been determined at different stages of processing. Gas chromatography of pyrolysis gases has shown that the basic gases produced by pyrolysis are H2 and hydrocarbons C2H4, C3H6, C3H8, C4H8, C2H6, C3H6O2, and C4H10, and a small amount of H2S, CO, and CO2. Noncondensable gases will be used as a fuel to heat the reactor and to implement the process.

  15. Design of a periodically operated SCR reactor

    Kotter, M.; Lintz, H.G.; Turek, T.

    1993-01-01

    A new NO x abatement process uses the rotating Ljungstroem air heater of the power plant for the selective catalytic reduction (SCR) of nitrogen monoxide with ammonia. For this purpose the air heater elements are covered by a catalytically active layer. The transformation can be carried out by simple replacement of the original air heater elements. Thus nitrogen monoxide control is possible without requiring major modifications of existing power plant equipment. Two oxidic catalysts have been developed to be employed in the different temperature sections of the air heater. The activity of the catalysts has been quantified with the aid of laboratory scale experiments. The results can be described using a simple expression for the rate of the chemical reaction. NO conversion and NH 3 slip to be expected in a catalytically active Ljungstroem heat exchanger are calculated with a reactor model taking into account the gas phase mass transfer resistances. The calculations show that the proposed device can be used if the NO concentration in the flue gas does not exceed 300 ppm. Recently Kraftanlagen AG, Heidelberg, installed a catalyst air heater system at Mandalay Generating Station in Oxnard, California. The comparison of the predicted results with preliminary experimental data proves the validity of the chosen reactor model. Under the given conditions NO conversions of more than 60% can be achieved maintaining the NH 3 slip below the specified value of 10 ppm. (orig.). 19 figs., 35 refs [de

  16. A computer control system for a research reactor

    Crawford, K.C.; Sandquist, G.M.

    1987-01-01

    Most reactor applications until now, have not required computer control of core output. Commercial reactors are generally operated at a constant power output to provide baseline power. However, if commercial reactor cores are to become load following over a wide range, then centralized digital computer control is required to make the entire facility respond as a single unit to continual changes in power demand. Navy and research reactors are much smaller and simpler and are operated at constant power levels as required, without concern for the number of operators required to operate the facility. For navy reactors, centralized digital computer control may provide space savings and reduced personnel requirements. Computer control offers research reactors versatility to efficiently change a system to develop new ideas. The operation of any reactor facility would be enhanced by a controller that does not panic and is continually monitoring all facility parameters. Eventually very sophisticated computer control systems may be developed which will sense operational problems, diagnose the problem, and depending on the severity of the problem, immediately activate safety systems or consult with operators before taking action

  17. The spheromak as a compact fusion reactor

    Hagenson, R.L.; Krakowski, R.A.

    1987-03-01

    After summarizing the economic and utility-based rationale for compact, higher-power-density fusion reactors, the gun-sustained spheromak concept is explored as one of a number of poloidal-field-dominated confinement configurations that might improve the prospects for economically attractive and operationally simplified fusion power plants. Using a comprehensive physics/engineering/costing model for the spheromak, guided by realistic engineering constraints and physics extrapolation, a range of cost-optimized reactor design points is presented, and the sensitivity of cost to key physics, engineering, and operational variables is reported. The results presented herein provide the basis for conceptual engineering designs of key fusion-power-core (FPC) subsystems and more detailed plasma modeling of this promising, high mass-power-density concept, which stresses single-piece FPC maintenance, steady-state current drive through electrostatic magnetic helicity injection, a simplified co-axial electrode-divertor, and efficient resistive-coal equilibrium-field coils. The optimal FPC size and the cost estimates project a system that competes aggressively with the best offered by alternative energy sources while simplifying considerably the complexity that has generally been associated with most approaches to magnetic fusion energy

  18. The spheromak as a compact fusion reactor

    Hagenson, R.L.; Krakowski, R.A.

    1987-03-01

    After summarizing the economic and utility-based rationale for compact, higher-power-density fusion reactors, the gun-sustained spheromak concept is explored as one of a number of poloidal-field-dominated confinement configurations that might improve the prospects for economically attractive and operationally simplified fusion power plants. Using a comprehensive physics/engineering/costing model for the spheromak, guided by realistic engineering constraints and physics extrapolation, a range of cost-optimized reactor design points is presented, and the sensitivity of cost to key physics, engineering, and operational variables is reported. The results presented herein provide the basis for conceptual engineering designs of key fusion-power-core (FPC) subsystems and more detailed plasma modeling of this promising, high mass-power-density concept, which stresses single-piece FPC maintenance, steady-state current drive through electrostatic magnetic helicity injection, a simplified co-axial electrode-divertor, and efficient resistive-coal equilibrium-field coils. The optimal FPC size and the cost estimates project a system that competes aggressively with the best offered by alternative energy sources while simplifying considerably the complexity that has generally been associated with most approaches to magnetic fusion energy.

  19. Cryogenic system design for a compact tokamak reactor

    Slack, D.S.; Kerns, J.A.; Miller, J.R.

    1988-01-01

    The International Tokamak Engineering Reactor (ITER) is a program presently underway to design a next-generation tokamak reactor. The cryogenic system for this reactor must meet unusual and new requirements. Unusually high heat loads (100 kW at 4.5 K) must be handled because neutron shielding has been limited to save space in the reactor core. Also, large variations in the cryogenics loads occur over short periods of time because of the pulsed nature of some of the operating scenarios. This paper describes a workable cryogenic system design for a compact tokamak reactor such as ITER. A design analysis is presented dealing with a system that handles transient loads, coil quenches, reactor cool-down and the effect of variations in helium-supply temperatures on the cryogenic stability of the coils. 5 refs., 4 figs., 1 tab

  20. Spring unit especially intended for a nuclear reactor core

    Brown, S.J.; Gorholt, Wilhelm.

    1977-01-01

    This invention relates to a spring unit or a group of springs bearing up a sprung mass against an unsprung mass. For instance, a gas cooled high temperature nuclear reactor includes a core of relatively complex structure supported inside a casing or vessel forming a shielded cavity enclosing the reactor core. This core can be assembled from a large number of graphite blocks of different sizes and shapes joined together to form a column. The blocks of each column can be fixed together so as to form together a loose side support. Under the effect of thermal expansion and contraction, shrinkage resulting from irradiation, the effects of pressure and the contraction and creep of the reactor vessel, it is not possible to confine all the columns of the reactor core in a cylindrical rigid structure. Further, the working of the nuclear reactor requires that the reactivity monitoring components may be inserted at any time in the reactor core. A standard process consists in mounting this loosely assembled reactor core in a floating manner by keeping it away from the vessel enclosure around it by means of a number of springs fitted between the lateral surfaces of the core unit and the reactor vessel. The core may be considered as a spring supported mass whereas, relatively, the reactor vessel is a mass that is not flexibly supported [fr

  1. Sloshing of coolant in a seismically isolated reactor

    Wu, T.S.; Guildys, J.; Seidensticker, R.W.

    1988-01-01

    During a seismic event, the liquid coolant inside the reactor vessel has sloshing motion which is a low-frequency phenomenon. In a reactor system incorporated with seismic isolation, the isolation frequency usually is also very low. There is concern on the potential amplification of sloshing motion of the liquid coolant. This study investigates the effects of seismic isolation on the sloshing of liquid coolant inside the reactor vessel of a liquid metal cooled reactor. Based on a synthetic ground motion whose response spectra envelop those specified by the NRC Regulator Guide 1.60, it is found that the maximum sloshing wave height increases from 18 in. to almost 30 in. when the system is seismically isolated. Since higher sloshing wave may introduce severe impact forces and thermal shocks to the reactor closure and other components within the reactor vessel, adequate design considerations should be made either to suppress the wave height or to reduce the effects caused by high waves

  2. A small modular fast reactor as starting point for industrial deployment of fast reactors

    Chang, Yoon I.; Lo Pinto, Pierre; Konomura, Mamoru

    2006-01-01

    The current commercial reactors based on light water technology provide 17% of the electricity worldwide owing to their reliability, safety and competitive economics. In the near term, next generation reactors are expected to be evolutionary type, taking benefits of extensive LWR experience feedbacks and further improved economics and safety provisions. For the long term, however, sustainable energy production will be required due to continuous increase of the human activities, environmental concerns such as greenhouse effect and the need of alternatives to fossil fuels as long term energy resources. Therefore, future generation commercial reactors should meet some criteria of sustainability that the current generation cannot fully satisfy. In addition to the current objectives of economics and safety, waste management, resource extension and public acceptance become other major objectives among the sustainability criteria. From this perspective, two questions can be raised: what reactor type can meet the sustainability criteria, and how to proceed to an effective deployment in harmony with the high reliability and availability of the current nuclear reactor fleet. There seems to be an international consensus that the fast spectrum reactor, notably the sodium-cooled system is most promising to meet all of the long term sustainability criteria. As for the latter, we propose a small modular fast reactor project could become a base to prepare the industrial infrastructure. The paper has the following contents: - Introduction; - SMFR project; - Core design; - Supercritical CO 2 Brayton cycle; - Near-term reference plant; - Advanced designs; - Conclusions. To summarize, the sodium-cooled fast reactor is currently recognized as the technology of choice for the long term nuclear energy expansion, but some research and development are required to optimize and validate advanced design solutions. A small modular fast reactor can satisfy some existing near-term market niche

  3. A large economic liquid metal reactor for United States utilities

    Rodwell, E.

    1985-01-01

    The United States has demonstrated its ability to build and operate small and medium sized liquid metal reactors and continues to operate the Experimental Breeder Reactor II and the Fast Flux Test Facility to demonstrate long life fuel designs. Similar-sized liquid metal reactors in Europe have been followed by a step-up to the 1200 MWe capacity of the Superphenix plant. To permit the United States to make a similar step-up in capacity, a 1320 MWe liquid metal reactor plant has been designed with the main emphasis on minimizing the specific capital cost in order to be competitive with light water reactor plant and fossil plant alternatives. The design is based on a four parallel heat transport loops arrangement and complies with current regulatory requirements. The primary heat transport loops are now being integrated into the reactor vessel to achieve further reduction in the capital cost

  4. Hybrid biogas upgrading in a two-stage thermophilic reactor

    Corbellini, Viola; Kougias, Panagiotis; Treu, Laura

    2018-01-01

    The aim of this study is to propose a hybrid biogas upgrading configuration composed of two-stage thermophilic reactors. Hydrogen is directly injected in the first stage reactor. The output gas from the first reactor (in-situ biogas upgrade) is subsequently transferred to a second upflow reactor...... (ex-situ upgrade), in which enriched hydrogenotrophic culture is responsible for the hydrogenation of carbon dioxide to methane. The overall objective of the work was to perform an initial methane enrichment in the in-situ reactor, avoiding deterioration of the process due to elevated pH levels......, and subsequently, to complete the biogas upgrading process in the ex-situ chamber. The methane content in the first stage reactor reached on average 87% and the corresponding value in the second stage was 91%, with a maximum of 95%. A remarkable accumulation of volatile fatty acids was observed in the first...

  5. RHTF 2, a 1200 MWe high temperature reactor

    Brisbois, Jacques

    1978-01-01

    After having adapted to French conditions the 1160 MWe G.A.C. reactor, Commissariat a l'Energie Atomique and French Industry have decided to design an High Temperature Reactor 1200 MWe based on the G.A.C. technology and taking into account the point of view of Electricite de France and the experience of C.E.A. and industry on the gas cooled reactor technology. The main objective of this work is to produce a reactor design having a low technical risk, good operability, with an emphasis on the safety aspects easing the licensing problems

  6. A critical review of homogenization techniques in reactor lattices

    Benoist, P.

    1983-01-01

    The determination of the shape of the neutron flux in a whole reactor is, at the time being, a much too complex problem to be treated by transport theory. Since the earlier times of reactor theory, the necessity appeared to solve the problem in two steps. First the reactor is divided into zones, each of them forming a regular lattice. In each of these zones, homogenized parameters are determined by transport theory, in order to define an equivalent smeared medium. In a second step, these parameters are introduced in a diffusion theory scheme in order to treat the reactor as a whole. This is the homogenization procedure. 14 refs

  7. A critical review of homogenization techniques in reactor lattices

    Benoist, P.

    1983-01-01

    The determination of the shape of the neutron flux in a whole reactor is, at the time being, a much too complex problem to be treated by transport theory. Since the earlier times of reactor theory, the necessity appeared to solve the problem in two steps. First the reactor is divided into zones, each of them forming a regular lattice. In each of these zones, homogenized parameters are determined by transport theory, in order to define an equivalent smeared medium. In a second step, these parameters are introduced in a diffusion theory scheme in order to treat the reactor as a whole. This is the homogenization procedure

  8. 75 FR 44720 - Safety Zone; Live-Fire Gun Exercise, M/V Del Monte, James River, VA

    2010-07-29

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard 33 CFR Part 165 [Docket No. USCG-2010-0585] RIN 1625-AA00 Safety Zone; Live-Fire Gun Exercise, M/V Del Monte, James River, VA AGENCY: Coast Guard, DHS... follows: Sec. 165.T05-0585 Safety Zone; Live-Fire Gun Exercise, M/V Del Monte, James River, VA (a...

  9. Investigation of flow stabilization in a compact reactor vessel of a FBR. Flow visualization in a reactor vessel

    Sato, Hiroyuki; Igarashi, Minoru; Kimura, Nobuyuki; Kamide, Hideki

    2002-01-01

    In the feasibility studies of Commercialized Fast Breeder Reactor Cycle System, a compact reactor vessel is considered from economical improvement point of a sodium cooled loop type fast reactor. The flow field was visualized by water experiment for a reactor vessel with 'a column type UIS (Upper Internal Structure)', which has a slit for fuel handling mechanism and is useful for a compact fast reactor. In this research, the 1/20 scale test equipment using water was made to understand coolant flow through a slit of a column type UIS' and fundamental behavior of reactor upper plenum flow. In the flow visualization tests, tracer particles were added in the water, and illuminated by the slit-shaped pulse laser. The flow visualization image was taken with a CCD camera. We obtained fluid velocity vectors from the visualization image using the Particle Imaging Velocimetry (PIV). The results are as follows. 1. Most of coolant flow through a slit of 'column type UIS' arrived the dip plate directly. In the opposite side of a slit, most of coolant flowed toward reactor vessel wall before it arrived the dip plate. 2. The PIV was useful to measure the flow field in the reactor vessel. The obtained velocity field was consistent with the flow visualization result. 3. The jet through the UIS slit was dependent on the UIS geometry. There is a possibility to control the jet by the UIS geometry. (author)

  10. Production of energy in a high temperature reactor

    Anon.

    1979-01-01

    The cooling gas having left the reactor core is fed to a generator for direct production of current from the kinetic energy. Afterwards the gas is fed to a heat exchanger for cooling, then compressed and refed to the reactor core. The method further comprises that one part of the energy of the fission material is directly converted to electric energy in the reactor core, whereas the other part of the energy of the fission material is impressed upon the cooling gas. According to the invention the cooling gas when entering the reactor is first fed to that part of the reactor core which serves as a thermoionic or thermoelectric transducer. Afterwards the cooling gas is fed to the remaining part of the reactor gas. (P.K.)

  11. Risk management activities at the DOE Class A reactor facilities

    Sharp, D.A.; Hill, D.J.; Linn, M.A.; Atkinson, S.A.; Hu, J.P.

    1993-01-01

    The probabilistic risk assessment (PRA) and risk management group of the Association for Excellence in Reactor Operation (AERO) develops risk management initiatives and standards to improve operation and increase safety of the DOE Class A reactor facilities. Principal risk management applications that have been implemented at each facility are reviewed. The status of a program to develop guidelines for risk management programs at reactor facilities is presented

  12. A university contribution to reactor safety

    Hall, W.B.

    1980-01-01

    The total UK university effort available for research specifically directed towards reactor safety is certainly small in comparison with that in industry. To be worth while, the work should complement that in the industry, and ways in which this can, and in some cases does, happen, will be discussed. There is, however, another reason for university involvement: the need for an informed body of opinion on matters of reactor safety outside the industry. Without this it is difficult for the public and its representatives to assure themselves that the depth and scope of safety analysis is commensurate with the seriousness of the problem, and that the best available data and techniques are being used. An independent inspectorate is an essential element in this philosophy, but in addition there is much to be said for exposing the arguments to scrutiny by the widest possible range of informed critics. Such people will be much more effective if they are themselves involved in real problems in the field. In a university, this involvement is probably best achieved through research; as mentioned above, the type of research should preferably complement that being carried out in the industry. The current situation, and the future, are discussed. (author)

  13. Method of cooling a pressure tube type reactor

    Kanazawa, Nobuhiro.

    1983-01-01

    Purpose: To improve the operation efficiency of a nuclear reactor by carrying out cooling depending on the power distribution in the reactor core. Constitution: Reactor core channels are divided into a plurality of channel groups depending on the reactor power, and a water drum and a pump are disposed to each of the channel groups so as to increase the amount of coolants in response to the magnitude of the power from each of the channel groups. In this way, the minimum limiting power ratio can be increased. (Seki, T.)

  14. A computer code for Tokamak reactor concepts evaluation

    Rosatelli, F.; Raia, G.

    1985-01-01

    A computer package has been developed which could preliminarily investigate the engineering configuration of a tokamak reactor concept. The code is essentially intended to synthesize, starting from a set of geometrical and plasma physics parameters and the required performances and objectives, three fundamental components of a tokamak reactor core: blanket+shield, TF magnet, PF magnet. An iterative evaluation of the size, power supply and cooling system requirements of these components allows the judgment and the preliminary design optimization on the considered reactor concept. The versatility of the code allows its application both to next generation tokamak devices and power reactor concepts

  15. Preliminary Design Concept for a Reactor-internal CRDM

    Lee, Jae Seon; Kim, Jong Wook; Kim, Tae Wan; Choi, Suhn; Kim, Keung Koo

    2013-01-01

    A rod ejection accident may cause severer result in SMRs because SMRs have relatively high control rod reactivity worth compared with commercial nuclear reactors. Because this accident would be perfectly excluded by adopting a reactor-internal CRDM (Control Rod Drive Mechanism), many SMRs accept this concept. The first concept was provided by JAERI with the MRX reactor which uses an electric motor with a ball screw driveline. Babcock and Wilcox introduced the concept in an mPower reactor that adopts an electric motor with a roller screw driveline and hydraulic system, and Westinghouse Electric Co. proposes an internal Control Rod Drive in its SMR with an electric motor with a latch mechanism. In addition, several other applications have been reported thus far. The reactor-internal CRDM concept is now widely adopted in many SMR designs, and this concept may also be applied in an evolutionary reactor development. So the preliminary study is conducted based on the SMART CRDM design. A preliminary design concept for a reactor-internal CRDM was proposed and evaluated through an electromagnetic analysis. It was found that there is an optimum design for the motor housing, and the results may contribute to the realization a reactor-internal CRDM for an evolutionary reactor development. More detailed analysis results will be reported later

  16. Construction of a graphic interface for a nuclear reactor modelling and simulation

    Cadrdenas C, Carlos Roberto; Riquelme R, Raul Antonio.

    1995-01-01

    A graphic interface is presented for real time transient analysis under reactivity insertion, reactor operators training, and the RECH-1 reactor licensing, using the Paret (Program for Analysis of Reactor Transients) computer code. 17 refs., 29 figs

  17. Integral Fast Reactor: A future source of nuclear energy

    Southon, R.

    1993-01-01

    Argonne National Laboratory is developing a reactor concept that would be an important part of the worlds energy future. This report discusses the Integral Fast Reactor (IFR) concept which provides significant improvements over current generation reactors in reactor safety, plant complexity, nuclear proliferation, and waste generation. Two major facilities, a reactor and a fuel cycle facility, make up the IFR concept. The reactor uses fast neutrons and metal fuel in a sodium coolant at atmospheric pressure that relies on laws of physics to keep it safe. The fuel cycle facility is a hot cell using remote handling techniques for fabricating reactor fuel. The fuel feed stock includes spent fuel from the reactor, and potentially, spent light water reactor fuel and plutonium from weapons. This paper discusses the unique features of the IFR concept and the differences the quality assurance program has from current commercial practices. The IFR concept provides an opportunity to design a quality assurance program that makes use of the best contemporary ideas on management and quality

  18. A nuclear reactor with buffered control rods

    Bevilacqua, F.

    1974-01-01

    The control rods for, e.g., water-cooled reactors are fastened as units on common crossbars in vertical downward direction. The fastening on the crossbar is achieved by means of cross-shaped parts, e.g., in the shape of a double 'H'. A cylinder connected with a drive rod in normal operation is joined to each of the crossbars. In an emergency shut-down, this connection is interrupted and the control rod unit drops into the core through the action of gravity. Its fall is slowed down by a cushion or shock absorbing unit. For this purpose a piston is provided mounted on the supporting plate below the cylinder and guided within it. In the cylinder, the coolant is contained as damping medium. An upper opening in the cylinder serves as a ventilation hole. The movement of the piston is limited by a stopping part within the cylinder and slowed down by a spiral spring. (DG) [de

  19. A new safety approach in the design of fast reactors

    Neuhold, R.J.; Marchaterre, J.F.; Waltar, A.E.

    1987-01-01

    A new approach to achieving fast reactor safety goals is becoming really apparent in the US Fast Reactor Program. Whereas the ''defense is best'' philosophy still prevails, there has been a tangible shift toward emphasizing passive mechanisms to protect the reactor and provide public safety---rather than relying on add-on active, engineered safety systems. This paper reviews the technical basis for this new safety approach and provides discussion on its implementation in current US liquid metal-cooled reactor designs. 4 refs., 4 figs

  20. Mo-99 production on a LEU solution reactor

    Brown, R.W.; Thome, L.A.; Khvostionov, V.Y.

    2005-01-01

    A pilot homogenous reactor utilizing LEU has been developed by the Kurchatov Institute in Moscow along with their commercial partner TCI Medical. This solution reactor operates at levels up to 50 kilowatts and has successfully produced high quality Mo-99 and Sr-89. Radiochemical extraction of medical radionuclides from the reactor solution is performed by passing the solution across a series of inorganic sorbents. This reactor has commercial potential for medical radionuclide production using LEU UO 2 SO 4 fuel. Additional development work is needed to optimize multiple 50 kilowatt cores while at the same time, optimizing production efficiency and capital expenditure. (author)

  1. CANDU - a versatile reactor for plutonium disposition or actinide burning

    Chan, P.S.W.; Gagnon, M.J.N.; Boczar, P.G.; Ellis, R.J.; Verrall, R.A.

    1997-10-01

    High neutron economy, on-line refuelling, and a simple fuel-bundle design result in a high degree of versatility in the use of the CANDU reactor for the disposition of weapons-derived plutonium and for the annihilation of long-lived radioactive actinides, such as plutonium, neptunium, and americium isotopes, created in civilian nuclear power reactors. Inherent safety features are incorporated into the design of the bundles carrying the plutonium and actinide fuels. This approach enables existing CANDU reactors to operate with various plutonium-based fuel cycles without requiring major changes to the current reactor design. (author)

  2. Functional systems of a pressurized water reactor

    Heinzel, V.

    1982-01-01

    The main topics, discussed in the present paper, are: - Principle design of the reactor coolant system - reactor pressure vessel with internals - containment design - residual heat removal and emergency cooling systems - nuclear component cooling systems - emergency feed water systems - plant electric power supply system. (orig./RW)

  3. A water inner circulation device for a reactor vessel

    Eriksson, O.

    1976-01-01

    A water inner circulation device for a reactor vessel comprising a pump mounted in the reactor vessel and driven by a water-cooled electric motor mounted in a housing outside the reactor vessel, the shaft of the pump passing through the reactor-vessel bottom and being coupled to the motor shaft in a member mechanically connected to the bottom of the reactor vessel in the vicinity of the motor housing, the pump shaft being surrounded by a resilient sealing ring, the reactor vessel communicating with the cooling channels of the pump, when the latter is operating, via a slot surrounding the pump hollow cylindrical shaft, characterized in that the slot inner end is used for/forming a circular space surrounding the pump shaft and surrounded by the motorhousing, in which is coaxially mounted a separating cylindral wall, the upper edge of which is tightly applied against the inner wall of the motor-housing to which it is fastened vertically, the inner surface of said wall being turned towards the outer surface of a circular packing-box, the outer surface of said separating wall constituting a separating radical inner surface for a circular chamber through which flow the motor cooling water. (author)

  4. Photocatalytic reactors for treating water pollution with solar illumination. II: a simplified analysis for flow reactors

    Sagawe, G.; Bahnemann, D. [Inst. fuer Technische Chemie, Univ. Hannover, Hannover (Germany); Brandi, R.J.; Cassano, A.E. [INTEC (Univ. Nacional del Litoral and CONICET), Santa Fe (Argentina)

    2003-07-01

    Very frequently outgoing streams of real wastewaters do not have a definite and constant composition. Additionally, when the degradation process makes use of solar irradiation, the photon flux is hardly constant. These two factors strongly militate against the use of very elaborate, exact models for analyzing the performance of the employed reactors. In these cases, approximate methods may be the most practical approach. One possible way is presented in this paper. The observed photonic efficiency concept developed in a previous contribution (sagawe et al., 2002a) is applied to continuous reactors for both steady state and transient operations of photocatalytic reactions applied to wastewaters decontamination processes. For this reactor the local observed photonic efficiency, defined at each reactor longitudinal position, is the convenient property to express the concentration spatial evolution. It is also shown that the description of the reactor performance employing a mass balance can be done in a rather simple way introducing a mass-moving coordinate transformation that remodel the mass inventory and permits working with simpler ordinary differential equations. (orig.)

  5. Reactor decommissioning in a deregulated market

    Beverridge, George; Cooper, T.

    2002-01-01

    Full text: Deregulation of the electricity markets in North America and Western Europe has had many profound effects on the electric utilities and the nuclear industry. Deregulation has led to cost transparency, increased competition, and a drive by the utilities to reduce costs in order to maintain market share and margins. In the context of this more competitive and dynamic market having a clear picture of decommissioning liabilities and their successful discharge has a material impact on the financial performance of a utility. This paper will summarise BNFL Environmental Services' experience with regard to its experience in both the planning and implementation phases of a reactor decommissioning project. In particular it will demonstrate how commercial projects in crucial areas of strategy development, project implementation and site restoration, can be combined with an approach that is both commercial and innovative to reduce the risks to a utility. This paper sets out to demonstrate this viewpoint. (author)

  6. Research and development of a super fast reactor (12). Considerations for the reactor characteristics

    Goto, Shoji; Ishiwatari, Yuki; Oka, Yoshiaki

    2008-01-01

    A research program aimed at developing the Super Fast Reactor (Super FR) has been entrusted by the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan since December 2005. It includes the following three projects. (A) Development of the Super Fast Reactor concept. (B)Thermal-hydraulic experiments. (C) Materials development. Tokyo Electric Power Company (TEPCO) has joined this program and works on part (A) together with the University of Tokyo. From the utility's viewpoint, it is important to consider the most desirable characteristics for Super FR to have. Four issues were identified in project (A), (1) Fuel design, (2) Reactor core design, (3) Safety, and (4) Plant characteristics of Super FR. This report describes the desired characteristics of Super FR with respect to item (1) fuel design and item (2) Reactor core design, as compared with a boiling water reactor (BWR) plant. The other two issues will be discussed in this project, and will also be considered in the design process of Super FR. (author)

  7. Control rod for a nuclear reactor

    Roman, W.G.; Sutton, H.G. Jr.

    1976-01-01

    A control rod assembly for a nuclear reactor is disclosed having a remotely disengageable coupling between the control rod and the control rod drive shaft. The coupling is actuated by first lowering then raising the drive shaft. The described motion causes axial repositioning of a pin in a grooved rotatable cylinder, each being attached to different parts of the drive shaft which are axially movable relative to each other. In one embodiment, the relative axial motion of the parts of the drive shaft is used either to couple or to uncouple the connection by forcing resilent members attached to the drive shaft into or out of shouldered engagement, respectively, with an indentation formed in the control rod

  8. Control rod for a nuclear reactor

    Roman, Walter G.; Sutton, Jr., Harry G.

    1979-01-01

    A control rod assembly for a nuclear reactor is disclosed having a remotely disengageable coupling between the control rod and the control rod drive shaft. The coupling is actuated by first lowering then raising the drive shaft. The described motion causes axial repositioning of a pin in a grooved rotatable cylinder, each being attached to different parts of the drive shaft which are axially movable relative to each other. In one embodiment, the relative axial motion of the parts of the drive shaft is used either to couple or to uncouple the connection by forcing resilient members attached to the drive shaft into or out of shouldered engagement, respectively, with an indentation formed in the control rod.

  9. Control rod for a nuclear reactor

    Roman, W.G.; Sutton, H.G. Jr.

    1979-01-01

    A control rod assembly for a nuclear reactor is disclosed having a remotely disengageable coupling between the control rod and the control rod drive shaft. The coupling is actuated by first lowering then raising the drive shaft. The described motion causes axial repositioning of a pin in a grooved rotatable cylinder, each being attached to different parts of the drive shaft which are axially movable relative to each other. In one embodiment, the relative axial motion of the parts of the drive shaft is used either to couple or to uncouple the connection by forcing resilient members attached to the drive shaft into or out of shouldered engagement, respectively, with an indentation formed in the control rod

  10. A review of fast reactor progress in Japan

    Tomabechi, K [Power Reactor and Nuclear Fuel Development Corporation, Tokyo (Japan)

    1978-07-01

    The fast reactor development project in Japan is continuing at a slightly increased scale of effort in budget. The total budget for LMFBR development for fiscal year 1978 was 24 billion yen. In August 1977 major industries engaged in LMFBR have set up an office where design work can be jointly conducted. Highlights and topics of the fast reactor development activities cover description of JOYO reactor, its first criticality experiment, and the prototype fast breeder MONJU. Research and development programmes dealt with fission products release and its possible interaction with the soodium coolant, inspection of reactor components, experiments simulating sodium leakage, development of steam generator.

  11. Cascade: a high-efficiency ICF power reactor

    Pitts, J.H.

    1985-01-01

    Cascade attains a net power-plant efficiency of 49% and its cost is competitive with high-temperature gas-cooled reactor, pressurized-water reactor, and coal-fired power plants. The Cascade reactor and blanket are made of ceramic materials and activation is 6 times less than that of the MARS Tandem Mirror Reactor operating at comparable power. Hands-on maintenance of the heat exchangers is possible one day after shutdown. Essentially all tritium is recovered in the vacuum system, with the remainder recovered from the helium power conversion loop. Tritium leakage external to the vacuum system and power conversion loop is only 0.03 Ci/d

  12. Neutron dosimetry. Environmental monitoring in a BWR type reactor

    Tavera D, L.; Camacho L, M.E.

    1991-01-01

    The measurements carried out on reactor dosimetry are applied mainly to the study on the effects of the radiation in 108 materials of the reactor; little is on the environmental dosimetry outside of the primary container of BWR reactors. In this work the application of a neutron spectrometer formed by plastic detectors of nuclear traces manufactured in the ININ, for the environmental monitoring in penetrations around the primary container of the unit I of the Laguna Verde central is presented. The neutron monitoring carries out with purposes of radiological protection, during the operational tests of the reactor. (Author)

  13. A model to describe the performance of the UASB reactor.

    Rodríguez-Gómez, Raúl; Renman, Gunno; Moreno, Luis; Liu, Longcheng

    2014-04-01

    A dynamic model to describe the performance of the Upflow Anaerobic Sludge Blanket (UASB) reactor was developed. It includes dispersion, advection, and reaction terms, as well as the resistances through which the substrate passes before its biotransformation. The UASB reactor is viewed as several continuous stirred tank reactors connected in series. The good agreement between experimental and simulated results shows that the model is able to predict the performance of the UASB reactor (i.e. substrate concentration, biomass concentration, granule size, and height of the sludge bed).

  14. Fixed-bed Reactor Dynamics and Control - A Review

    Jørgensen, S. B.

    1986-01-01

    The industrial diversity of fixed bed reactors offers a challenging and relevant set of control problems. These intricate problems arise due to the rather complex dynamics of fixed bed reactors and to the complexity of actual reactor configurations. Many of these control problems are nonlinear...... and multi-variable. During the last decade fixed bed reactor control strategies have been proposed and investigated experimentally. This paper reviews research on these complex control problems with an emphasis upon solutions which have been demon-strated to work in the laboratory and hold promise...

  15. Passive cooling of a fixed bed nuclear reactor

    Petry, V.J.; Bortoli, A.L. de; Sefidwash, F.

    2005-01-01

    Small nuclear reactors without the need for on-site refuelling have greater simplicity, better compliance with passive safety systems, and are more adequate for countries with small electric grids and limited investment capabilities. Here the passive cooling characteristic of the fixed bed nuclear reactor (FBNR), that is being developed under the International Atomic Energy Agency (IAEA) Coordinated Research Project, is studied. A mathematical model is developed to calculate the temperature distribution in the fuel chamber of the reactor. The results demonstrate the passive cooling of this nuclear reactor concept. (authors)

  16. Challenges in licensing a sodium-cooled advanced recycling reactor

    Levin, Alan E.

    2008-01-01

    As part of the Global Nuclear Energy Partnership (GNEP), the U.S. Department of Energy (DOE) has focused on the use of sodium-cooled fast reactors (SFRs) for the destruction of minor actinides derived from used reactor fuel. This approach engenders an array of challenges with respect to the licensing of the reactor: the U.S. Nuclear Regulatory Commission (NRC) has never completed the review of an application for an operating license for a sodium-cooled reactor. Moreover, the current U.S. regulatory structure has been developed to deal almost exclusively with light-water reactor (LWR) designs. Consequently, the NRC must either (1) develop a new regulatory process for SFRs, or (2) reinterpret the existing regulations to apply them, as appropriate, to SFR designs. During the 1980s and 1990s, the NRC conducted preliminary safety assessments of the Sodium Advanced Fast Reactor (SAFR) and the Power Reactor Innovative Small Module (PRISM) designs, and in that context, began to consider how to apply LWR-based regulations to SFR designs. This paper builds on that work to consider the challenges, from the reactor designer's point of view, associated with licensing an SFR today, considering (1) the evolution of SFR designs, (2) the particular requirements of reactor designs to meet GNEP objectives, and (3) the evolution of NRC regulations since the conclusion of the SAFR and PRISM reviews. (author)

  17. A Design of Alarm System in a Research Reactor Facility

    Park, Jaekwan; Jang, Gwisook; Seo, Sangmun; Suh, Yongsuk

    2013-01-01

    The digital alarm system has become an indispensable design to process a large amount of alarms of power plants. Korean research reactor operated for decades maintains a hybrid alarm system with both an analog annunciator and a digital alarm display. In this design, several alarms are indicated on an analog panel and digital display, respectively, and it requires more attention and effort of the operators. As proven in power plants, a centralized alarm system design is necessary for a new research reactor. However, the number of alarms and operators in a research reactor is significantly lesser than power plants. Thus, simplification should be considered as an important factor for the operation efficiency. This paper introduces a simplified alarm system. As advances in information technology, fully digitalized alarm systems have been applied to power plants. In a new research reactor, it will be more useful than an analog or hybrid configuration installed in research reactors decades ago. However, the simplification feature should be considered as an important factor because the number of alarms and number of operators in a research reactor is significantly lesser than in power plants

  18. Economic characteristics of a smaller, simpler reactor

    LaBar, M.; Bowers, H.

    1988-01-01

    Reduced load growth and heightened concern with economic risk has led to an expressed utility preference for smaller capacity additions. The Modular High Temperature Reactor (MHTGR) plant has been developed as a small, simple plant that has limited financial risk and is economically competitive with comparatively sized coal plants. Competitive economics is achieved by the simplifications made possible in a small MHTGR, reduction in the quantity of nuclear grade construction and design standardization and certification. Assessments show the MHTGR plant to have an economic advantage over coal plants for plant sizes from 270 MWe to 1080 MWe. Financial risk is limited by small unit sizes and short lead times that allow incremental deployment. Evaluations show the MHTGR incremental deployment capability to reduce negative cash flows by almost a factor of 2 relative to that required by a single large nuclear plant

  19. Order concerning a nuclear reactor shutdown

    Anon.

    1991-01-01

    Judgment of the State Administrative Court of Baden Wuerttemberg in head notes including: The authority of the Minister-President to give general guidelines includes the right to issue single directives; in matters of prime political significance he can take measures to realize such aims. - It is no extraneous consideration for the supervisory board under atomic energy law to point out in an order concerning a nuclear reactor shutdown that the disallowed operation of a nuclear plant conflicts with the obligation of the state to provide protection and constitutes a penal offence. Further a discourse on the assignment of discretionary powers under Paragraph 19 Section 3 Clause 2 No. 3 of the Atomic Energy Law. (HSCH) [de

  20. A friendly Maple module for one and two group reactor model

    Baptista, Camila O.; Pavan, Guilherme A.; Braga, Kelmo L.; Silva, Marcelo V.; Pereira, P.G.S.; Werner, Rodrigo; Antunes, Valdir; Vellozo, Sergio O.

    2015-01-01

    The well known two energy groups core reactor design model is revisited. A simple and friendly Maple module was built to cover the steps calculations of a plate reactor in five situations: 1. one group bare reactor, 2. two groups bare reactor, 3. one group reflected reactor, 4. 1-1/2 groups reflected reactor and 5. two groups reflected reactor. The results show the convergent path of critical size, as it should be. (author)