ISIS Training Reactor: A Reactor Dedicated to Education and Training for Students and Professionals

International Nuclear Information System (INIS)

Foulon, F.

2014-01-01

Conclusion: • INSTN strategy: complete theoretical courses by practical courses on the ISIS research reactor. • Training courses integrated both in Academic degree programs and continuing education. • 27 hours of training courses have been developed focusing on the practical and safety aspects of reactor operation. • The Education and Training activity became the main activity of ISIS reactor: 400 trainees/year; 360 hours/year; 40% in English. • Remote access to the Training courses: Internet Reactor Laboratory under development to be started from 2014 to broadcast training courses from ISIS reactor to guest institutions

Childhood vaccines and Kawasaki disease, Vaccine Safety Datalink, 1996-2006.

Science.gov (United States)

Abrams, Joseph Y; Weintraub, Eric S; Baggs, James M; McCarthy, Natalie L; Schonberger, Lawrence B; Lee, Grace M; Klein, Nicola P; Belongia, Edward A; Jackson, Michael L; Naleway, Allison L; Nordin, James D; Hambidge, Simon J; Belay, Ermias D

2015-01-03

Kawasaki disease is a childhood vascular disorder of unknown etiology. Concerns have been raised about vaccinations being a potential risk factor for Kawasaki disease. Data from the Vaccine Safety Datalink were collected on children aged 0-6 years at seven managed care organizations across the United States. Defining exposure as one of several time periods up to 42 days after vaccination, we conducted Poisson regressions controlling for age, sex, season, and managed care organization to determine if rates of physician-diagnosed and verified Kawasaki disease were elevated following vaccination compared to rates during all unexposed periods. We also performed case-crossover analyses to control for unmeasured confounding. A total of 1,721,186 children aged 0-6 years from seven managed care organizations were followed for a combined 4,417,766 person-years. The rate of verified Kawasaki disease was significantly lower during the 1-42 days after vaccination (rate ratio=0.50, 95% CL=0.27-0.92) and 8-42 days after vaccination (rate ratio=0.45, 95% CL=0.22-0.90) compared to rates during unexposed periods. Breaking down the analysis by vaccination category did not identify a subset of vaccines which was solely responsible for this association. The case-crossover analyses revealed that children with Kawasaki disease had lower rates of vaccination in the 42 days prior to symptom onset for both physician-diagnosed Kawasaki disease (rate ratio=0.79, 95% CL=0.64-0.97) and verified Kawasaki disease (rate ratio=0.38, 95% CL=0.20-0.75). Childhood vaccinations' studied did not increase the risk of Kawasaki disease; conversely, vaccination was associated with a transient decrease in Kawasaki disease incidence. Verifying and understanding this potential protective effect could yield clues to the underlying etiology of Kawasaki disease. Copyright © 2014. Published by Elsevier Ltd.

GE Nuclear Hitachi Energy is prepared for the nuclear Renaissance

International Nuclear Information System (INIS)

Carelli, J. M.

2008-01-01

GE Hitachi Nuclear Energy (GEH) is offering two technologies to meet the needs of utilities planning new nuclear projects. An aging workforce, new technological developments and forecasts of considerable new construction projects, raise questions for the entire industry regarding our human resources. In order to prepare for the coming resurgence in new nuclear projects, GEH taking positive action to ensure that adequate human resources are available. From early learning programs that encourage young students to pursue careers in science and technology, to hands-on vocational and engineering programs, GEH works with communities and young people to recruit and train the workforce that will enable our success. (Author)

Interdisciplinary Integrated Engineering Development Course in HITACHI

Science.gov (United States)

Ojima, Masahiro

As an example of interdisciplinary education for engineers in private companies, IED (Integrated Engineering Development) course at HITACHI Ltd. is presented. To help 30 years old or so promising engineers create a new product based on a new technology, one year term course is designed for four types of engineers; mechanical, electric & electronic, information software, and digital systems. Each course has core basic technologies plus related supplementary subjects to promote an interdisciplinary integrated engineer. Not only lectures given by university professors but heavy duty home work is also given by senior engineers of HITACHI to make them apply basic theory to practical problems. Furthermore, self development planning, leadership development program and technology-marketing project are introduced to promote human skills and business sense needed for technology leaders in company.

Two cases of Kawasaki disease presented with acute febrile jaundice.

Science.gov (United States)

Kaman, Ayşe; Aydın-Teke, Türkan; Gayretli-Aydın, Zeynep Gökçe; Öz, Fatma Nur; Metin-Akcan, Özge; Eriş, Deniz; Tanır, Gönül

2017-01-01

Kawasaki disease is an acute, systemic vasculitis of unknown etiology. Although gastrointestinal involvement does not belong to the classic diagnostic criteria; diarrhea, abdominal pain, hepatic dysfunction, hydrops of gallbladder, and acute febrile cholestatic jaundice are reported in patients with Kawasaki disease. We describe here two cases presented with fever, and acute jaundice as initial features of Kawasaki disease.

The rearing progress and varietal characteristics in new cultivar red bunching onion [Allium fistulosum] 'Hitachi-benikko'

International Nuclear Information System (INIS)

Kaizuka, T.; Suzuki, M.

2006-01-01

In order to raise a red bunching onion, a thick leaf sheath with stabilized coloring, breeding has been carried out since 1984. 'Hitachi-benikko' was developed in 1997.It was selected from soft X-ray irradiated seeds in 1996, between crossing of ('Chouetsu' x 'A3-middle') x 'Akasyonai-strain'. The color of the leaf sheath in 'Hitachi-benikko' is stabilizes deep and the leaf sheath of 'Hitachi-benikko' is thick, because it has fewer tillers than 'Benizome'. If 'Hitachi-benikko' is planted in autumn, the growth and development increases, and the quality of the leaf shealth is greater than planting in spring. Standard amount of applied fertilizer is the best because a 20% reduction in amount of application slightly decreases the growth and development of 'Hitachi-benikko'. If the spacing between plants is 15 cm or 20 cm, the growth and development increases, and the quality of the leaf shealth is greater than 5 cm or 10 cm in 'Hitachi-benikko'

Myocardial ischemia in Kawasaki disease

International Nuclear Information System (INIS)

Fukuda, Tsuyoshi

1993-01-01

The detection of myocardial ischemia is essential for evaluation of patients with Kawasaki disease, especially who have had coronary artery lesions. To evaluate the clinical efficacy of Tl-201 single photon emission computed tomography (SPECT) after dipyridamole infusion (maximum dose 0.70 mg/kg) for detecting myocardial ischemia, 44 patients with Kawasaki disease aged 7.7±4.8 years at the study and 10 age matched controls were observed. In the Kawasaki disease group, significant coronary artery stenosis was observed in 14, coronary aneurysm without stenosis in 18, the regression of the coronary aneurysms in 2 and without coronary lesions in 10 patients. In 24 of 44 patients, treadmill exercise stress test was also performed at the same period. Myocardial ischemic changes were observed in 11 patients, all combined with significant coronary artery stenosis. The sensitivity of SPECT for detection of overall coronary stenosis was 79%, coronary that of treadmill exercise test was only 33% (p<0.001). Furthermore, among the patients having significant coronary stenosis, the severity score was significantly elevated in patients who had electrocardiographic abnormal Q wave compared to those without abnormal Q wave (51.0±38.8 versus 20.0±12.1, p<0.05). These data suggest that the pharmacological stress scintigraphy using dipyridamole injection provides not only the accurate detection but quantitative evaluation of myocardial ischemia in these patients. This noninvasive technique may become one of the most useful index for detection and follow-up of myocardial ischemia in Kawasaki disease. (author)

Heart and coronary artery damage related to Kawasaki syndrome

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A. A. Leontyeva

2014-01-01

Full Text Available Kawasaki syndrome is an acute systemic vasculitis of unknown etiology, which mainly affects children within the first 5 years of fife. At the present time, Kawasaki syndrome is recognized to be a leading cause of acquired organic heart diseases in children, which may result in coronary heart disease, myocardial infarction, and sudden death in children and young people. Most complications are associated with the cardiovascular system, with coronary artery changes in particular. Transthoracic echocardiography, which, besides coronary artery assessment, makes it possible to evaluate right and left ventricular systolic and diastolic functions and to study the cardiac valves and changes in pericardial effusion, is a major technique in Kawasaki syndrome. The paper outlines an update on the epidemiology, etiology, pathogenetic mechanisms, and pathomorphology of Kawasaki syndrome and considers possible coronary and noncoronary changes, outcomes, and clinical manifestations.

Training courses at VR-1 reactor

International Nuclear Information System (INIS)

Sklenka, L.; Kropik, M.

2006-01-01

This paper describes one of the main purposes of the VR-1 training reactor utilization - i.e. extensive educational program. The educational program is intended for the training of university students and selected nuclear power plant personnel. The training courses provide them experience in reactor and neutron physics, dosimetry, nuclear safety and operation of nuclear facilities. At present, the training course participants can go through more than 20 standard experimental exercises; particular exercises for special training can be prepared. Approximately 200 university students become familiar with the reactor (lectures, experiments, experimental and diploma works, etc.) every year. About 12 different faculties from Czech universities use the reactor. International co-operation with European universities in Germany, Hungary, Austria, Slovakia, Holland and UK is frequent. The VR-1 reactor takes also part in Eugene Wigner Course on Reactor Physics Experiments in the framework of European Nuclear Educational Network (ENEN) association. Recently, training courses for Bulgarian research reactor specialists supported by IAEA were carried out. An attractive program including demonstration of reactor operation is prepared also for high school students. Every year, more than 1500 high school students come to visit the reactor, as do many foreigner visitors. (author)

Doença de Kawasaki: experiência clínica em hospital universitário Kawasaki disease: clinical experience in a university hospital

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Angela Esposito Ferronato

2010-06-01

Full Text Available OBJETIVO: A doença de Kawasaki é uma vasculite sistêmica aguda de etiologia desconhecida. Seu diagnóstico baseia-se em critérios clínicos. O objetivo deste estudo foi descrever os casos de pacientes com doença de Kawasaki internados no Hospital Universitário da Universidade de São Paulo entre janeiro/2000 e junho/2008. MÉTODOS: Dentre todos os pacientes internados na Enfermaria de Pediatria no período acima, foram selecionados aqueles cujo CID de alta foi doença de Kawasaki. Realizou-se estudo descritivo por meio da análise dos prontuários dessas crianças. RESULTADOS: Foram encontrados 18 casos. A média de internações foi de 2,1 casos/ano. A idade variou de três meses a nove anos. A proporção meninos:meninas foi 1:1,25. Receberam outros diagnósticos prévios 17 pacientes, sendo escarlatina em 2/3 dos casos. O tempo de febre antes do diagnóstico variou de cinco a 11 dias. Nove crianças apresentaram quatro sinais sugestivos de doença de Kawasaki; oito apresentaram cinco sinais e uma apresentou dois sinais, o que foi considerado doença de Kawasaki incompleta. Receberam gamaglobulina 15 crianças (entre o sexto e o décimo dias de evolução e 11 (73% ficaram afebris após infusão da medicação. Os demais tiveram febre até 24 horas após a administração. Todos os pacientes realizaram ecocardiograma e três apresentaram aneurisma leve da coronária. CONCLUSÕES: A doença de Kawasaki é habitualmente confundida com outras doenças, o que causa retardo no tratamento e aumento no risco de complicações cardíacas.OBJECTIVE: Kawasaki disease is an acute systemic vasculitis of unknown etiology. Its diagnosis is based on clinical criteria. This study aimed to describe Kawasaki disease cases treated at the University Hospital of Universidade de São Paulo, from January/2000 to June/2008. METHODS: Among all patients admitted to the pediatric ward during this period, patients whose discharge ICD was Kawasaki disease were

Training and Certification of Research Reactor Personnel

International Nuclear Information System (INIS)

Zarina Masood

2011-01-01

The safe operation of a research reactor requires that reactor personnel be fully trained and certified by the relevant authorities. Reactor operators at PUSPATI TRIGA Reactor underwent extensive training and are certified, ever since the reactor first started its operation in 1982. With the emphasis on enhancing reactor safety in recent years, reactor operator training and certification have also evolved. This paper discusses the changes that have to be implemented and the challenges encountered in developing a new training programme to be in line with the national standards. (author)

Differential expression of miR-145 in children with Kawasaki disease.

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Chisato Shimizu

Full Text Available Kawasaki disease is an acute, self-limited vasculitis of childhood that can result in structural damage to the coronary arteries. Previous studies have implicated the TGF-β pathway in disease pathogenesis and generation of myofibroblasts in the arterial wall. microRNAs are small non-coding RNAs that modulate gene expression at the post-transcriptional level and can be transported between cells in extracellular vesicles. To understand the role that microRNAs play in modifying gene expression in Kawasaki disease, we studied microRNAs from whole blood during the acute and convalescent stages of the illness.RNA isolated from the matched whole blood of 12 patients with acute and convalescent Kawasaki disease were analyzed by sequencing of small RNA. This analysis revealed six microRNAs (miRs-143, -199b-5p, -618, -223, -145 and -145* (complementary strand whose levels were significantly elevated during the acute phase of Kawasaki disease. The result was validated using targeted qRT-PCR using an independent cohort (n = 16. miR-145, which plays a critical role in the differentiation of neutrophils and vascular smooth muscle cells, was expressed at high levels in blood samples from acute Kawasaki disease but not adenovirus-infected control patients (p = 0.005. miR-145 was also detected in small extracellular vesicles isolated from acute Kawasaki disease plasma samples. Pathway analysis of the predicted targets of the 6 differentially expressed microRNAs identified the TGF-β pathway as the top pathway regulated by microRNAs in Kawasaki disease.Sequencing of small RNA species allowed discovery of microRNAs that may participate in Kawasaki disease pathogenesis. miR-145 may participate, along with other differentially expressed microRNAs, in regulating expression of genes in the TGF-β pathway during the acute illness. If the predicted target genes are confirmed, our findings suggest a model of Kawasaki disease pathogenesis whereby miR-145 modulates TGF

Kawasaki disease following Rocky Mountain spotted fever: a case report.

Science.gov (United States)

Bal, Aswine K; Kairys, Steven W

2009-07-06

Kawasaki disease is an idiopathic acute systemic vasculitis of childhood. Although it simulates the clinical features of many infectious diseases, an infectious etiology has not been established. This is the first reported case of Kawasaki disease following Rocky Mountain spotted fever. We report the case of a 4-year-old girl who presented with fever and petechial rash. Serology confirmed Rocky Mountain spotted fever. While being treated with intravenous doxycycline, she developed swelling of her hands and feet. She had the clinical features of Kawasaki disease which resolved after therapy with intravenous immune globulin (IVIG) and aspirin. This case report suggests that Kawasaki disease can occur concurrently or immediately after a rickettsial illness such as Rocky Mountain spotted fever, hypothesizing an antigen-driven immune response to a rickettsial antigen.

Doença de Kawasaki Kawasaki disease

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Patrícia Aparecida de Castro

2009-08-01

Full Text Available A doença de Kawasaki é vasculite sistêmica e aguda de etiologia desconhecida. Constitui a principal causa de doença cardíaca adquirida em crianças nos EUA. Ocorre mais frequentemente em meninos, 80% dos casos em crianças com menos de cinco anos, sendo rara após os oito anos. Pode atingir crianças de todas as raças, tendo maior incidência entre os descendentes asiáticos. Caracteriza-se por febre, conjuntivite bilateral não exsudativa, eritema e edema de língua, lábios e mucosa oral, alterações de extremidades, linfonodomegalia cervical, exantema polimórfico. Aneurismas e estenoses de artérias coronárias são comuns em percentual que varia de 20 a 25% dos pacientes não tratados, podendo posteriormente levar a infarto agudo do miocárdio e morte súbita. O tratamento com imunoglobulina intravenosa é efetivo e deve ser iniciado precocemente a fim de evitar sequelas cardíacas. O desenvolvimento de testes diagnósticos, terapêuticas mais específicas e a prevenção dessa doença potencialmente fatal em crianças dependem dos contínuos avanços na determinação de sua etiopatogenia.Kawasaki disease is a systemic acute vasculitis of unknown etiology. It is the leading cause of acquired heart disease in children in the USA. It occurs more frequently in boys and eighty percent of the cases occur in children under five years of age. The disease rarely occurs after eight years and it can affect children of all races, with higher incidence among Asian descendants. Kawasaki disease is characterized by fever, bilateral non-exudative conjunctivitis, redness and swelling of the tongue, lips and oral mucosa, abnormalities in the extremities, cervical lymph node, and polymorphic exanthema. Aneurysms and stenoses of coronary arteries occur in pproximately 20 to 25% of untreated patients and subsequently can lead to acute myocardial infarction and sudden death. Treatment with intravenous immunoglobulin is effective and should be initiated

Training of research reactor personnel

International Nuclear Information System (INIS)

Cherruau, F.

1980-01-01

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

Kawasaki disease following Rocky Mountain spotted fever: a case report

Directory of Open Access Journals (Sweden)

Bal Aswine K

2009-07-01

Full Text Available Abstract Introduction Kawasaki disease is an idiopathic acute systemic vasculitis of childhood. Although it simulates the clinical features of many infectious diseases, an infectious etiology has not been established. This is the first reported case of Kawasaki disease following Rocky Mountain spotted fever. Case presentation We report the case of a 4-year-old girl who presented with fever and petechial rash. Serology confirmed Rocky Mountain spotted fever. While being treated with intravenous doxycycline, she developed swelling of her hands and feet. She had the clinical features of Kawasaki disease which resolved after therapy with intravenous immune globulin (IVIG and aspirin. Conclusion This case report suggests that Kawasaki disease can occur concurrently or immediately after a rickettsial illness such as Rocky Mountain spotted fever, hypothesizing an antigen-driven immune response to a rickettsial antigen.

77 FR 13367 - General Electric-Hitachi Global Laser Enrichment, LLC, Proposed Laser-Based Uranium Enrichment...

Science.gov (United States)

2012-03-06

... NUCLEAR REGULATORY COMMISSION [NRC-2009-0157] General Electric-Hitachi Global Laser Enrichment, LLC, Proposed Laser-Based Uranium Enrichment Facility, Wilmington, NC AGENCY: Nuclear Regulatory... Impact Statement (EIS) for the proposed General Electric- Hitachi Global Laser Enrichment, LLC (GLE...

Genetics Home Reference: Kawasaki disease

Science.gov (United States)

... how do mutations occur? How can gene mutations affect health and development? More about ... but the inheritance pattern is unknown. Children of parents who have had Kawasaki disease have twice the ...

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

International Nuclear Information System (INIS)

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

Association between Kawasaki Disease and Autism: A Population-Based Study in Taiwan

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Ho-Chang Kuo

2014-04-01

Full Text Available Objective: The association between Kawasaki disease and autism has rarely been studied in Asian populations. By using a nationwide Taiwanese population-based claims database, we tested the hypothesis that Kawasaki disease may increase the risk of autism in Taiwan. Materials and Methods: Our study cohort consisted of patients who had received the diagnosis of Kawasaki disease (ICD-9-CM: 446.1 between 1997 and 2005 (N = 563. For a comparison cohort, five age- and gender-matched control patients for every patient in the study cohort were selected using random sampling (N = 2,815. All subjects were tracked for 5 years from the date of cohort entry to identify whether they had developed autism (ICD-9-CM code 299.0 or not. Cox proportional hazard regressions were then performed to evaluate 5-year autism-free survival rates. Results: The main finding of this study was that patients with Kawasaki disease seem to not be at increased risk of developing autism. Of the total patients, four patients developed autism during the 5-year follow-up period, among whom two were Kawasaki disease patients and two were in the comparison cohort. Further, the adjusted hazard ratios (AHR (AHR: 4.81; 95% confidence interval: 0.68–34.35; P = 0.117 did not show any statistical significance between the Kawasaki disease group and the control group during the 5-year follow-up. Conclusion: Our study indicated that patients with Kawasaki disease are not at increased risk of autism.

Self-Sustaining Thorium Boiling Water Reactors

International Nuclear Information System (INIS)

Greenspan, Ehud; Gorman, Phillip M.; Bogetic, Sandra; Seifried, Jeffrey E.; Zhang, Guanheng; Varela, Christopher R.; Fratoni, Massimiliano; Vijic, Jasmina J.; Downar, Thomas; Hall, Andrew; Ward, Andrew; Jarrett, Michael; Wysocki, Aaron; Xu, Yunlin; Kazimi, Mujid; Shirvan, Koroush; Mieloszyk, Alexander; Todosow, Michael; Brown, Nicolas; Cheng, Lap

2015-01-01

The primary objectives of this project are to: Perform a pre-conceptual design of a core for an alternative to the Hitachi proposed fuel-self- sustaining RBWR-AC, to be referred to as a RBWR-Th. The use of thorium fuel is expected to assure negative void coefficient of reactivity (versus positive of the RBWR-AC) and improve reactor safety; Perform a pre-conceptual design of an alternative core to the Hitachi proposed LWR TRU transmuting RBWR-TB2, to be referred to as the RBWR-TR. In addition to improved safety, use of thorium for the fertile fuel is expected to improve the TRU transmutation effectiveness; Compare the RBWR-Th and RBWR-TR performance against that of the Hitachi RBWR core designs and sodium cooled fast reactor counterparts - the ARR and ABR; and, Perform a viability assessment of the thorium-based RBWR design concepts to be identified along with their associated fuel cycle, a technology gap analysis, and a technology development roadmap. A description of the work performed and of the results obtained is provided in this Overview Report and, in more detail, in the Attachments. The major findings of the study are summarized.

Self-Sustaining Thorium Boiling Water Reactors

Energy Technology Data Exchange (ETDEWEB)

Greenspan, Ehud [Univ. of California, Berkeley, CA (United States); Gorman, Phillip M. [Univ. of California, Berkeley, CA (United States); Bogetic, Sandra [Univ. of California, Berkeley, CA (United States); Seifried, Jeffrey E. [Univ. of California, Berkeley, CA (United States); Zhang, Guanheng [Univ. of California, Berkeley, CA (United States); Varela, Christopher R. [Univ. of California, Berkeley, CA (United States); Fratoni, Massimiliano [Univ. of California, Berkeley, CA (United States); Vijic, Jasmina J. [Univ. of California, Berkeley, CA (United States); Downar, Thomas [Univ. of Michigan, Ann Arbor, MI (United States); Hall, Andrew [Univ. of Michigan, Ann Arbor, MI (United States); Ward, Andrew [Univ. of Michigan, Ann Arbor, MI (United States); Jarrett, Michael [Univ. of Michigan, Ann Arbor, MI (United States); Wysocki, Aaron [Univ. of Michigan, Ann Arbor, MI (United States); Xu, Yunlin [Univ. of Michigan, Ann Arbor, MI (United States); Kazimi, Mujid [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Shirvan, Koroush [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Mieloszyk, Alexander [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Todosow, Michael [Brookhaven National Lab. (BNL), Upton, NY (United States); Brown, Nicolas [Brookhaven National Lab. (BNL), Upton, NY (United States); Cheng, Lap [Brookhaven National Lab. (BNL), Upton, NY (United States)

2015-03-15

The primary objectives of this project are to: Perform a pre-conceptual design of a core for an alternative to the Hitachi proposed fuel-self- sustaining RBWR-AC, to be referred to as a RBWR-Th. The use of thorium fuel is expected to assure negative void coefficient of reactivity (versus positive of the RBWR-AC) and improve reactor safety; Perform a pre-conceptual design of an alternative core to the Hitachi proposed LWR TRU transmuting RBWR-TB2, to be referred to as the RBWR-TR. In addition to improved safety, use of thorium for the fertile fuel is expected to improve the TRU transmutation effectiveness; Compare the RBWR-Th and RBWR-TR performance against that of the Hitachi RBWR core designs and sodium cooled fast reactor counterparts - the ARR and ABR; and, Perform a viability assessment of the thorium-based RBWR design concepts to be identified along with their associated fuel cycle, a technology gap analysis, and a technology development roadmap. A description of the work performed and of the results obtained is provided in this Overview Report and, in more detail, in the Attachments. The major findings of the study are summarized.

Adult Kawasaki's disease with myocarditis, splenomegaly, and highly elevated serum ferritin levels.

Science.gov (United States)

Cunha, Burke A; Pherez, Francisco M; Alexiadis, Varvara; Gagos, Marios; Strollo, Stephanie

2010-01-01

Kawasaki's disease is a disease of unknown cause. The characteristic clinical features of Kawasaki's disease are fever> or =102 degrees F for> or =5 days accompanied by a bilateral bulbar conjunctivitis/conjunctival suffusion, erythematous rash, cervical adenopathy, pharyngeal erythema, and swelling of the dorsum of the hands/feet. Kawasaki's disease primarily affects children and is rare in adults. In children, Kawasaki's disease is more likely to be associated with aseptic meningitis, coronary artery aneurysms, and thrombocytosis. In adult Kawasaki's disease, unilateral cervical adenopathy, arthritis, conjunctival suffusion/conjunctivitis, and elevated serum transaminases (serum glutamic oxaloacetic transaminase [SGOT]/serum glutamate pyruvate transaminase [SGPT]) are more likely. Kawasaki's disease in adults may be mimicked by other acute infections with fever and rash, that is, group A streptococcal scarlet fever, toxic shock syndrome (TSS), and Rocky Mountain Spotted Fever (RMSF). Because there are no specific tests for Kawasaki's disease, diagnosis is based on clinical criteria and the syndromic approach. In addition to rash and fever, scarlet fever is characterized by circumoral pallor, oropharyngeal edema, Pastia's lines, and peripheral eosinophilia, but not conjunctival suffusion, splenomegaly, swelling of the dorsum of the hands/feet, thrombocytosis, or an elevated SGOT/SGPT. In TSS, in addition to rash and fever, there is conjunctival suffusion, oropharyngeal erythema, and edema of the dorsum of the hands/feet, an elevated SGOT/SGPT, and thrombocytopenia. Patients with TSS do not have cervical adenopathy or splenomegaly. RMSF presents with fever and a maculopapular rash that becomes petechial, first appearing on the wrists/ankles after 3 to 5 days. RMSF is accompanied by a prominent headache, periorbital edema, conjunctival suffusion, splenomegaly, thrombocytopenia, an elevated SGOT/SGPT, swelling of the dorsum of the hands/feet, but not oropharyngeal

Strontium-90 determination in air dust filter using solid phase extraction after the accident of FD-NPS

International Nuclear Information System (INIS)

Zhang, Zijian; Kakitani, Shunsuke; Ninomiya, Kazuhiko

2013-01-01

Radioactivities of Sr-90 in air-dust filters collected in Hitachi, Kawasaki and Toyonaka were determined using solid state extraction method and low background beta-ray counting system. In Hitachi, though the Sr-90 activity concentration was decreased with time, the activity rates of Sr-90/Cs-137 kept about 10"-"3 order. This fact suggests that Sr-90 transportation behavior in the atmosphere is similar to that of Cs-137 during the time of sample collection. (author)

Secular distribution of radioactive concentration in the atmosphere at Fukushima, Hitachi and Marumori

International Nuclear Information System (INIS)

Zhang, ZiJian; Kakitani, Shunsuke; Ninomiya, Kazuhiko; Takahashi, Naruto; Shinohara, Atsushi; Yamaguchi, Yoshiaki; Yoshimura, Takashi; Kita, Kazuyuki; Watanabe, Akira

2013-01-01

Our group started gamma ray measurement of air dust sample after the Fukushima Dai-ichi nuclear power station accident. Air dust filters was collected at Hitachi, Fukushima and Marumori. The activity of Cs-134 and Cs-137 was determined by germanium semiconductor detector. The radiocesium activity concentration in air dust(Bq/m"3) after October 2011 were stable and 6.2×10"-"6 at Hitachi, 3.0×10"-"4 at Fukushima and 1.3×10"-"4 at Marumori. (author)

Tomographic myocardial perfusion scintigraphy in children with Kawasaki disease

International Nuclear Information System (INIS)

Spielmann, R.P.; Nienaber, C.A.; Hausdorf, G.; Montz, R.

1987-01-01

Myocardial infarction and stenotic coronary lesions are serious late complications in children with Kawasaki disease. For the noninvasive assessment of myocardial perfusion, dipyridamole-redistribution 201 Tl emission computed tomography (ECT) was performed in seven children (age 2 8/12-8 7/12 yr) 3-20 mo after the acute stage of the disease. In all patients, coronary aneurysms had been demonstrated by cross-sectional echocardiography. The scintigrams of six children showed no significant regional reduction of myocardial thallium uptake. These children had remained asymptomatic since the acute stage of Kawasaki disease. Persistent and transient thallium defects were present in one child with documented myocardial infarction. For this patient, obstruction of corresponding coronary vessels was confirmed by contrast angiography. It is suggested, that 201 Tl ECT after dipyridamole-induced vasodilation may be used as a safe alternative to invasive coronary angiography for follow-up investigations in patients with Kawasaki disease

Spontaneous closure of patent ductus arteriosus after an episode of Kawasaki disease: a case report

Directory of Open Access Journals (Sweden)

Lin Ming-Chih

2012-01-01

Full Text Available Abstract Introduction Kawasaki disease is regarded as systemic vasculitis. Many experts believe that not only coronary arteries but also other small arteries are involved during the period of systemic inflammation. However, the evidence to support this point view is limited. Case presentation We report the case of a one-year-four-month-old Taiwanese girl whose patent ductus arteriosus was incidentally found during an episode of Kawasaki disease. The ductus closed spontaneously after the acute phase of Kawasaki disease. Conclusions In this patient, the patent ductus arteriosus may have closed spontaneously after Kawasaki disease due to its involvement in the generalized vasculitis that this disease incurs. This would support the theory that the vasculitis of Kawasaki disease is limited not only to coronary arteries but also to all medium- sized arteries.

Blood N-terminal Pro-brain Natriuretic Peptide and Interleukin-17 for Distinguishing Incomplete Kawasaki Disease from Infectious Diseases.

Science.gov (United States)

Wu, Ling; Chen, Yuanling; Zhong, Shiling; Li, Yunyan; Dai, Xiahua; Di, Yazhen

2015-06-01

To explore the diagnostic value of blood N-terminal pro-brain natriuretic peptide (NT-proBNP) and interleukin-17(IL-17) for incomplete Kawasaki disease. Patients with Kawasaki disease, Incomplete Kawasaki disease and unclear infectious fever were included in this retrospective study. Their clinical features, and laboratory test results of blood NT-proBNP and IL-17 were collected and compared. 766 patients with complete clinical information were recruited, consisting of 291 cases of Kawasaki disease, 74 cases of incomplete Kawasaki disease, and 401 cases of unclear infectious diseases. When the consistency with indicator 2 and 3 in Kawasaki disease diagnosis criteria was assessed with blood IL-17 ?11.55 pg/mL and blood NT-proBNP ? 225.5 pg/dL as the criteria, the sensitivity and specificity for distinguishing incomplete Kawasaki disease and infectious diseases reached 86.5% and 94.8%, respectively. When we chose the consistency with indicator 1 and 2 in Kawasaki disease diagnosis criteria, the appearance of decrustation and/or the BCG erythema, blood IL-17 ?11.55 pg/mL and blood NT-Pro BNP ?225.5 pg/dL as the criteria, the sensitivity and specificity for distinguishing incomplete Kawasaki disease and infectious diseases was 43.2% and 100%, respectively. Blood NT-proBNP and IL-17 are useful laboratory indicators for distinguishing incomplete Kawasaki disease and infectious diseases at the early stage.

Safety operation of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.

2001-01-01

There are three nuclear research reactors in the Czech Republic in operation now: light water reactor LVR-15, maximum reactor power 10 MW t , owner and operator Nuclear Research Institute Rez; light water zero power reactor LR-0, maximum reactor power 5 kW t , owner and operator Nuclear Research Institute Rez and training reactor VR-1 Sparrow, maximum reactor power 5 kW t , owner and operate Faculty of Nuclear Sciences and Physical Engineering, CTU in Prague. The training reactor VR-1 Vrabec 'Sparrow', operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly it is designed for training the students of Czech universities, preparing the experts for the Czech nuclear programme, as well as for certain research work, and for information programmes in the nuclear programme, as well as for certain research work, and for information programmes in sphere of using the nuclear energy (public relations). (author)

Next generation reactor development activity at Hitachi, Ltd

International Nuclear Information System (INIS)

Yamashita, Junichi

2005-01-01

Developments of innovative nuclear systems in Japan have been highly requested to cope with uncertain future nuclear power generation and fuel cycle situation. Next generation reactor system shall be surely deployed earlier to be capable to provide with several options such as plutonium multi-recycle, intermediate storage of spent fuels, simplified reprocessing of spent fuels and separated storage of 'Pu+FP' and 'U', spent fuels storage after Pu LWR recycle and their combinations, while future reactor system will be targeted at ideal fuel recycle system of higher breeding gain and transmutation of radioactive wastes. Modified designs of the ABWR at large size and medium and small size have been investigated as well as a BWR based RMWR and a supercritical-pressure LWR to ensure safety and improve economics. Advanced fuel cycle technologies of a combination of fluoride volatility process and PUREX process with high decontamination (FLUOREX process) and a modified fluoride volatility process with low decontamination have been developed. (T. Tanaka)

Kawasaki disease: review of 21 cases

Directory of Open Access Journals (Sweden)

Cem Arat

2016-03-01

Conclusion: Kawasaki disease has difficulty in diagnosis because of having broad spectrum of presenting symptoms. Early diagnosis and treatment is very important in preventing coronary artery abnormalities. [Cukurova Med J 2016; 41(1.000: 97-104

Multimodality Cardiac Imaging in a Patient with Kawasaki Disease and Giant Aneurysms

Directory of Open Access Journals (Sweden)

Ranjini Srinivasan

2016-01-01

Full Text Available Kawasaki disease is a well-known cause of acquired cardiac disease in the pediatric and adult population, most prevalent in Japan but also seen commonly in the United States. In the era of intravenous immunoglobulin (IVIG treatment, the morbidity associated with this disease has decreased, but it remains a serious illness. Here we present the case of an adolescent, initially diagnosed with Kawasaki disease as an infant, that progressed to giant aneurysm formation and calcification of the coronary arteries. We review his case and the literature, focusing on the integral role of multimodality imaging in managing Kawasaki disease.

Hitachi's proposed DCS solution for new build CANDU EC6 using the G-HIACS unified platform

Energy Technology Data Exchange (ETDEWEB)

Tan, D.; Ishii, K.; Otsuka, Y.; Uemura, K., E-mail: daisuke.tan.ye@hitachi.com [Hitachi Ltd., Infrastructure Systems Co., Ibaraki (Japan); Marko, P.E. [Hitachi Power Systems Canada Ltd., Power and Industry Div., Ontario (Canada)

2013-07-01

Hitachi Ltd. has developed the safe and secure functional safety DCS controller for potential new build NPP projects in the global market. Hitachi has improved the availability, maintainability, and reliability for its latest DCS systems named G-HIACS. In this latest paper on its DCS product development program, Hitachi would like to report a proposed DCS solution for new build CANDU NSP and BOP based on the G-HIACS Unified Architecture (R800FS/HSC800FS vSAFE Functional Safety Controller and R900/HSC900 General Purpose Controller) hybrid control system. (author)

Education and Training on ISIS Research Reactor

International Nuclear Information System (INIS)

Foulon, F.; Badeau, G.; Lescop, B.; Wohleber, X.

2013-01-01

In the frame of academic and vocational programs the National Institute for Nuclear Science and Technology uses the ISIS research reactor as a major tool to ensure a practical and comprehensive understanding of the nuclear reactor physics, principles and operation. A large set of training courses have been developed on ISIS, optimising both the content of the courses and the pedagogical approach. Programs with duration ranging from 3 hours (introduction to reactor operation) to 24 hours (full program for the future operators of research reactors) are carried out on ISIS reactor. The reactor is operated about 350 hours/year for education and training, about 40 % of the courses being carried out in English. Thus, every year about 400 trainees attend training courses on ISIS reactor. We present here the ISIS research reactor and the practical courses that have been developed on ISIS reactor. Emphasis is given to the pedagogical method which is used to focus on the operational and safety aspects, both in normal and incidental operation. We will present the curricula of the academic and vocational courses in which the practical courses are integrated, the courses being targeted to a wide public, including operators of research reactors, engineers involved in the design and operation of nuclear reactors as well as staff of the regulatory body. We address the very positive impact of the courses on the development of the competences and skills of participants. Finally, we describe the Internet Reactor Laboratories (IRL) that are under development and will consist in broadcasting the training courses via internet to remote facilities or institutions

Education and Training on ISIS Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Foulon, F.; Badeau, G.; Lescop, B.; Wohleber, X. [French Atomic Energy and Alternative Energies Commission, Paris (France)

2013-07-01

In the frame of academic and vocational programs the National Institute for Nuclear Science and Technology uses the ISIS research reactor as a major tool to ensure a practical and comprehensive understanding of the nuclear reactor physics, principles and operation. A large set of training courses have been developed on ISIS, optimising both the content of the courses and the pedagogical approach. Programs with duration ranging from 3 hours (introduction to reactor operation) to 24 hours (full program for the future operators of research reactors) are carried out on ISIS reactor. The reactor is operated about 350 hours/year for education and training, about 40 % of the courses being carried out in English. Thus, every year about 400 trainees attend training courses on ISIS reactor. We present here the ISIS research reactor and the practical courses that have been developed on ISIS reactor. Emphasis is given to the pedagogical method which is used to focus on the operational and safety aspects, both in normal and incidental operation. We will present the curricula of the academic and vocational courses in which the practical courses are integrated, the courses being targeted to a wide public, including operators of research reactors, engineers involved in the design and operation of nuclear reactors as well as staff of the regulatory body. We address the very positive impact of the courses on the development of the competences and skills of participants. Finally, we describe the Internet Reactor Laboratories (IRL) that are under development and will consist in broadcasting the training courses via internet to remote facilities or institutions.

Reactor safety training for decision making

International Nuclear Information System (INIS)

Scott, C.K.

2003-01-01

The purpose of this paper is to describe an approach to reactor safety training for technical staff working at an operating station. The concept being developed is that, when the engineer becomes a registered professional engineer, they have sufficient reactor safety knowledge to perform independent technical work without compromising the safety of the plant. This goal would be achieved with a focused training program while working as an engineer-in-training (four years in NB). (author)

76 FR 4948 - GE Hitachi Nuclear Energy; Notice of Receipt and Availability of an Application for Renewal of...

Science.gov (United States)

2011-01-27

... NUCLEAR REGULATORY COMMISSION [NRC-2011-0020] GE Hitachi Nuclear Energy; Notice of Receipt and... December 7, 2010, GE Hitachi Nuclear Energy (GEH) filed with the U.S. Nuclear Regulatory Commission (NRC..., Certifications, and Approvals for Nuclear Power Plants,'' an application for a design certification (DC) renewal...

New training reactor at Dresden Technical University

International Nuclear Information System (INIS)

Hansen, W.; Knorr, J.; Wolf, T.

2006-01-01

A total of 14 low-power (up to 10 W) training reactors have been operated at German universities, 9 of them officially classified as being operational in 2004, though for very different uses. This number is expected to drop sharply. The only comprehensive upgrading of a training reactor took place at Dresden Technical University: AKR-2, the most modern facility in Germany, started routine operation in April 2005, under a newly granted license pursuant to Sec. 7, Subsec. 1 of the German Atomic Energy Act, for training students in nuclear technology, for suitable research projects, and a a center of information about reactor technology and nuclear technology for the interested public. One special aspect of this refurbishment was the installation of digital safety I and C systems of the TELEPERM XS line, which are used also in other modern plants. This fact, plus the easy possibility to use the plant for many basic experiments in reactor physics and radiation protection, make the AKR-2 attractive also to other users (e.g. for training reactor personnel or other persons working in nuclear technology). (orig.)

Basic training of nuclear power reactor personnel

International Nuclear Information System (INIS)

Palabrica, R.J.

1981-01-01

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

IAEA Activities supporting education and training at research reactors

International Nuclear Information System (INIS)

Peld, N.D.; Ridikas, D.

2013-01-01

Full-text: Through the provision of neutrons for experiments and their historical association with universities, research reactors have played a prominent role in nuclear education and training of students, scientists and radiation workers. Today education and training remains the foremost application of research reactors, involving close to 160 facilities out of 246 operational. As part of its mandate to facilitate and expand the contribution of atomic energy to peace, health and prosperity throughout the world, the IAEA administers a number of activities intended to promote nuclear research and enable access to nuclear technology for peaceful purposes, one of which is the support of various education and training measures involving research reactors. In the last 5 years, education and training has formed one pillar for the creation of research reactor coalitions and networks to pool their resources and offer joint programmes, such as the on-going Group Fellowship Training Course. Conducted mainly through the Eastern European Research Reactor Initiative, this programme is a periodic sic week course for young scientists and engineers on nuclear techniques and administration jointly conducted at several member research reactor institutes. Organization of similar courses is under consideration in Latin America and the Asia-Pacific Region, also with support from the IAEA. Additionally, four research reactor institutes have begun offering practical education courses through virtual reactor experiments and operation known as the Internet Reactor Laboratory. Through little more than an internet connection and projection screens, university science departments can be connected regionally or bilaterally with the control room o a research reactor for various training activities. Finally, two publications are being prepared, namely Hands-On Training Courses Using Research Reactors and Accelerators, and Compendium on Education and training Based on Research Reactors. These

Enfermedad de Kawasaki en un infante Kawasaki disease in a child

Directory of Open Access Journals (Sweden)

José Luis Lobaina Lafita

2012-11-01

Full Text Available Se presenta el caso clínico de un infante de 4 años de edad, con antecedente de amigdalitis a repetición, ingresado en el Hospital Infantil Norte Docente "Dr. Juan de la Cruz Martínez Maceira" de Santiago de Cuba por presentar, desde hacía 9 días, fiebre de 38 y 39 °C, odinofagia, aumento de volumen del cuello y erupción cutánea generalizada. Teniendo en cuenta el examen físico y los resultados de los estudios complementarios efectuados se diagnosticó la enfermedad de Kawasaki, por lo cual se indicó tratamiento con Intacglobin®, Aspirina® y vitaminoterapia. El paciente evolucionó favorablemente y egresó de la institución hospitalaria sin complicaciones.The case of a 4 year-old child with history of recurrent tonsillitis, who was admitted to "Dr. Juan de la Cruz Martínez Maceira" Northern Teaching Children Hospital of Santiago de Cuba is reported for presenting with temperature of 38 and 39°C, odynophagia, enlargement of the neck and generalized rash in the past nine days. Based on physical examination and the results of complementary tests the Kawasaki disease was diagnosed, for which a treatment with Intacglobin®, Aspirin®, and vitamin therapy was indicated. The patient made good progress and was discharged from the hospital without complications.

Use of Corticosteroid in Children with Unresponsiveness to Intravenous Immunoglobulin in Kawasaki Disease

Directory of Open Access Journals (Sweden)

Abdolkarim Hamedi

2017-08-01

Full Text Available Background Kawasaki Disease (KD is a vasculitis with multi-organ involvementof unknown etiology; it is the most common cause of pediatric-heart diseases in developed countries. Treatment with Intravenous Immunoglobulin (IVIG prevents coronary artery lesions; although there are some IVIG-resistant cases, combination therapy with corticosteroids and IVIG is one of the recommendations for treatment of these cases. The aim of this study was to compare these three options for treatment of Kawasaki Disease and to evaluate their ability to deal with coronary artery complication of Kawasaki Disease. Materials and Methods A prospective cross- sectional study of hospitalized cases of Kawasaki Disease, conducted in pediatric department of Imam Reza hospital, Mashhad-Iran, during 2013 to 2015 (18 months. Based on demographic and clinical data of these patients, children with high risk of unresponsiveness to IVIG therapy (based on Harada score, were determined and treated with IVIG and corticosteroids- combination initially. Follow-up patients for heart complications were 6 weeks. Results Twenty five patients (89.2% out of total 28 hospitalized patients in this period of time who fulfilled diagnostic criteria were considered as complete Kawasaki Disease. Coronary Artery Lesions (CALs were shown in 4 patients during the follow-up period, with high risk in patients with incomplete presentation (33.3% versus 12%, P

Unexpected myocardial uptake on bone scintigraphy in an infant with Kawasaki disease

International Nuclear Information System (INIS)

Macdonald, W.B.G.; Troedson, R.G.

2003-01-01

Full text: A two-month-old female infant was admitted to hospital because of irritability and poor feeding over the preceding two weeks. There was no history of fever but serum inflammatory markers were elevated and a throat swab yielded a pure growth of Strep, pyogenes. There was no response to antibiotics. The nursing staff noted the infant disliked handling and skeletal pathology was suspected. A bone scan using Tc-99m hydroxymethylene diphosphonate (HDP) showed myocardial activity, with no evidence of abnormal skeletal activity. Subsequent echocardiography showed coronary artery ectasia, typical of Kawasaki disease, with papillary muscle dysfunction, indicating likely myocarditis. A diagnosis of myocarditis secondary to Kawasaki disease was made and the patient promptly improved following intravenous immunoglobulin therapy. Cardiac manifestations of Kawasaki disease included coronary artery aneurysms, myocardial infarction, regional perfusion abnormalities and myocarditis. Myocardial uptake of phosphate tracers is well known following myocardial infarction but there was no wall motion disturbance or ECG abnormality to suggest infarction in this patient and she was felt to have myocarditis. Myocardial uptake of phosphate tracers has not previously been reported in Kawasaki disease. Copyright (2003) The Australian and New Zealand Society of Nuclear Medicine Inc

RELAP/SCDAPSIM Reactor System Simulator Development and Training for University and Reactor Applications

International Nuclear Information System (INIS)

Hohorst, J.K.; Allison, C.M.

2010-01-01

The RELAP/SCDAPSIM code, designed to predict the behaviour of reactor systems during normal and accident conditions, is being developed as part of an international nuclear technology development program called SDTP (SCDAP Development and Training Program). SDTP involves more than 60 organizations in 28 countries. One of the important applications of the code is for simulator training of university faculty and students, reactor analysts, and reactor operations and technical support staff. Examples of RELAP/SCDAPSIM-based system thermal hydraulic and severe accident simulator packages include the SAFSIM simulator developed by NECSA for the SAFARI research reactor in South Africa, university-developed simulators at the University of Mexico and Shanghai Jiao Tong University in China, and commercial VISA and RELSIM packages used for analyst and reactor operations staff training. This paper will briefly describe the different packages/facilities. (authors)

RELAP/SCDAPSIM Reactor System Simulator Development and Training for University and Reactor Applications

Energy Technology Data Exchange (ETDEWEB)

Hohorst, J.K.; Allison, C.M. [Innovative Systems Software, 1242 South Woodruff Avenue, Idaho Falls, Idaho 83404 (United States)

2010-07-01

The RELAP/SCDAPSIM code, designed to predict the behaviour of reactor systems during normal and accident conditions, is being developed as part of an international nuclear technology development program called SDTP (SCDAP Development and Training Program). SDTP involves more than 60 organizations in 28 countries. One of the important applications of the code is for simulator training of university faculty and students, reactor analysts, and reactor operations and technical support staff. Examples of RELAP/SCDAPSIM-based system thermal hydraulic and severe accident simulator packages include the SAFSIM simulator developed by NECSA for the SAFARI research reactor in South Africa, university-developed simulators at the University of Mexico and Shanghai Jiao Tong University in China, and commercial VISA and RELSIM packages used for analyst and reactor operations staff training. This paper will briefly describe the different packages/facilities. (authors)

Technical highlights of the latest upgrades to Hitachi's G-HIACS νSAFE functional safety controller

International Nuclear Information System (INIS)

Tan, D.; Ishii, K.; Otsuka, Y.; Uemura, K.; Suenaga, M.; Koyamada, T.

2014-01-01

Hitachi has developed the G-HIACS νSAFE (pronounced 'nu-safe'), a Functional Safety (FS) controller compliant to IEC 61508 SIL 2, in part to satisfy the requirements of control systems for Nuclear Steam Plants (NSP). Hitachi has reported some of the main challenges, counter-measures and improvements encountered and designed during the several phases of development of controller system at previous Canadian Nuclear Society (CNS) Annual Conferences. Hitachi received initial Product Version 1 (PV1) certification from TUV Rheinland in 2010. Since then, additional functional and design improvements and changes have made product re-certification necessary, in order to cover the scope of the additional and improved capabilities. This paper describes some of these Product Version 2 (PV2) capabilities (certified by TUV Rheinland in 2013). (author)

76 FR 9612 - GE Hitachi Nuclear Energy; Acceptance for Docketing of an Application for Renewal of the U.S...

Science.gov (United States)

2011-02-18

... NUCLEAR REGULATORY COMMISSION [Docket No. 52-045; NRC-2011-0020] GE Hitachi Nuclear Energy... Certification On December 7, 2010, GE Hitachi Nuclear Energy (GEH) submitted an application to the U.S. Nuclear... and Approvals for Nuclear Power Plants.'' A notice of receipt and availability of this application was...

Training reactor deployment. Advanced experimental course on designing new reactor cores

International Nuclear Information System (INIS)

Skoda, Radek

2009-01-01

Czech Technical University in Prague (CTU) operating its training nuclear reactor VR1, in cooperation with the North West University of South Africa (NWU), is applying for accreditation of the experimental training course ''Advanced experimental course on designing the new reactor core'' that will guide the students, young nuclear engineering professionals, through designing, calculating, approval, and assembling a new nuclear reactor core. Students, young professionals from the South African nuclear industry, face the situation when a new nuclear reactor core is to be build from scratch. Several reactor core design options are pre-calculated. The selected design is re-calculated by the students, the result is then scrutinized by the regulator and, once all the analysis is approved, physical dismantling of the current core and assembling of the new core is done by the students, under a close supervision of the CTU staff. Finally the reactor is made critical with the new core. The presentation focuses on practical issues of such a course, desired reactor features and namely pedagogical and safety aspects. (orig.)

Extensive utilization of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, Karel; Sklenka, Lubomir

2003-01-01

Full text: The training reactor VR-1 Vrabec ('Sparrow'), operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly, it is designed and operated for training of students from Czech universities, preparing of experts for the Czech nuclear programme, as well as for certain research and development work, and for information programmes in the sphere of non-military nuclear energy use (public relation). The VR-1 training reactor is a pool-type light-water reactor based on enriched uranium with maximum thermal power 1kWth and short time period up to 5kW th . The moderator of neutrons is light demineralized water (H 2 O) that is also used as a reflector, a biological shielding, and a coolant. Heat is removed from the core with natural convection. The reactor core contains 14 to 18 fuel assemblies IRT-3M, depending on the geometric arrangement and kind of experiments to be performed in the reactor. The core is accommodated in a cylindrical stainless steel vessel - pool, which is filled with water. UR-70 control rods serve the reactor control and safe shutdown. Training of the VR-1 reactor provides students with experience in reactor and neutron physics, dosimetry, nuclear safety, and nuclear installation operation. Students from technical universities and from natural sciences universities come to the reactor for training. Approximately 200 university students are introduced to the reactor (lectures, experiments, experimental and diploma works, etc.) every year. About 12 different faculties from Czech universities use the reactor. International co-operation with European universities in Germany, Hungary, Austria, Slovakia, Holland and UK is frequent. Practical Course on Reactor Physics in Framework of European Nuclear Engineering Network has been newly introduced. Currently, students can try out more than 20 experimental exercises. Further training courses have been included

Natriuretic Peptides in Kawasaki Disease: the Myocardial Perspective

Directory of Open Access Journals (Sweden)

Nagib Dahdah

2013-01-01

Full Text Available Making a diagnosis of Kawasaki disease with certainty may be challenging, especially since the recognition of cases with incomplete diagnostic criteria and its consequences. In order to build the diagnostic case in daily practice, clinicians rely on clinical criteria established over four decades ago, aided by non specific laboratory tests, and above all inspired by experience. We have recently studied the diagnostic value of N-terminal pro B-type natriuretic peptide to improve the diagnostic certainty of cases with complete or incomplete clinical criteria. Our working hypothesis was based on the fact that myocarditis is present in nearly all Kawasaki disease patients supported by histology data. In this paper, we review these facts and the myocardial perspective from the diagnostic and the mechanistic standpoints.

U.S. NRC training for research and training reactor inspectors

International Nuclear Information System (INIS)

Sandquist, G.M.; Kunze, J.F.

2011-01-01

Currently, a large number of license activities (Early Site Permits, Combined Operating License, reactor certifications, etc.), are pending for review before the United States Nuclear Regulatory Commission (US NRC). Much of the senior staff at the NRC is now committed to these review and licensing actions. To address this additional workload, the NRC has recruited a large number of new Regulatory Staff for dealing with these and other regulatory actions such as the US Fleet of Research and Test Reactors (RTRs). These reactors pose unusual demands on Regulatory Staff since the US Fleet of RTRs, although few (32 Licensed RTRs as of 2010), they represent a broad range of reactor types, operations, and research and training aspects that nuclear reactor power plants (such as the 104 LWRs) do not pose. The US NRC must inspect and regulate all these entities. This paper addresses selected training topics and regulatory activities provided US NRC Inspectors for US RTRs. (author)

Development of Safety Review Guidance for Research and Training Reactors

International Nuclear Information System (INIS)

Oh, Kju-Myeng; Shin, Dae-Soo; Ahn, Sang-Kyu; Lee, Hoon-Joo

2007-01-01

The KINS already issued the safety review guidance for pressurized LWRs. But the safety review guidance for research and training reactors were not developed. So, the technical standard including safety review guidance for domestic research and training reactors has been applied mutates mutandis to those of nuclear power plants. It is often difficult for the staff to effectively perform the safety review of applications for the permit by the licensee, based on peculiar safety review guidance. The NRC and NSC provide the safety review guidance for test and research reactors and European countries refer to IAEA safety requirements and guides. The safety review guide (SRG) of research and training reactors was developed considering descriptions of the NUREG- 1537 Part 2, previous experiences of safety review and domestic regulations for related facilities. This study provided the safety review guidance for research and training reactors and surveyed the difference of major acceptance criteria or characteristics between the SRG of pressurized light water reactor and research and training reactors

Extensive utilization of training reactor VR-1

International Nuclear Information System (INIS)

Karel, Matejka; Lubomir, Sklenka

2005-01-01

This paper describes one of the main purposes of the VR-1 training reactor utilisation - i.e. extensive educational programme. The educational programme is intended for the training of university students (all technical universities in Czech Republic) and selected nuclear power plant personnel. At the present, students can go through more than 20 different experimental exercises. An attractive programme including demonstration of reactor operation is prepared also for high school students. Moreover, research and development works and information programmes proceed at the VR-1 reactor as well

Use of the VR-1 ''Vrabec'' training reactor

International Nuclear Information System (INIS)

Matejka, K.; Kolros, A.; Krops, S.; Polach, S.; Sklenka, L.

1994-01-01

An overview is presented of the extent and ways of using the VR-1 training reactor, which is operated by the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague. A list and the characteristics of 16 problems developed for teaching purposes is given, and the 14 faculties and 2 research institutes participating in the teaching activities are listed. The reactor is used in the education and training of nuclear scientists and engineers. The instrumentation, experimental, handling and operating tools, as well as documentation and texts relating to the reactor are described. The following examples of the teaching activities are included: a guided visit to the operating reactor site, reactor dynamics study and delayed neutron measurement, training course, and the basic criticality experiment. Nuclear safety aspects (hypothetical accidents, quality control and system qualification demonstration, safety culture) are stressed during the education. The reactor department is involved in international cooperation projects. (J.B.). 3 refs

Advanced Reactor PSA Methodologies for System Reliability Analysis and Source Term Assessment

Energy Technology Data Exchange (ETDEWEB)

Grabaskas, D.; Brunett, A.; Passerini, S.; Grelle, A.; Bucknor, M.

2017-06-26

Beginning in 2015, a project was initiated to update and modernize the probabilistic safety assessment (PSA) of the GE-Hitachi PRISM sodium fast reactor. This project is a collaboration between GE-Hitachi and Argonne National Laboratory (Argonne), and funded in part by the U.S. Department of Energy. Specifically, the role of Argonne is to assess the reliability of passive safety systems, complete a mechanistic source term calculation, and provide component reliability estimates. The assessment of passive system reliability focused on the performance of the Reactor Vessel Auxiliary Cooling System (RVACS) and the inherent reactivity feedback mechanisms of the metal fuel core. The mechanistic source term assessment attempted to provide a sequence specific source term evaluation to quantify offsite consequences. Lastly, the reliability assessment focused on components specific to the sodium fast reactor, including electromagnetic pumps, intermediate heat exchangers, the steam generator, and sodium valves and piping.

Radiation-hygienic estimation of training reactors location

International Nuclear Information System (INIS)

Konstantinov, Yu.O.; Fedorin, Eh.V.

1978-01-01

The radiation exposure conditions are provided during the normal operation (excluding emergency situations) of four training pool type reactors. Radiation monitoring of the environment near the reactors do not show any increase in external irradiation or in radioactive contamination over what is considered normal radiation background in the locality. Therefore it is possible to judge the potential levels of additional exposure of the population to radiation from the reactors only by means of theoretic modeling of the radiation conditions. Tabular data on maximal levels of this additional radiation are presented, and it is concluded from these data that it is permissible to install training and research reactors up to 3000 kilowatts within large cities, including dwelling areas

Genome-wide association study identifies FCGR2A as a susceptibility locus for Kawasaki disease

NARCIS (Netherlands)

Khor, Chiea Chuen; Davila, Sonia; Breunis, Willemijn B.; Lee, Yi-Ching; Shimizu, Chisato; Wright, Victoria J.; Yeung, Rae S. M.; Tan, Dennis E. K.; Sim, Kar Seng; Wang, Jie Jin; Wong, Tien Yin; Pang, Junxiong; Mitchell, Paul; Cimaz, Rolando; Dahdah, Nagib; Cheung, Yiu-Fai; Huang, Guo-Ying; Yang, Wanling; Park, In-Sook; Lee, Jong-Keuk; Wu, Jer-Yuarn; Levin, Michael; Burns, Jane C.; Burgner, David; Kuijpers, Taco W.; Hibberd, Martin L.; Lau, Yu-Lung; Zhang, Jing; Ma, Xiao-Jing; Liu, Fang; Wu, Lin; Yoo, Jeong-Jin; Hong, Soo-Jong; Kim, Kwi-Joo; Kim, Jae-Jung; Park, Young-Mi; Mi Hong, Young; Sohn, Sejung; Young Jang, Gi; Ha, Kee-Soo; Nam, Hyo-Kyoung; Byeon, Jung-Hye; Weon Yun, Sin; Ki Han, Myung; Lee, Kyung-Yil; Hwang, Ja-Young; Kuipers, Irene M.; Ottenkamp, Jaap J.; Biezeveld, Maarten; Tacke, Carline

2011-01-01

Kawasaki disease is a systemic vasculitis of unknown etiology, with clinical observations suggesting a substantial genetic contribution to disease susceptibility. We conducted a genome-wide association study and replication analysis in 2,173 individuals with Kawasaki disease and 9,383 controls from

Nuclear Power Reactor simulator - based training program

International Nuclear Information System (INIS)

Abdelwahab, S.A.S.

2009-01-01

nuclear power stations will continue playing a major role as an energy source for electric generation and heat production in the world. in this paper, a nuclear power reactor simulator- based training program will be presented . this program is designed to aid in training of the reactor operators about the principles of operation of the plant. also it could help the researchers and the designers to analyze and to estimate the performance of the nuclear reactors and facilitate further studies for selection of the proper controller and its optimization process as it is difficult and time consuming to do all experiments in the real nuclear environment.this program is written in MATLAB code as MATLAB software provides sophisticated tools comparable to those in other software such as visual basic for the creation of graphical user interface (GUI). moreover MATLAB is available for all major operating systems. the used SIMULINK reactor model for the nuclear reactor can be used to model different types by adopting appropriate parameters. the model of each component of the reactor is based on physical laws rather than the use of look up tables or curve fitting.this simulation based training program will improve acquisition and retention knowledge also trainee will learn faster and will have better attitude

Jordan Research and Training Reactor (JRTR) Utilization Facilities

International Nuclear Information System (INIS)

Xoubi, N.

2013-01-01

Jordan Research and Training Reactor (JRTR) is a 5 MW light water open pool multipurpose reactor that serves as the focal point for Jordan National Nuclear Centre, and is designed to be utilized in three main areas: Education and training, nuclear research, and radioisotopes production and other commercial and industrial services. The reactor core is composed of 18 fuel assemblies, MTR plate type 19.75% enriched uranium silicide (U 3 Si 2 ) in aluminium matrix, and is reflected on all sides by beryllium and graphite. The reactor power is upgradable to 10 MW with a maximum thermal flux of 1.45×10 14 cm -2 s -1 , and is controlled by a Hafnium control absorber rod and B 4 C shutdown rod. The reactor is designed to include laboratories and classrooms that will support the establishment of a nuclear reactor school for educating and training students in disciplines like nuclear engineering, reactor physics, radiochemistry, nuclear technology, radiation protection, and other related scientific fields where classroom instruction and laboratory experiments will be related in a very practical and realistic manner to the actual operation of the reactor. JRTR is designed to support advanced nuclear research as well as commercial and industrial services, which can be preformed utilizing any of its 35 experimental facilities. (author)

The training and research reactor of the Zittau Technical College

International Nuclear Information System (INIS)

Ackermann, G.; Hampel, R.; Konschak, K.

1979-01-01

The light-water moderated training and research reactor of the Zittau Technical College, which has been put into operation 1 July 1979, is described. Having a power of 10 MW, it is provided for education of students and advanced training of nuclear power plant staff members. High inherent nuclear safety and economy of operation are achieved by appropriate design of the reactor core and the use of fresh fuel elements provided for the 10-MW research reactor at the Rossendorf Central Institute for Nucleear Research for one year on a loan basis. Further characteristics of the reactor are easy accessibility of the core interior for in-core studies, sufficient external experimental channels, and a control and protection system meeting the requirements of teaching operation. The installed technological and dosimetric devices not only ensure reliable operation of the reactor, but also extend the potentialities of experimental work and education that is reported in detail. The principles on which the training programs are based are explained in the light of some examples. The training reactor is assumed to serve for providing basic knowledge about processes in nuclear power stations with pressurized water reactors. Where the behaviour of a nuclear power station cannot sufficiently be demonstrated by the training reactor, a reasonable completion of practical training at special simulation models and experimental facilities of the Technical College and at the nuclear power plant simulator of the Rheinsberg nuclear power plant school has been conceived. (author)

Training and research reactor facility longevity extension program

International Nuclear Information System (INIS)

Carriveau, G.W.

1991-01-01

Since 1943, over 550 training and research reactors have been in operation. According to statistics from the International Atomic Energy Agency, ∼325 training and research reactors are currently in service. This total includes a wide variety of designs covering a range of power and research capabilities located virtually around the world. A program has been established at General Atomics (GA) that is dedicated to the support of extended longevity of training and research reactor facilities. Aspects of this program include the following: (1) new instrumentation and control systems; (2) improved and upgraded nuclear monitoring and control channels; (3) facility testing, repair and upgrade services that include (a) pool or tank integrity, (b) cooling system, and (c) water purification system; (4) fuel element testing procedures and replacement; (5) control rod drive rebuilding and upgrades; (6) control and monitoring system calibration and repair service; (7) training services, including reactor operations, maintenance, instrumentation calibration, and repair; and (8) expanded or new uses such as neutron radiography and autoradiography, isotope production, nuclear medicine, activation analysis, and material properties modification

Extensive utilisation of VR-1 reactor for nuclear education and training

International Nuclear Information System (INIS)

Rataj, J.

2010-01-01

The paper presents utilisation of the VR-1 reactor for nuclear education and training at national and international level. VR-1 reactor has been operating by the Czech Technical University since December 1990. The reactor is a pool-type light water reactor based on enriched uranium (19.7% 235 U) with maximum thermal power 1kW and for short time period up to 5kW. The moderator of neutrons is light water, which is also used as a reflector, a biological shielding and a coolant. Heat is removed from the core by natural convection. The pool disposition of the reactor facilitates access to the core, setting and removing of various experimental samples and detectors, easy and safe handling of fuel assemblies. The reactor core can contain from 17 to 21 fuel assemblies IRT-4M, depending on the geometric arrangement and kind of experiments to be performed in the reactor. The reactor is equipped with several experimental devices; e.g. horizontal, radial and tangential channels used to take out a neutron beam, reactivity oscillator for dynamics study and bubble boiling simulator. The reactor has been used very efficiently especially for education and training of university students and NPP's specialists for more than 18 years. The VR-1 reactor is utilised within various national and international activities such as Czech Nuclear Education Network (CENEN), European Nuclear Education Network and also Eastern European Research Reactor Initiative (EERRI). The reactor is well equipped for education and training not only by the experimental facility itself but also by incessant development of training methods and improvement of education experiments. The education experiments can be combined into training courses attended by students according to their study specialization and knowledge level. The training programme is aimed to the reactor and neutron physics, dosimetry, nuclear safety, and control of nuclear installations. Every year, approximately 250 university students undergo

Training and research on the nuclear reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.

1998-01-01

The VR-1 training reactor is a light water reactor of the pool type using enriched uranium as the fuel. The moderator is demineralized light water, which also serves as the neutron reflector, biological shielding, and coolant. Heat evolved during the fission process is removed by natural convection. The reactor is used in the education of students in the field of reactor and neutron physics, dosimetry, nuclear safety, and instrumentation and control systems for nuclear facilities. Although primarily intended for students in various branches of technology (power engineering, nuclear engineering, physical engineering), this specialized facility is also used by students of faculties educating future natural scientists and teachers. Typical tasks trained at the VR-1 reactor include: measurement of delayed neutrons; examination of the effect of various materials on the reactivity of the reactor; measurement of the neutron flux density by various procedures; measurement of reactivity by various procedures; calibration of reactor control rods by various procedures; approaching the critical state; investigation of nuclear reactor dynamics; start-up, control and operation of a nuclear reactor; and investigation of the effect of a simulated nucleate boil on reactivity. In addition to the education of university-level students, training courses are also organized for specialists in the Czech nuclear programme

Coronary artery calcification in Kawasaki disease

International Nuclear Information System (INIS)

Ino, T.; Shimazaki, S.; Akimoto, K.; Park, I.; Nishimoto, K.; Yabuta, K.; Tanaka, A.

1990-01-01

To evaluate the angiographic features of coronary lesions in Kawasaki disease with coronary artery calcification, cinefluoroscopy and cineangiography were retrospectively reviewed in 116 patients who had undergone coronary angiography between 1982 and 1989. Angiographic abnormalities of coronary arteries were demonstrated in 55 of 116 patients. In 5 (9.1%) of the 55 patients, 9 with calcification were identified by cinefluoroscopy and chest X-ray. Eight of the 9 calcified lesions showed a circular or ring-shape configuration. Coronary angiography revealed a total occlusion of the right coronary artery with collateral circulation from the distal left coronary artery in 2 patients and a severe stenosis of the right coronary artery in 2 patients, in whom anticoagulant therapy had not been continued during the follow-up periods. The remaining patient in whom anticoagulant therapy had been continued had bilateral aneurysms but no significant stenosis. These results indicate that a ring-shape calcification on chest X-ray in 2 patients with a history of Kawasaki disease may suggest an involvement by coronary artery stenosis even when anticoagulant drugs had been given. Therefore, coronary angiography should be performed to evaluate the stenotic lesions if this type of calcification is found by routine radiographic examination. (orig.)

Influence of photoisomers in bilirubin determinations on Kodak Ektachem and Hitachi analysers in neonatal specimens study of the contribution of structural and configurational isomers.

Science.gov (United States)

Gulian, J M; Dalmasso, C; Millet, V; Unal, D; Charrel, M

1995-08-01

We compared data obtained with the Kodak Ektachem and Hitachi 717 Analysers and HPLC from 83 neonates under phototherapy. Total bilirubin values determined with the Kodak and Hitachi are in good agreement, but we observed a large discrepancy in the results for conjugated (Kodak) and direct (Hitachi) bilirubin. HPLC revealed that all the samples contained configurational isomers, while only 7.7% and 30.8% contained conjugated bilirubin and structural isomers, respectively. We developed a device for the specific and quantitative production of configurational or structural isomers, by irradiation with blue or green light. In vitro, total bilirubin values are coherent for the routine analysers in the presence of configurational or structural isomers. With configurational isomers, unconjugated bilirubin (Kodak) is lower than total bilirubin (Kodak), and conjugated bilirubin (Kodak) is always equal to zero, so the apparatus gives a false positive response for delta bilirubin. In contrast, the direct bilirubin (Hitachi) is constant. Furthermore, in the presence of structural isomers, unconjugated bilirubin (Kodak) is unexpectedly higher than total bilirubin (Kodak), conjugated bilirubin (Kodak) is proportional to the quantity of these isomers, and direct bilirubin (Hitachi) is constant. The contribution of photoisomers in bilirubin measurements is discussed.

Artificial Intelligence/Robotics Applications to Navy Aircraft Maintenance.

Science.gov (United States)

1984-06-01

Northrup, Martin-Marietta, Rand, Perceptronics, PAR, Unilever , and » Philips. Japanese companies include Hitachi, Kawasaki, Fujitsu, NTT, NEC...in which computer systems have been configured. Another commercial development has also attracted attention. The General Electric Company is...increases the contrast to make dark objects in the scene stand out against a light background (or vice versa). Finally, it applies various simple and

Education and training by utilizing irradiation test reactor simulator

International Nuclear Information System (INIS)

Eguchi, Shohei; Koike, Sumio; Takemoto, Noriyuki; Tanimoto, Masataka; Kusunoki, Tsuyoshi

2016-01-01

The Japan Atomic Energy Agency, at its Japan Materials Testing Reactor (JMTR), completed an irradiation test reactor simulator in May 2012. This simulator simulates the operation, irradiation test, abnormal transient change during operation, and accident progress events, etc., and is able to perform operation training on reactor and irradiation equipment corresponding to the above simulations. This simulator is composed of a reactor control panel, process control panel, irradiation equipment control panel, instructor control panel, large display panel, and compute server. The completed simulator has been utilized in the education and training of JMTR operators for the purpose of the safe and stable operation of JMTR and the achievement of high operation rate after resuming operation. For the education and training, an education and training curriculum has been prepared for use in not only operation procedures at the time of normal operation, but also learning of fast and accurate response in case of accident events. In addition, this simulator is also being used in operation training for the purpose of contributing to the cultivation of human resources for atomic power in and out of Japan. (A.O.)

Comparison of avian biochemical test results with Abaxis VetScan and Hitachi 911 analyzers.

Science.gov (United States)

Greenacre, Cheryl B; Flatland, Bente; Souza, Marcy J; Fry, Michael M

2008-12-01

To compare results of clinical biochemical analysis using an Abaxis VetScan bench-top analyzer with reagents specifically marketed for avian use and a Hitachi 911 analyzer, plasma (both methods) and whole blood (VetScan method) samples from 20 clinically healthy Hispaniolan Amazon parrots (Amazona ventralis) were analyzed. Correlation between methods was very high (r = 0.9-1.0) for aspartate aminotransferase (AST), calcium, glucose, and uric acid; high (r = 0.7-0.89) for creatine kinase (CK), phosphorus, potassium, and total protein; moderate (r = 0.5-0.69) for globulin; and low (r = 0.3-0.49) for albumin and sodium. VetScan analyzer results for globulin, sodium, and uric acid had a constant negative bias (values below those from the Hitachi method). Based on difference plot analysis, results for AST, calcium, CK, and glucose are comparable. Because 16 of 20 values fell below the lower detection limit of the VetScan analyzer, bile acid data were excluded from analysis. By using a relatively small sample size (0.1 ml whole blood or plasma), the VetScan analyzer offers rapid in-house results, compact size, and ease of operation. For 4 of the most clinically relevant biochemical analytes used in avian medicine (AST, calcium, CK, glucose), it offers reliable values. For an additional 4 analytes (phosphorous, potassium, total protein, uric acid), establishing analyzer-specific reference intervals is recommended. Neither the VetScan nor the Hitachi method is recommended to assess albumin and globulin concentrations.

New human machine interface for VR-1 training reactor

International Nuclear Information System (INIS)

Kropik, M.; Matejka, K.; Sklenka, L.; Chab, V.

2002-01-01

The contribution describes a new human machine interface that was installed at the VR-1 training reactor. The human machine interface update was completed in the summer 2001. The human machine interface enables to operate the training reactor. The interface was designed with respect to functional, ergonomic and aesthetic requirements. The interface is based on a personal computer equipped with two displays. One display enables alphanumeric communication between a reactor operator and the control and safety system of the nuclear reactor. Messages appear from the control system, the operator can write commands and send them there. The second display is a graphical one. It is possible to represent there the status of the reactor, principle parameters (as power, period), control rods' positions, the course of the reactor power. Furthermore, it is possible to set parameters, to show the active core configuration, to perform reactivity calculations, etc. The software for the new human machine interface was produced in the InTouch developing environment of the WonderWare Company. It is possible to switch the language of the interface between Czech and English because of many foreign students and visitors at the reactor. The former operator's desk was completely removed and superseded with a new one. Besides of the computer and the two displays, there are control buttons, indicators and individual numerical displays of instrumentation there. Utilised components guarantee high quality of the new equipment. Microcomputer based communication units with proper software were developed to connect the contemporary control and safety system with the personal computer of the human machine interface and the individual displays. New human machine interface at the VR-1 training reactor improves the safety and comfort of the reactor utilisation, facilitates experiments and training, and provides better support of foreign visitors.(author)

Use of the Oregon State University TRIGA reactor for education and training

International Nuclear Information System (INIS)

Dodd, B.

1989-01-01

This paper summarizes the recent use of the Oregon State University TRIGA Reactor (OSTR) for education and training. In particular, data covering the last 5 yr are presented, which cover education through formal university classes, theses, public information, and school programs. Training is covered by presenting data on domestic and foreign reactor operator training, health physics training, and neutron activation analysis training. While education and training only occupy ∼16% of the OSTR's total use time, nevertheless, this is an important mission of all nonpower reactors that cannot be performed effectively in any other way

CLINICAL MANIFESTATION, DIAGNOSTICS AND TREATMENT OF KAWASAKI DISEASE: KNOWN DATA AND UNSOLVED QUESTIONS

Directory of Open Access Journals (Sweden)

G. А. Lyskina

2013-01-01

Full Text Available The lecture deals with the most common systemic vasculitis in pediatric practice — Kawasaki disease. This disorder is associated with risk of myocardial infarction and sudden cardiac death in children and young adults and at present is considered to be the main cause of the acquired heard diseases in children. The authors give historical aspects and modern opinions on etiology, pathogenesis, clinical manifestation, diagnostics and treatment of Kawasaki disease. The data were summarized from Russian and foreign literature as well as from the own authors’ experience.

Radiation protection personnel training in Research Reactors

International Nuclear Information System (INIS)

Fernandez, Carlos Dario; Lorenzo, Nestor Pedro de

1996-01-01

The RA-6 research reactor is considering the main laboratory in the training of different groups related with radiological protection. The methodology applied to several courses over 15 years of experience is shown in this work. The reactor is also involved in the construction, design, start-up and sell of different installation outside Argentina for this reason several theoretical and practical courses had been developed. The acquired experience obtained is shown in this paper and the main purpose is to show the requirements to be taken into account for every group (subjects, goals, on-job training, etc) (author)

Maximizing the use of research reactors in training power reactor operating staff with special reference to US experience

International Nuclear Information System (INIS)

Cox, J.A.

1976-01-01

Research reactors have been used in training nuclear power plant personnel for many years. Using the experience in the United States of America a programme is proposed that will maximize the training conducted at a research reactor and lessen the time that the staff must spend training elsewhere. The programme is adaptable to future training of replacement staff and for staff retraining. (author)

VR-1 training reactor in use for twelve years to train experts for the Czech nuclear power sector

International Nuclear Information System (INIS)

Matejka, K.; Sklenka, L.

2003-01-01

The VR-1 training reactor has been serving students of the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague, for more than 12 years now. The operation history of the reactor is highlighted. The major changes made at the VR-1 reactor are outlined and the main experimentally verified core configurations are shown. Some components of the new equipment installed on the VR-1 reactor are described in detail. The fields of application are shown: the reactor serves not only the training of university students within whole Czech Republic but also the training of specialists, research activities, and information programmes in the nuclear power domain. (P.A.)

Education and research at the VR-1 Vrabec training reactor facility

International Nuclear Information System (INIS)

Matejka, K.

1993-01-01

The results of 12 years' efforts devoted to the construction of the VR-1 ''Vrabec'' training reactor at the Faculty of Nuclear Science and Physical Engineering, Czech Technical University in Prague and to establishing the training reactor department, as well as the contribution of the training reactor facility to the teaching and scientific activities of the Faculty are presented in a comprehensive manner. The thesis is divided into 2 parts: (i) preconditions, reactor construction and commissioning, and constituting the reactor department, and (ii) basic and comprehensive information concerning the current utilization of the reactor for the benefit of students from various university level institutions. The prospects of scientific activities of the department are also outlined. Attention is paid to selected nuclear safety aspects of the reactor during operation and teaching of students, as well as to its innovated digital control system whose implementation is planned. The results achieved are compared with the initial goals and with similar experience abroad. (P.A.)

Nuclear renaissance in the reactor training of Areva

International Nuclear Information System (INIS)

De Braquilanges, Bertrand; Napior, Amy; Schoenfelder, Christian

2010-01-01

Because of the perspectives of new builds, a significant increase in the number of design, construction and management personnel working in AREVA, their clients and sub-contractors has been estimated for the next future. In order to cope with the challenge to integrate newly hired people quickly and effectively into the AREVA workforce, a project - 'Training Task Force (TTF)' - was launched in 2008. The objective was to develop introductory and advanced courses and related tools harmonized between AREVA Training Centers in France, Germany and USA. First, a Global Plants Introductory Session (GPIS) was developed for newly hired employees. GPIS is a two weeks training course introducing in a modular way AREVA and specifically the activities and the reactors technical basics. As an example, design and operation of a nuclear power plant is illustrated on EPRTM. Since January 2009, these GPIS are held regularly in France, Germany and the US with a mixing of employees from these 3 regions. Next, advanced courses for more experienced employees were developed: - Advanced EPR TM , giving a detailed presentation of the EPR TM reactor design; - Codes and Standards; - Technical Nuclear Safety. Finally, feasibility studies on a Training Material Management (TMM) system, able to manage the training documentation, and on a worldwide training administration tool, were performed. The TTF project was completed mid of 2009; it transferred their recurrent activities to a new AREVA training department. This unit now consists of the French, German and US Reactors Training Centers. In particular, all courses developed by the TTF are now implemented worldwide with an opening to external trainees. The current worldwide course catalogue includes training courses for operation and maintenance personnel as well as for managers, engineers and non technical personnel of nuclear operators, suppliers, safety authorities and expert organizations. Training delivery is supported effectively by tools

The Utilization of Dalat nuclear research reactor for education and training purposes

International Nuclear Information System (INIS)

Luong, Ba Vien; Nguyen, Nhi Dien; Le, Vinh Vinh; Nguyen, Xuan Hai

2017-01-01

The Dalat Nuclear Research Reactor (DNRR) with the nominal power of 500 kWt is today the unique one in Vietnam. It was designed for the purposes of radioisotope production, neutron activation analysis, basic and applied researches, and nuclear education and training. With the rising demand in development of human resources for utilization of atomic energy in the country, the DNRR has been playing an important role in the nuclear education and training for students from universities and professionals who are interested in reactor engineering. At present, the Dalat Nuclear Research Institute (DNRI) offers two types of training course utilizing the research reactor: an one-week practical training course is applied for undergraduate students and a two-week training course on reactor engineering is applied for the professionals. This paper presents the reactor facility and experiments performed at the DNRR for education and training purposes. In addition, the co-operation between the DNRI with national and international educational organizations for nuclear human resource development for national and regional demands is also mentioned in the paper. (author)

A small-scale experimental reactor combined with a simulator for training purposes

International Nuclear Information System (INIS)

Destot, M.; Hagendorf, M.; Vanhumbeeck, D.; Lecocq-Bernard, J.

1981-01-01

The authors discuss how a small-scale reactor combined to a training simulator can be a valuable aid in all forms of training. They describe the CEN-based SILOETTE reactor in Grenoble and its combined simulator. They also take a look at prospects for the future of the system in the light of experience acquired with the ARIANE reactor and the trends for the development of simulators for training purposes [fr

Lifting of a sector block for YE-2 at Kawasaki.

CERN Multimedia

R. Loveless/U. of Wisconsin

2000-01-01

YE-2 is build from machined sector blocks. Trial assembly is carried out horizontally. This picture represents the lifting of a machined sector block destined to the trial assembly of a half disk YE-2 at Kawasaki (KHI) Kobe, Japan.

Use of research reactors for training and teaching nuclear sciences

International Nuclear Information System (INIS)

Safieh, J.; Gless, B.

2002-01-01

Training activities on reactors are organized by Cea on 2 specially dedicated reactors Ulysse (Saclay) and Siloette (Grenoble) and 2 research reactors Minerve (Cadarache) and Azur (Cadarache, facility managed by Technicatome). About 4000 students have been trained on Ulysse since its commissioning more than 40 years ago. The concept that led to the design of Ulysse was to build a true reactor dedicated to teaching and training activities and that was able to operate with great flexibility and under high conditions of safety, this reactor is inspired from the Argonaut-type reactor. The main specificities of Ulysse are: a nominal power of 100 kW, a maximal thermal neutron flux of 1.4 10 12 n.cm -2 .s -1 , a 90 % enriched fuel, a graphite reflector, the use of water as coolant and moderator, and 6 cadmium plates as control rods. Ulysse allows students to get practical experience on a large range of topics: approach to criticality, effect of the starting neutron source, calibration of control rods, distribution of the neutron flux in the thermal column, temperature coefficient, radiation detectors, neutron activation analysis, and radioprotection. (A.C.)

Use of multiple on-campus reactors in education and training programs

International Nuclear Information System (INIS)

Schlapper, G.A.

1989-01-01

In its undergraduate and graduate programs in nuclear engineering and health physics, Texas A ampersand M University utilizes two reactors for the training and education of students. The 5-W AGN-201 nuclear training reactor has been in use since the late 1950s, while the 1-MW TRIGA Nuclear Science Center Reactor (NSCR) was first utilized in late 1961. Both facilities have been upgraded since initial criticality, the AGN power level being increased from the original 200-mW limit to its 5-W current level and the NSCR undergoing conversion from a 100-kW materials test reactor fueled deign to a 1-MW TRIGA-fueled facility. The AGN reactor is operated by the Department of Nuclear Engineering of the College of Engineering and is almost solely utilized in training and education programs. The NSCR facility is administered by the Texas Engineering Experiment Station and support research efforts of faculty and students of departments within and outside the university in addition to contributing to the education and training programs of the nuclear engineering department

77 FR 14838 - General Electric-Hitachi Global Laser Enrichment LLC, Commercial Laser-Based Uranium Enrichment...

Science.gov (United States)

2012-03-13

... Laser Enrichment LLC, Commercial Laser-Based Uranium Enrichment Facility, Wilmington, North Carolina... a license to General Electric-Hitachi Global Laser Enrichment LLC (GLE or the applicant) to authorize construction of a laser-based uranium enrichment facility and possession and use of byproduct...

Kawasaki dynamics with two types of particles : critical droplets

NARCIS (Netherlands)

Hollander, den W.Th.F.; Nardi, F.R.; Troiani, A.

2012-01-01

This is the third in a series of three papers in which we study a two-dimensional lattice gas consisting of two types of particles subject to Kawasaki dynamics at low temperature in a large finite box with an open boundary. Each pair of particles occupying neighboring sites has a negative binding

Kawasaki dynamics with two types of particles : critical droplets

NARCIS (Netherlands)

Hollander, den W.Th.F.; Nardi, F.R.; Troiani, A.

2012-01-01

This is the third in a series of three papers in which we study a two-dimensional lattice gas consisting of two types of particles subject to Kawasaki dynamics at low temperature in a large ¿nite box with an open boundary. Each pair of particles occupying neighboring sites has a negative binding

Nuclear renaissance in the reactor training of Areva

Energy Technology Data Exchange (ETDEWEB)

De Braquilanges, Bertrand [Reactor Training Center/France Manager, La Tour Areva - 1, place Jean Millier - 92084 Paris - La Defense (France); Napior, Amy [Reactor Training Center/USA Manager, 1300 Old Graves Mill Road - Lynchburg VA, 2450 (United States); Schoenfelder, Christian [Reactor Training Center/Germany Manager, Kaiserleistrasse 29 - 63067 Offenbach (Germany)

2010-07-01

Because of the perspectives of new builds, a significant increase in the number of design, construction and management personnel working in AREVA, their clients and sub-contractors has been estimated for the next future. In order to cope with the challenge to integrate newly hired people quickly and effectively into the AREVA workforce, a project - 'Training Task Force (TTF)' - was launched in 2008. The objective was to develop introductory and advanced courses and related tools harmonized between AREVA Training Centers in France, Germany and USA. First, a Global Plants Introductory Session (GPIS) was developed for newly hired employees. GPIS is a two weeks training course introducing in a modular way AREVA and specifically the activities and the reactors technical basics. As an example, design and operation of a nuclear power plant is illustrated on EPRTM. Since January 2009, these GPIS are held regularly in France, Germany and the US with a mixing of employees from these 3 regions. Next, advanced courses for more experienced employees were developed: - Advanced EPR{sup TM}, giving a detailed presentation of the EPR{sup TM} reactor design; - Codes and Standards; - Technical Nuclear Safety. Finally, feasibility studies on a Training Material Management (TMM) system, able to manage the training documentation, and on a worldwide training administration tool, were performed. The TTF project was completed mid of 2009; it transferred their recurrent activities to a new AREVA training department. This unit now consists of the French, German and US Reactors Training Centers. In particular, all courses developed by the TTF are now implemented worldwide with an opening to external trainees. The current worldwide course catalogue includes training courses for operation and maintenance personnel as well as for managers, engineers and non technical personnel of nuclear operators, suppliers, safety authorities and expert organizations. Training delivery is supported

Multiple giant succular and fusiform right and left coronary artery aneurysms after early and adequate treatment of atypical kawasaki disease with unusual presentation.

Directory of Open Access Journals (Sweden)

Mostafa Behjati-Ardakani

2014-06-01

Full Text Available The major complication of Kawasaki disease is coronary artery dilatation and aneurysm. It occurs in approximately 15-25% of untreated children with Kawasaki Disease. Early diagnosis and treatment with Intravenous immune globulin (IVIG and aspirin (ASA can reduce the incidence of coronary artery abnormality to 2%-5%. We report one case of Atypical Kawasaki Disease with Multiple giant coronary artery aneurysms despite early adequate treatment with IVIG and ASA.

WWER-1000 reactor simulator. Material for training courses and workshops. 2. ed

International Nuclear Information System (INIS)

2005-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series No.12, Reactor Simulator Development (2001). Course material for workshops using a pressurized water reactor (PWR) simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada is presented in the IAEA publication, Training Course Series No. 22, 2nd edition, Pressurized Water Reactor Simulator (2005) and Training Course Series No.23, 2nd edition, Boiling Water Reactor Simulator (2005). This report consists of course material for workshops using the WWER-1000 Reactor Department Simulator from the Moscow Engineering and Physics Institute, Russian Federation

IAEA-RCA training course on in-service inspection of research reactors

International Nuclear Information System (INIS)

2002-01-01

Bhabha Atomic Research Centre (BARC) has acquired a wide range of experience for over four decades in design, construction, operation and maintenance of research reactors. The two-week training course on In-Service Inspection of Research Reactors (ISI) has greatly increased the awareness in the field of ISI of Research Reactors. The training course has been formulated so as to cover most of the topics relevant to ISI of research reactors. Important topics such as rationale for in-service inspection, material degradation mechanisms, non-destructive examination techniques, design evaluation of flaws and radiological, codal and regulatory aspects of ISI for research reactors were covered. Lectures on ISI of elastomeric materials and concrete structures, which are generally used in the construction of reactors have also been included in the course. Papers relevant to INIS are indexed separately

A dedicated program for the extended longevity of research and training reactors

International Nuclear Information System (INIS)

Carriveau, G.W.

1992-01-01

In the past 49 years, over 555 research and training reactors have been in operation, with approximately 325 currently in service. The age distribution of operating research reactors shows that the average age is about 24 years; about 74% are 20 years old or older and about 33% are 30 years old or older. This group of reactors represents a very large investment in capital expense with replacement costs in 1990's prices much higher than when they were originally constructed. Furthermore, decommissioning costs may be much greater than the original investments. General Atomics has been directly involved for the better part of the nearly fifty year history of research and training reactors. This paper will describe a General Atomics program illustrating a dedicated commitment to the full service support of extended and improved use for all types of research and training reactors. (author)

Kawasaki disease in Ghana: Case reports from Korle Bu Teaching ...

African Journals Online (AJOL)

Kawasaki disease, an acute febrile vasculitis, predominantly affects children under the age of 5 years and is thought to be a rare disease in the developing world. . It has previously never been reported in Ghana. We report 3 cases from February, 2007 to February, 2008. This potentially serious disease has no definitive ...

Experiments with the SUR 100 training reactor

International Nuclear Information System (INIS)

Milicic, B.

1984-06-01

This paper contains a compilation of various experiments using the SUR - 100 reactor for training purposes, which have been widly proved in practical work at the School for Nuclear Technology of the Karlsruhe Research Center. (orig.) [de

Pyrosequencing Analysis of Norovirus Genogroup II Distribution in Sewage and Oysters: First Detection of GII.17 Kawasaki 2014 in Oysters.

Science.gov (United States)

Pu, Jian; Kazama, Shinobu; Miura, Takayuki; Azraini, Nabila Dhyan; Konta, Yoshimitsu; Ito, Hiroaki; Ueki, You; Cahyaningrum, Ermaya Eka; Omura, Tatsuo; Watanabe, Toru

2016-12-01

Norovirus GII.3, GII.4, and GII.17 were detected using pyrosequencing in sewage and oysters in January and February 2015, in Japan. The strains in sewage and oyster samples were genetically identical or similar, predominant strains belonging to GII.17 Kawasaki 2014 lineage. This is the first report of GII.17 Kawasaki 2014 in oysters.

Biphasic thallium 201 SPECT-imaging for the noninvasive diagnosis of myocardial perfusion abnormalities in a child with Kawasaki disease--a case report

International Nuclear Information System (INIS)

Hausdorf, G.; Nienaber, C.A.; Spielman, R.P.

1988-01-01

The mucocutaneous lymph node syndrome (Kawasaki disease) is of increasing importance for the pediatric cardiologist, for coronary aneurysms with the potential of thrombosis and subsequent stenosis can develop in the course of the disease. The authors report a 2 1/2-year-old female child in whom, fourteen months after the acute phase of Kawasaki disease, myocardial infarction occurred. Biphasic thallium 201 SPECT-imaging using dipyridamole depicted anterior wall ischemia and inferolateral infarction. This case demonstrates that noninvasive vasodilation-redistribution thallium 201 SPECT-imaging has the potential to predict reversible myocardial perfusion defects and myocardial necrosis, even in small infants with Kawasaki disease

The design and use of proficiency based BWR reactor maintenance and refuelling training mockups

International Nuclear Information System (INIS)

Ford, G.J.

1996-01-01

The purpose of this paper is to describe the ABB experience with the design and use of boiling water reactor training facilities. The training programs were developed and implemented in cooperation with the nuclear utilities. ABB operates two facilities, the ABB ATOM Light Water Reactor Service Center located in Vasteras, Sweden, and the ABB Combustion Engineering Nuclear Operations BWR Training Center located in Chattanooga, Tennessee, USA. The focus of the training centers are reactor maintenance and refueling activities plus the capability to develop and qualify tools, procedures and repair techniques

Approach to training the operators of WWER-440 reactors

International Nuclear Information System (INIS)

Pironkov, L.; Minakova, R.

2002-01-01

The paper has three parts. (1) Personnel Training and Qualifications (2) Description of Kozloduy NPP Training and Qualification System (TQS) built in the last 7 years and its interfaces with the Certification System and (3) Application of the TQS for the Senior Reactor Operator (SRO). (author)

Study on reactor power transient characteristics (reactor training experiments). Control rod reactivity calibration by positive period method and other experiment

International Nuclear Information System (INIS)

Ozaki, Yoshihiko; Sunagawa, Takeyoshi

2014-01-01

In this paper, it is reported about some experiments that have been carried out in the reactor training that targets sophomore of the department of applied nuclear engineering, FUT. Reactor of Kinki University Atomic Energy Research Institute (UTR-KINKI) was used for reactor training. When each critical state was achieved at different reactor output respectively in reactor operating, it was confirmed that the control rod position at that time does not change. Further, control rod reactivity calibration experiments using positive Period method were carried out for shim safety rod and regulating rod, respectively. The results were obtained as reasonable values in comparison with the nominal value of the UTR-KINKI. The measurement of reactor power change after reactor scram was performed, and the presence of the delayed neutron precursor was confirmed by calculating the half-life. The spatial dose rate measurement experiment of neutrons and γ-rays in the reactor room in a reactor power 1W operating conditions were also performed. (author)

Vaccines and Kawasaki disease.

Science.gov (United States)

Esposito, Susanna; Bianchini, Sonia; Dellepiane, Rosa Maria; Principi, Nicola

2016-01-01

The distinctive immune system characteristics of children with Kawasaki disease (KD) could suggest that they respond in a particular way to all antigenic stimulations, including those due to vaccines. Moreover, treatment of KD is mainly based on immunomodulatory therapy. These factors suggest that vaccines and KD may interact in several ways. These interactions could be of clinical relevance because KD is a disease of younger children who receive most of the vaccines recommended for infectious disease prevention. This paper shows that available evidence does not support an association between KD development and vaccine administration. Moreover, it highlights that administration of routine vaccines is mandatory even in children with KD and all efforts must be made to ensure the highest degree of protection against vaccine-preventable diseases for these patients. However, studies are needed to clarify currently unsolved issues, especially issues related to immunologic interference induced by intravenous immunoglobulin and biological drugs.

Hands-on Training Courses Using Research Reactors and Accelerators

International Nuclear Information System (INIS)

2014-01-01

The enhancement of nuclear science education and training in all Member States is of interest to the IAEA since many of these countries, particularly in the developing world, are building up and expanding their scientific and technological infrastructures. Unfortunately, most of these countries still lack sufficient numbers of well-educated and qualified nuclear specialists and technologists. This may arise from, amongst other things: a lack of candidates with sufficient educational background in nuclear science who would qualify to receive specialized training; a lack of institutions available for training nuclear science specialists; a lack of lecturers in nuclear related fields; and a lack of suitable educational and teaching materials. A related concern is the potential loss of valuable knowledge accumulated over many decades due to the ageing workforce. An imperative for Member States is to develop and offer suitable graduate and postgraduate academic programmes which combine study and project work so that students can attain a prerequisite level of knowledge, abilities and skills in their chosen subject area. In nearly all academic programmes, experimental work forms an essential and integral component of study to help students develop general and subject specific skills. Experimental laboratory courses and exercises can mean practical work in a conventional laboratory or an advanced facility with an operational particle accelerator or research reactor often accompanied by computer simulations and theoretical exercises. In this context, available or newly planned research reactors and particle accelerators should be seen as extremely important and indispensable components of nuclear science and technology curricula. Research reactors can demonstrate nuclear science and technology based on nuclear fission and the interaction of neutrons and photons with matter, while particle accelerators can demonstrate nuclear science and technology based on charged particle

75 FR 1819 - GE-Hitachi Global Laser Enrichment LLC; (GLE Commercial Facility); Notice of Receipt of...

Science.gov (United States)

2010-01-13

... Energy Americas LLC (GEH), which is a wholly owned subsidiary of GE-Hitachi Nuclear Energy Holdings LLC..., 2009, the NRC published notice of its intent to prepare an Environmental Impact Statement (EIS) on the... on the issuance of a license is completed. See Notice of Intent to Prepare an Environmental Impact...

Development of Reactor TRIGA PUSPATI Simulator for Education and Training

International Nuclear Information System (INIS)

Mohd Sabri Minhat; Zarina Masood; Muhammad Rawi Mohamed Zin

2016-01-01

The real-time simulator for Reactor TRIGA PUSPATI (RTP) which is under development. The main purpose of this simulator is operator training and a dynamic test bed (DTB) to test and validate the control logics in reactor regulating system (RRS) of RTP. The simulator configuration is divided into hardware and software. The simulator hardware consists of a host computer, operator station, a network switch, control rod drive mechanism and a large display panel. The RTP hardwired panel is replicated similar to real console. The software includes a mathematical model includes reactor kinetics and thermal-hydraulics that implements plant dynamics in real-time using LabVIEW, an instructor station module work as host computer that manages user instructions, and a human machine interface module as a graphical user interface which is used in the real RTP plant. The developed TRIGA reactor simulators are installed in the Malaysian Nuclear Agency nuclear training center for reactor operator training. To use the simulator as a dynamic test-bed, the reactor regulating system modeling software of the simulator was replaced by actual RRS cabinet which is consist of Programmable Logic Controller (PLC) S7-1500, and was interfaced using a hard-wired and network-based interface. RRS cabinet generates control signals for reactor power control based on the various feedback signals from DTB such as neutron detector signal and control rod positions, and the DTB runs plant dynamics based on the RRS control signals. Thus the Hardware-In-the-Loop Simulation between RRS and the emulated plant (DTB) has been implemented and tested in this configuration. Normal and abnormal case test have been emulated for this project. In conclusion, the functions and the control performance of the developed RTP dynamic test bed simulator have been tested showing reasonable and acceptable results. (author)

Pulse methylprednisolone therapy for impending cardiac tamponade in immunoglobulin-resistant Kawasaki disease

NARCIS (Netherlands)

Dahlem, P. G.; von Rosenstiel, I. A.; Lam, J.; Kuijpers, T. W.

1999-01-01

We describe a boy with Kawasaki disease (KD) whose clinical course was marked by a rapid improvement upon treatment with intravenous immunoglobulin (IVIG) and oral aspirin, which - within 14 days - was followed by the development of a large pericardial effusion with symptoms of impending cardiac

Nuclear Education and Training Courses as a Commercial Product of a Low Power Research Reactor

International Nuclear Information System (INIS)

Böck, H.; Villa, M.; Steinhauser, G.

2013-01-01

The Vienna University of Technology (VUT) operates a 250 kW TRIGA Mark II research reactor at the Atominstitut (ATI) since March 1962. This reactor is uniquely devoted to nuclear education and training with the aim to offer an instrument to perform academic research and training. During the past decade a number of requests to the Atominstitut asked for the possibility to offer this reactor for external training courses. Over the years, such courses have been developed as regular courses for students during their academic curricula at the VUT/ATI. The courses cover such subjects as “Reactor physics and kinetics”, and “Reactor instrumentation and control”, in total about 20 practical exercises. Textbooks have been developed in English language for both courses. Target groups for commercial courses are other universities without an access to research reactors (i.e., the Technical University of Bratislava, Slovak Republic, or the University of Manchester, UK), international organisations (i.e., IAEA Dept of Safeguards, training section), research centres (ie. Mol, Belgium) for retraining of their reactor staff or nuclear power plants for staff retraining. These courses have been very successful during the past five years in such a manner that the Atominstitut has now to decline new course applications as the reactor is also used for Masters thesis and PhD work which requires full power operation while courses require low power operation. The paper describes typical training programs, target groups and possible transfers of these courses to other reactors. (author)

Medium/small-scale computers HITACHI M-620, M-630, and M-640 systems: the aim of development and characteristics

Energy Technology Data Exchange (ETDEWEB)

Oshima, N; Saiki, Y; Sunaga, K [Hitachi, Ltd., Tokyo (Japan)

1990-10-01

The medium/small-scale HITACHI M-620, M-630, and M-640 computer systems are outlined. Every system is featured by the configuration usable as a medium or small-scale host computer in offices, the function connectable with large-scale host computers, the performance of 5-50 times those of conventional office computers, easy operation and fast processing. As features of the hardware, the one-board CPU and small integrated cubicle structure containing the CPU board, high-speed large-capacity magnetic disk storage device, various kinds of controllers and others are illustrated. As features of the software, the OS (VOS K) featured by the virtual data space control (VDSA) and relational database (RDB) functions, EAGLE/4GL (effective approach to achieving high level software productivity/4th generation language), STEP (self training environmental support program) and simple end user language ACE3/E2 are outlined. 7 figs.

PC data station for Hitachi F-2000 spectrofluorimeter

International Nuclear Information System (INIS)

Yakub Ali, Mohd; Dhoble, A.R.; Jadhav, R.T.; Godbole, S.V.

2004-01-01

The paper describes the PC based data station for stand-alone HIT ACHI F-2000 Spectrofluorimeter, for data acquisition, storage and analysis. The hardware link between the instrument and PC is made through RS232 serial port. The state of art software for control and data management is designed, developed and implemented in Visual Basic (Version 6). The software features on-screen editing of all operation parameters of the instrument and the operational control is achieved by Visual Basic command words communicated through serial port. Using this system, in addition to acquiring and storage of spectral data, it was possible to obtain the normalized absorption spectra of the samples. PC adapted Hitachi F-2000 Spectrofluorimeter can be successfully used for various operations such as photometric detection of UO22+ ions, recording of emission and excitation spectra and time evolution of fluorescence intensity on continuous UV irradiation. The data storage achieved through PC adaptation has also enabled recording of absorption spectra. (author)

Minority and female training programs at the Ford Nuclear Reactor, University of Michigan

International Nuclear Information System (INIS)

Burn, R.R.

1992-01-01

Nuclear power industry operations staffs are composed predominantly of white males because most of the personnel come from the nuclear submarine and surface branches of the U.S. Navy. The purpose of the minority and female training programs sponsored by the Ford Nuclear Reactor at the University of Michigan is to provide a path for minorities and women to enter the nuclear industry as operators, technicians, and, in the long term, as graduate engineers. The training programs are aimed at high school students, preferably juniors. While the training is directed toward operation of a nuclear reactor, it is equally applicable to careers in most other technical fields. It is hoped that some of the participants will remain at the Ford Nuclear Reactor as reactor operators, enter college, and obtain college degrees, after which they will enter the nuclear industry as graduate engineers

United States Department of Energy breeder reactor staff training domestic program

International Nuclear Information System (INIS)

1984-01-01

Two US DOE projects in the Pacific Northwest offer unique on-the-scene training opportunities at sodium-cooled fast-reactor plants: the Fast Flux Test Facility (FFTF) near Richland, Washington, which has operated successfully in a wide range of irradiation test programs since 1980; and the Experimental Breeder Reactor II (EBR-II) near Idaho Falls, Idaho, which has been in operation for approximately 20 years. Training programs have been especially designed to take advantage of this plant experience. Available courses are described

Training courses on neutron detection systems on the ISIS research reactor: on-site and through internet training

Energy Technology Data Exchange (ETDEWEB)

Lescop, B.; Badeau, G.; Ivanovic, S.; Foulon, F. [National Institute for Nuclear science and Technology French Atomic Energy and Alternative Energies Commission (CEA), Saclay Research Center, 91191 Gif-sur-Yvette (France)

2015-07-01

Today, ISIS research reactor is an essential tool for Education and Training programs organized by the National Institute for Nuclear Science and Technology (INSTN) from CEA. In the field of nuclear instrumentation, the INSTN offers both, theoretical courses and training courses on the use of neutron detection systems taking advantage of the ISIS research reactor for the supply of a wide range of neutron fluxes. This paper describes the content of the training carried out on the use of neutron detectors and detection systems, on-site or remote. The ISIS reactor is a 700 kW open core pool type reactor. The facility is very flexible since neutron detectors can be inserted into the core or its vicinity, and be used at different levels of power according to the needs of the course. Neutron fluxes, typically ranging from 1 to 10{sup 12} n/cm{sup 2}.s, can be obtained for the characterisation of the neutron detectors and detection systems. For the monitoring of the neutron density at low level of power, the Instrumentation and Control (I and C) system of the reactor is equipped with two detection systems, named BN1 and BN2. Each way contains a fission chamber, type CFUL01, connected to an electronic system type SIREX.The system works in pulse mode and exhibits two outputs: the counting rate and the doubling time. For the high level of power, the I and C is equipped with two detection systems HN1 and HN2.Each way contain a boron ionization chamber (type CC52) connected to an electronics system type SIREX. The system works in current mode and has two outputs: the current and the doubling time. For each mode, the trainees can observe and measure the signal at the different stages of the electronic system, with an oscilloscope. They can understand the role of each component of the detection system: detector, cable and each electronic block. The limitation of the detection modes and their operating range can be established from the measured signal. The trainees can also

Training courses on neutron detection systems on the ISIS research reactor: on-site and through internet training

International Nuclear Information System (INIS)

Lescop, B.; Badeau, G.; Ivanovic, S.; Foulon, F.

2015-01-01

Today, ISIS research reactor is an essential tool for Education and Training programs organized by the National Institute for Nuclear Science and Technology (INSTN) from CEA. In the field of nuclear instrumentation, the INSTN offers both, theoretical courses and training courses on the use of neutron detection systems taking advantage of the ISIS research reactor for the supply of a wide range of neutron fluxes. This paper describes the content of the training carried out on the use of neutron detectors and detection systems, on-site or remote. The ISIS reactor is a 700 kW open core pool type reactor. The facility is very flexible since neutron detectors can be inserted into the core or its vicinity, and be used at different levels of power according to the needs of the course. Neutron fluxes, typically ranging from 1 to 10 12 n/cm 2 .s, can be obtained for the characterisation of the neutron detectors and detection systems. For the monitoring of the neutron density at low level of power, the Instrumentation and Control (I and C) system of the reactor is equipped with two detection systems, named BN1 and BN2. Each way contains a fission chamber, type CFUL01, connected to an electronic system type SIREX.The system works in pulse mode and exhibits two outputs: the counting rate and the doubling time. For the high level of power, the I and C is equipped with two detection systems HN1 and HN2.Each way contain a boron ionization chamber (type CC52) connected to an electronics system type SIREX. The system works in current mode and has two outputs: the current and the doubling time. For each mode, the trainees can observe and measure the signal at the different stages of the electronic system, with an oscilloscope. They can understand the role of each component of the detection system: detector, cable and each electronic block. The limitation of the detection modes and their operating range can be established from the measured signal. The trainees can also modify the

The computer aided education and training system for accident management

International Nuclear Information System (INIS)

Yoneyama, Mitsuru; Kubota, Ryuji; Fujiwara, Tadashi; Sakuma, Hitoshi

1999-01-01

The education and training system for Accident Management was developed by the Japanese BWR group and Hitachi Ltd. The education and training system is composed of two systems. One is computer aided instruction (CAI) education system and the education and training system with computer simulations. Both systems are designed to be executed on personal computers. The outlines of the CAI education system and the education and training system with simulator are reported below. These systems provides plant operators and technical support center staff with the effective education and training for accident management. (author)

Training nuclear power plant personnel on SR-O reactor

International Nuclear Information System (INIS)

Cerny, K.; Boucek, F.; Kveton, M.; Prokopec, Z.; Fleischhans, J.

1983-01-01

The SR-O reactor is an experimental pool-type reactor with a maximum output of 1 MW and maximum thermal neutron flux density of 5.3x10 13 m -2 s -1 . The reactor is described in detail and its specifications are given. The protection and control systems of the reactor permit both manual and automatic operation. The reactor is used for training courses for nuclear power plant operators and for post-graduate study courses for other specialists. Intensive courses for 4 to 6 persons take 15 to 20 days. The course is adjusted to the results of introductory theoretical tests. An optimal teaching method has been developed based on the flowchart algorithmic method, dividing activities into operations (manipulations with controls, issuing commands, making records, etc.) and decision making (information reception and processing). (M.D.)

Facial nerve palsy in a thirteen-year-old male youth with Kawasaki disease

NARCIS (Netherlands)

Biezeveld, Maarten H.; Voorbrood, Bas S.; Clur, Sally-Ann B.; Kuijpers, Taco W.

2002-01-01

A 13-year-old male youth was hospitalized with Kawasaki disease. In the course of the disease he developed a facial nerve palsy and an aneurysm of the right coronary artery. After treatment with immunoglobulins both complications disappeared within 10 days and 1 month, respectively

Operation characteristics and conditions of training reactor VR-1

International Nuclear Information System (INIS)

Matejka, K.; Kolros, A.; Polach, S.; Sklenka, L.

1994-01-01

The first 3 years of operation of the VR-1 training reactor are reviewed. This period includes its physical start-up (preparation, implementation, results) and operation development as far as the current operating configuration of the reactor core. The physical start-up was commenced using a reactor core referred to as AZ A1, whose physical parameters had been verified by calculation and whose configuration was based on data tested experimentally on the SR-0 reactor at Vochov. The next operating core, labelled AZ A2, was already prepared during the test operation of the VR-1 reactor. Its configuration was such that both of the main horizontal channels, radial and tangential, could be employed. The configuration that followed, AZ A3, was an intermediate step before testing the graphite side reflector. The current reactor core, labelled AZ A3 G, was obtained by supplementing the previous core with a one-sided graphite side reflector. (Z.S.). 2 tabs., 11 figs., 2 refs

Behavioral Response in the Immediate Aftermath of Shaking: Earthquakes in Christchurch and Wellington, New Zealand, and Hitachi, Japan

Directory of Open Access Journals (Sweden)

Ihnji Jon

2016-11-01

Full Text Available This study examines people’s response actions in the first 30 min after shaking stopped following earthquakes in Christchurch and Wellington, New Zealand, and Hitachi, Japan. Data collected from 257 respondents in Christchurch, 332 respondents in Hitachi, and 204 respondents in Wellington revealed notable similarities in some response actions immediately after the shaking stopped. In all four events, people were most likely to contact family members and seek additional information about the situation. However, there were notable differences among events in the frequency of resuming previous activities. Actions taken in the first 30 min were weakly related to: demographic variables, earthquake experience, contextual variables, and actions taken during the shaking, but were significantly related to perceived shaking intensity, risk perception and affective responses to the shaking, and damage/infrastructure disruption. These results have important implications for future research and practice because they identify promising avenues for emergency managers to communicate seismic risks and appropriate responses to risk area populations.

Ideal gas approximation for a two-dimensional rarefied gas under Kawasaki dynamics

NARCIS (Netherlands)

Gaudillière, A.; Hollander, den W.Th.F.; Nardi, F.R.; Olivieri, E.; Scoppola, E.

2009-01-01

In this paper we consider a two-dimensional lattice gas under Kawasaki dynamics, i.e., particles hop around randomly subject to hard-core repulsion and nearest-neighbor attraction. We show that, at fixed temperature and in the limit as the particle density tends to zero, such a gas evolves in a way

Metastability for Kawasaki dynamics at low temperature with two types of particles

NARCIS (Netherlands)

Hollander, den W.Th.F.; Nardi, F.R.; Troiani, A.

2011-01-01

This is the fi??rst in a series of three papers in which we study a two-dimensional lattice gas consisting of two types of particles subject to Kawasaki dynamics at low temperature in a large fi??nite box with an open boundary. Each pair of particles occupying neighboring sites has a negative

Needs of nuclear data for advanced light water reactor

International Nuclear Information System (INIS)

Chaki, Masao

2008-01-01

Hitachi has been developing medium sized ABWRs as a power source that features flexibility to meet various market needs, such as minimizing capital risks, providing a timely return on capital investments, etc. Basic design concepts of the medium sized ABWRs are 1) using the current ABWR design which has accumulated favorable construction and operation histories as a starting point; 2) utilizing standard BWR fuels which have been fabricated by proven technology; 3) achieving a rationalized design by suitably utilizing key components developed for large sized reactors. Development of the medium sized ABWRs has proceeded in a systematic, stepwise manner. The first step was to design an output scale for the 600MWe class reactor (ABWR-600), and the next step was to develop an uprating concept to extend this output scale to the 900MWe class reactor (ABWR-900) based on the rationalized technology of the ABWR-600 for further cost savings. In addition, Hitachi and MHI developed an ultra small reactor, 'Package-Reactor'. About the nuclear data, for the purpose of verification of the nuclear analysis method of BWR for mixed oxide (MOX) cores, UO 2 and MOX fuel critical experiments EPICURE and MISTRAL were analyzed using nuclear design codes HINES and CERES with ENDF/B nuclear data file. The critical keffs of the absorber worth experiments, the water hole worth experiments and the 2D void worth experiments agreed with those of the reference experiments within about 0.1%Δk. The root mean square differences of radial power distributions between calculation and measurement were almost less than 2.0%. The calculated reactivity worth values of the absorbers, the water hole and the 2D void agreed with the measured values within nearly experimental uncertainties. These results indicate that the nuclear analysis method of BWR in the present paper give the same accuracy for the UO 2 cores and the MOX cores. (author)

Dipyridamole-thallium-201 tomography documenting improved myocardial perfusion with therapy in Kawasaki disease

International Nuclear Information System (INIS)

Nienaber, C.A.; Spielmann, R.P.; Hausdorf, G.

1988-01-01

Thallium-201 tomographic perfusion studies after pharmacologic vasodilation were performed in seven children (aged 2 years 8 months to 8 years 7 months), 3 to 20 months after the acute stage of the disease. In all patients coronary aneurysms were seen on cross-sectional echocardiograms. The scintigrams of six children showed no significant regional reduction of myocardial thallium-201 uptake. These children had remained asymptomatic in the follow-up period after the acute inflammatory stage of Kawasaki disease. Persistent and transient thallium defects were present in one child with acute posterolateral myocardial infarction; obstruction of two coronary vessels supplying the defect zones was confirmed by contrast angiography. After 8 months of treatment a follow-up nuclear scan showed marked reduction in the size of the defect and almost complete abolishment of the ischemic reaction. Thus tomographic thallium-201 perfusion scintigraphy in conjunction with vasodilation stress is useful to assess myocardial perfusion in children with Kawasaki disease and demonstrates marked improvement in regional perfusion after adequate medical therapy

Kawasaki disease: An unusual presentation in a 14-year old boy in ...

African Journals Online (AJOL)

Kawasaki disease (KD) is an acute systemic vasculitis that mostly affects children less than 5years. Occasionally, it may presents with renal involvement of varying severity. In Nigeria and most of Africa, only a few cases of KD have been reported and these were among children within the typical age group. We report an ...

Guideline related to training and re-training of research reactor personnel

International Nuclear Information System (INIS)

1983-01-01

The guideline, which entered into force on 1 July 1983, lays down training and re-training requirements to be met by research reactor personnel in the framework of the Radiation Protection Ordinance of 26 November 1969, the Regulation related to the Licensing of Nuclear Facilities of 21 June 1979, and the Regulation related to Further Education in the Field of Radiation Protection 27 January 1975. It contains the scope of application; the principles and objectives; the minimum requirements relating to technical qualification of plant managers, shift personnel, and responsible radiation protection officers; appointment and certification; the preservation of the technical qualification; and exceptional and transitional regulations

Plasma discharge in ferritic first wall vacuum vessel of the Hitachi Tokamak HT-2

International Nuclear Information System (INIS)

Abe, Mitsushi; Nakayama, Takeshi; Asano, Katsuhiko; Otsuka, Michio

1997-01-01

A tokamak discharge with ferritic material first wall was tried successfully. The Hitachi Tokamak HT-2 had a stainless steel SUS304 vacuum vessel and modified to have a ferritic plate first wall for experiments to investigate the possibility of ferritic material usage in magnetic fusion devices. The achieved vacuum pressure and times used for discharge cleaning was roughly identical with the stainless steel first wall or the original HT-2. We concluded that ferritic material vacuum vessel is possible for tokamaks. (author)

The reconstruction of the training reactor of the Budapest Technical University

International Nuclear Information System (INIS)

Viragh, E.

1981-01-01

The reconstruction of the training reactor between 1978 and 1981 did not hinder the education and training activities of the University. Dosimetric measurements during the test run revealed no additional hazard from the elevation of power from 10 to 100 kW. (author)

Pilot program: NRC severe reactor accident incident response training manual: Severe reactor accident overview

International Nuclear Information System (INIS)

McKenna, T.J.; Martin, J.A.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

1987-02-01

This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Severe Reactor Accident Overview is the second in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assesment. Each volume serves, respectively, as the text for a course of instruction in a series of courses. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

A positron emission tomography study of cardiac sequelae in children with Kawasaki disease, 1

International Nuclear Information System (INIS)

Ohmochi, Yutaka

1994-01-01

This study quantitatively measured regional myocardial blood flow (MBF) and perfusable tissue fraction (pTF) in 25 children (mean age: 17.2±2.7) with Kawasaki disease using positron emission tomography and H 2 15 O. Patients were divided into three groups based on coronary angiographic findings. Group 1 consisted of 11 patients with normal coronary angiograms; Group 2, 7 patients with stenotic coronary lesions. There were no significant differences in MBF and pTF among 5 divided regions on the left ventricular wall. Average MBF at rest in Group 1 was 0.91±0.19 ml/min/g. There was a poor correlation between MBF estimated positron emission tomography and patient's age in Group 1. (r=-0.374, Y=-0.0234X + 1.254: p 2 15 O, to determine the functional capacity of coronary artery lesions and myocardial damage in children with Kawasaki disease. (author)

PENGARUH KELOMPOK REFERENSI TERHADAP KEPUTUSAN PEMBELIAN KAWASAKI NINJA 250 CC

OpenAIRE

Kartika WB, Sylvia; Sidig, Rosyid

2018-01-01

The purpose of this study is to examine the affect of reference groups  on purchasing decision of  Kawasaki Ninja 250 cc in the city of Jambi. Size of sample consist of 100 unit that chousen randomly. While data analysis used  multiple regression analysis. The results showed that simultaneouly   normative, value expression, and  informative have significant role. But, based on partiall test  normative has no significant affect. Hence,  reference group h...

AKR-1 nuclear training reactor of Dresden Technical University turns twenty-five

International Nuclear Information System (INIS)

Hansen, W.

2003-01-01

Twenty-five years ago, in the night of July 27 to 28, 1978, the AKR-1 nuclear training reactor of the Dresden Technical University went critical for the first time and was commissioned. On the occasion of this anniversary, a colloquy was arranged with representatives from science, politics and industry, at which the reactor's history, the excellent achievements in research and training with the reactor, and the status and perspectives of this research facility were described. The AKR-1 had been built within the framework of the Nuclear Development Program of the then German Democratic Republic (GDR). The Nuclear Power Scientific Division of the Dresden Technical University had been entrusted with the responsibility, among other things, to train university personnel for the GDR Nuclear Power Program. The review by an expert group in 1996 of this plant had resulted in a recommendation in favor of long-term plant operation. A nuclear licensing procedure to this effect was initiated, and the necessary technical backfitting measures were implemented. The AKR-1 plant now equally serves for the specialized training of students and for research. (orig.) [de

Training methods and facilities on reactor and simulators at the Grenoble Nuclear Research Centre

International Nuclear Information System (INIS)

Destot, M.; Siebert, S.

1987-01-01

Siloette is a CEA unit with a threshold vocation: operation of the Siloette 100 KW pool-type research reactor; basic training in reactor physics for nuclear power plant operators; and production of nuclear power plant simulators: PWR, GCR and more generally of all types of industrial unit simulators, thermal power plant, network, chemical plant, etc. From this experience, they would emphasize in particular the synergy arising from these complementary activities, the essential role of training in basic principles as a complement to operation training, and the ever-increasing importance of design ergonomics of the training means

Study of dietary supplements compositions by neutron activation analysis at the VR-1 training reactor

Science.gov (United States)

Stefanik, Milan; Rataj, Jan; Huml, Ondrej; Sklenka, Lubomir

2017-11-01

The VR-1 training reactor operated by the Czech Technical University in Prague is utilized mainly for education of students and training of various reactor staff; however, R&D is also carried out at the reactor. The experimental instrumentation of the reactor can be used for the irradiation experiments and neutron activation analysis. In this paper, the neutron activation analysis (NAA) is used for a study of dietary supplements containing the zinc (one of the essential trace elements for the human body). This analysis includes the dietary supplement pills of different brands; each brand is represented by several different batches of pills. All pills were irradiated together with the standard activation etalons in the vertical channel of the VR-1 reactor at the nominal power (80 W). Activated samples were investigated by the nuclear gamma-ray spectrometry technique employing the semiconductor HPGe detector. From resulting saturated activities, the amount of mineral element (Zn) in the pills was determined using the comparative NAA method. The results show clearly that the VR-1 training reactor is utilizable for neutron activation analysis experiments.

Moroccan TRIGA nuclear reactor, an important tool for the development of research, education and training

International Nuclear Information System (INIS)

Caoui, A.

2011-01-01

Full text: The construction of the Nuclear Research Center of Maamora (NRCM) will enable to the National Center for Nuclear Energy, Sciences and Techniques (CNESTEN) to fulfill its missions for promotion of nuclear techniques in socioeconomic fields, act as technical support for the authorities, and contribute to the introduction of nuclear power for electricity generation considered in the new energy strategy as alternative option for the period 2020-2030. The CNESTEN has commisioned its nuclear research reactor Triga Mark II of 2000 KW on 2007 for wich the operating authorization was delivered on 2009. This research reactor is the keystone structure of the NRCM, its existing and planed utilization include: production of radioisotopes for medical use, neutron activation analysis, non-destructive examination techniques, neutron scattering, reactor physics research and training. In term of human ressources development, CNESTEN is more focusing on education and training for wich an international training Center is under development. The TRIGA research reactor will be an important component of this center. In order to promote the utilization of the reserch reactor in socio-economical sectors at national level, CNESTEN organizea meetings, schools and conferences around each of the reactor applications, and offers the opportunity to researchers, students, socio-economic operators to know more about reactor utilization within scientific visits, courses and training programs. At the international level, CNESTEN strengthens its international partenership. The regional and international cooperation with IAEA, AFRA and bilateral parteners (USA, France), constitutes the platform for capacity building in different areas of CNESTEN RIGA research reactor utilization

Kawasaki dynamics with two types of particles : stable/megastable configurations and communication heights

NARCIS (Netherlands)

Hollander, den W.Th.F.; Nardi, F.R.; Troiani, A.

2011-01-01

This is the second in a series of three papers in which we study a two-dimensional lattice gas consisting of two types of particles subject to Kawasaki dynamics at low temperature in a large finite box with an open boundary. Each pair of particles occupying neighboring sites has a negative binding

Kawasaki dynamics with two types of particles: stable/megastable configurations and communication heights

NARCIS (Netherlands)

Hollander, den W.Th.F.; Nardi, F.R.; Troiani, A.

2011-01-01

This is the second in a series of three papers in which we study a two-dimensional lattice gas consisting of two types of particles subject to Kawasaki dynamics at low temperature in a large finite box with an open boundary. Each pair of particles occupying neighboring sites has a negative binding

SARIE upgrade: Nuclear reactor and water systems 'engineering and training' simulator

International Nuclear Information System (INIS)

Roth, P.

2006-01-01

Confronted as of its origins with the on-board layout constraints of the French Navy ships, TECHNICATOME integrates, as of the design, the ergonomics and the risks control related to the human factors. During more than 30 years, TECHNICATOME demonstrated a one of a kind know-how from the design to the execution of powerful, flexible and highly available nuclear compact reactors. A total control which includes up to the supervision and monitoring systems, the acoustic discreetly of the systems and its components, implemented on on-board reactors, testing reactors as well as experimental reactors. The functionalities of simulation were right from the start used by TECHNICATOME during the design phase of these installations to carry out operation engineering analyses on the thermal hydraulic and neutron aspects, to validate the principles of operation of the supervision systems like by the use of digital models in 3D CAD to validate the kinematics of operation or the interactions between systems. More recently, and starting from the end of the Nineties, a thought needs was launched to determine the interests related to the development of a training simulator associated with these installations with objectives, among others, to ensure the phase of initial training of the new operators, to widen the field of the training to the accidental situations, the management of crisis and crews behaviour supervision, the possibilities of replay which support the consolidation of the acquired knowledge(debriefing) with situation resume, and to increase the overall training capacity. An upgrade and modernisation project of these various simulation means was thus launched since 2001 with the objective to optimize the whole of the tasks supported by these means. (author)

Enfermedad de kawasaki: A propósito de un caso

Directory of Open Access Journals (Sweden)

Raquel Fernández Ferrán

2000-09-01

Full Text Available Se presenta una paciente de 2 meses de edad con los síntomas y signos de la enfermedad de Kawasaki. Se descartan mediante los exámenes complementarios otras enfermedades más comunes en la infancia. Se hace una revisión de la enfermedad y se señala la importancia del diagnóstico y tratamiento precoces. A pesar de la corta edad de la niña ésta no presentó afectación de las arterias coronarias. Su evolución fue favorable, y se observó mejoría (caída de la temperatura a menos de 38 C a partir del 4to. día después de comenzar el tratamiento. Se utilizó el esquema de dosis única de gammaglobulina asociada con los salicilatos.A two-months old female patient with symptoms and signs of Kawasaki disease is presented in this paper. Supplementary tests disregarded the presence of other common diseases in early childhood. The disease is reviewed, pointing out the importance of early diagnosis and treatment. Despite her small age, the girls did not have any lesion in coronary arteries. A recovery was observed (temperature fell below 38 C on the 4th day after beginning of the treatment. The single dosage of gammaglobulin scheme associated to salicylates was used.

Outline of advanced boiling water reactor

International Nuclear Information System (INIS)

Yoshio Matsuo

1987-01-01

The ABWR (Advanced Boiling Water Reactor) is based on construction and operational experience in Japan, USA and Europe. It was developed jointly by the BWR supplieres, General Electric, Hitachi, and Toshiba, as the next generation BWR for Japan. The Tokyo Electric Power Co. provided leadership and guidance in developing the ABWR, and in combination with five other Japanese electric power companies. The major objectives in developing the ABWR are: 1. Enhanced plant operability, maneuverability and daily load-following capability; 2. Increased plant safety and operating margins; 3. Improved plant availability and capacity factor; 4. Reduced occupational radiation exposure; 5. Reduced radwaste volume, and 6. Reduced plant capital and operating costs. (Liu)

Recent development of the Cu/Nb-Ti superconducting cables for SSC in Hitachi Cable, Ltd

International Nuclear Information System (INIS)

Sakai, S.; Iwaki, G.; Sawada, Y.; Moriai, H.; Ishigami, Y.

1989-01-01

In these few years, Cu/Nb-Ti superconducting cables for the dipole magnets of SSC projects have been developed in the industrial scale in Hitachi Cable, Ltd. The features of these developed conductors are as follows. (1) The diameter of Nb-Ti filaments is very small, 4-6 μm. (2) The critical current density (J c ) is very high, 2,850-3,050 A/mm 2 at 5 T on wires, 2750-2950 A/mm 2 at 5 T on cables in industrial scale. The champion J c of wires is 3,460 A/mm 2 at 5 T in the laboratory scale. (3) The RRR Residual Resistivity Ratio values of developed cables is very high, approximately 200, due to the newly developed high purity Oxygen Free Copper (OFC). (4) The conductors have been wound to the 1 m length dipole magnet in Hitachi Ltd., and it has generated 6.7 T in the central magnetic field at 6,595 A. The Cu/Cu-Mn/Nb-Ti composite wires which avoid the possibility of electrical coupling of the filaments have been produced in laboratory scale. The RRR of the copper stabilizer and J c properties have not degraded because of no metallurgical reactions between Cu and Mn, Nb-Ti and Mn. 7 refs., 9 figs., 4 tabs

Oral considerations of Kawasaki syndrome : a case report

OpenAIRE

Figueiredo, Márcia Cançado; Pires, Patrícia Duarte Simões; Silva, Daniel Demétrio Faustino da; Ouriques, Maurício Cernicchiaro; Squef, Rocío

2010-01-01

El objetivo del presente estudio es presentar un caso clínico y revisar la literatura existente sobre el Síndrome de Kawasaki (SK) tan frecuente en pacientes con necesidades especiales. Las características clínicas de esta patología se observan ya en niños muy jóvenes, en la gran mayoría de los casos menores de 5 años de edad. Esta es una patología que puede llevar al óbito, pues revela un compromiso cardíaco importante. Hay señales y síntomas en la cavidad oral en la fase aguda de la enferme...

Reactor operator: Training for the job while earning college credit

International Nuclear Information System (INIS)

Murdick, S.A.

1988-01-01

The nuclear industry is looking for ways to maximize the dollars spent to train licensed reactor operators and other personnel and, at the same time, upgrade their educational level. The prospects of college credit and/or degree requirements imposed by the US Nuclear Regulatory Commission have provided a significant driving force behind this search. The task is complicated, however, because shift schedules do not permit reactor operators to pursue higher education through the traditional classroom route, and the need for plant-specific training and requalification programs dictate against uniformly adapting college-based courses for training use. The National Program on Noncollegiate Sponsored Instruction (National PONSI) has been of considerable help to the nuclear industry in meeting these challenges. Through its college credit recommendation service, National PONSI has assessed the comparability of certain industry training activities to college-level instruction and has been instrumental in gaining academic recognition of these activities. The program has become a vital means for the industry to achieve its dual mission of preparing employees to successfully perform their jobs and providing them with ways to obtain college degrees in the shortest possible time

Reactor operator: Training for the job while earning college credit

Energy Technology Data Exchange (ETDEWEB)

Murdick, S.A.

1988-01-01

The nuclear industry is looking for ways to maximize the dollars spent to train licensed reactor operators and other personnel and, at the same time, upgrade their educational level. The prospects of college credit and/or degree requirements imposed by the US Nuclear Regulatory Commission have provided a significant driving force behind this search. The task is complicated, however, because shift schedules do not permit reactor operators to pursue higher education through the traditional classroom route, and the need for plant-specific training and requalification programs dictate against uniformly adapting college-based courses for training use. The National Program on Noncollegiate Sponsored Instruction (National PONSI) has been of considerable help to the nuclear industry in meeting these challenges. Through its college credit recommendation service, National PONSI has assessed the comparability of certain industry training activities to college-level instruction and has been instrumental in gaining academic recognition of these activities. The program has become a vital means for the industry to achieve its dual mission of preparing employees to successfully perform their jobs and providing them with ways to obtain college degrees in the shortest possible time.

Reactor training simulator for the Replacement Research Reactor (RRR)

International Nuclear Information System (INIS)

Etchepareborda, A; Flury, C.A; Lema, F; Maciel, F; Alegrechi, D; Damico, M; Ibarra, G; Muguiro, M; Gimenez, M; Schlamp, M; Vertullo, A

2004-01-01

The main features of the ANSTO Replacement Research Reactor (RRR) Reactor Training Simulator (RTS) are presented.The RTS is a full-scope and partial replica simulator.Its scope includes a complete set of plant normal evolutions and malfunctions obtained from the plant design basis accidents list.All the systems necessary to implement the operating procedures associated to these transients are included.Within these systems both the variables connected to the plant SCADA and the local variables are modelled, leading to several thousands input-output variables in the plant mathematical model (PMM).The trainee interacts with the same plant SCADA, a Foxboro I/A Series system.Control room hardware is emulated through graphical displays with touch-screen.The main system models were tested against RELAP outputs.The RTS includes several modules: a model manager (MM) that encapsulates the plant mathematical model; a simulator human machine interface, where the trainee interacts with the plant SCADA; and an instructor console (IC), where the instructor commands the simulation.The PMM is built using Matlab-Simulink with specific libraries of components designed to facilitate the development of the nuclear, hydraulic, ventilation and electrical plant systems models [es

NORA project offers unique reactor research and advanced training opportunities

International Nuclear Information System (INIS)

1961-01-01

An international program for reactor research and advanced training for a period of three years has been established in connection with the Norwegian critical assembly NORA. The aim of the project is to determine, through integral experiments, the basic reactor physics data for lattices moderated with light-water, heavy-water or mixtures of heavy and light water, with fuels of different sizes and spacing, three different enrichments and compositions. The objectives, programme, and facilities are described in details

Hitachi product data management system toward the 21st century by CALS approach

International Nuclear Information System (INIS)

Yoshinaga, Toshiaki; Kibushi, Haruo; Kitaur, Ayumu

1998-01-01

HIPDM21 (Hitachi Product Data Management System for the 21st century) is a comprehensive computer information management system which has been developed for the purpose of plant life cycle business support in terms of the electronics information exchange and sharing between the disciplines using the product data management technology. The system consists of core systems (Engineering Data Control System, Integrated Commodity Database system, and Document Management System) and business application systems. In the present development phase, the system is being enhanced to support CALS standards including EDT, SGML, and STEP, and to support information exchange and sharing with outside the company including clients, construction companies, and domestic/international vendors. (author)

Education and training at the Rensselaer Polytechnic Institute reactor critical facility

International Nuclear Information System (INIS)

Harris, D.R.

1989-01-01

The Rensselaer Polytechnic Institute (RPI) Reactor Critical Facility (RCF) has provided hands-on education and training for RPI and other students for almost a quarter of a century. The RCF was built in the 1950s by the American Locomotive Company (ALCO) as a critical facility in which to carry out experiments in support of the Army Package power Reactor (APPR) program. A number of APPRs were built and operated. In the middle 1960s, ALCO went out of business and provided the facility to RPI. Since that time, RPI has operated the RCF primarily in a teaching mode in the nuclear engineering department, although limited amounts of reactor research, activation analysis, and reactivity assays have been carried out as well. Recently, a U.S. Department of Energy (DOE) upgrade program supported refueling the RCF with 4.81 wt% enriched UO 2 high-density pellets clad in stainless steel rods. The use of these SPERT (F1) fuel rods in the RCF provided a cost-effective approach to conversion from high-enrichment bombgrade fuel to low-enrichment fuel. More important, however, is the fact that the new fuel is of current interest for light water power reactors with extended lifetime fuel. Thus, not only are critical reactor experiments being carried out on the fuel but, more importantly, the quality of the education and training has been enhanced

Investigation of slightly forced buoyant flow in a training reactor

International Nuclear Information System (INIS)

Legradi, G.; Aszodi, A.; Por, G.

2001-01-01

A measurement based on the temperature noise analysis method was carried out in the Training Reactor of the Budapest University of Technology and Economics. The main goals were the estimation of the flow velocity immediately above the reactor core and investigation of the thermal-hydraulical conditions of the reactor, mainly in the core. Subsequently 2D and 3D computations were carried out with the aid of the code CFX- 4.3. The main objective of the 2D calculation was to clarify the thermal-hydraulical conditions of the whole reactor tank with a reasonable computing demand. It was also necessary to accomplish 3D numerical investigations of the reactor core and the space above since three dimensional effects of the flow could only be studied in this way. In addition, obtaining certain boundary conditions of the 3D computations was another significant aim of the 2D investigations. It is important that the results of the noise analysis and the operational measuring system of the reactor gave us a basis for verifying our computations.(author)

Kawasaki disease in Sicily: clinical description and markers of disease severity

OpenAIRE

Maggio, M.; Corsello, G.; Prinzi, E.; Cimaz, R.

2016-01-01

Background Kawasaki disease (KD) is an acute systemic vasculitis of small and middle size arteries; 15-25 % of untreated patients and 5 % of patients treated with intravenous immunoglobulin (IVIG) develop coronary artery lesions (CAL). Many studies tried to find the most effective treatment in the management of resistant KD and to select the risk factors for CAL. Our data are assessed on children from west Sicily, characterized by a genetic heterogeneity. Methods We studied the clinical data ...

Training and teaching with SILOETTE reactor and associated simulators at the Nuclear Research Centre of Grenoble

International Nuclear Information System (INIS)

Destot, M.

1983-10-01

Thanks to its three reactors SILOE (35 MW), MELUSINE (8 MW) and SILOETTE (100 KW), the Reactor Department of the Nuclear Research Centre of Grenoble has gained a considerable experience in the operation and utilization of research and material testing reactors. Inside of this general framework, the Reactor Department of Grenoble has built up a training and teaching centre that has been permanently active since 1975, with the aim of satisfying the considerable needs arising from the development of electro-nuclear power stations. The course is mainly intended for engineers and technicians who will be responsible for running power stations. A thorough series of practical exercices, carried out in the SILOETTE training reactor and in a PWR or in a Gas Cooled Reactor Simulator, desmonstrates the application of the theorical courses and familiarises the trainees with the behaviour of reactors and power stations

Procalcitonin Levels in Patients with Complete and Incomplete Kawasaki Disease

Directory of Open Access Journals (Sweden)

Hwa Jin Cho

2013-01-01

Full Text Available Incomplete Kawasaki disease (iKD is considered to be a less complete form of Kawasaki disease (cKD, and several differences in the laboratory presentations of iKD and cKD have been noted. We investigated serum procalcitonin levels in patients with iKD, cKD, and other febrile diseases (a control group. Seventy-seven patients with cKD, 24 with iKD, and 41 controls admitted to our hospital from November 2009 to November 2011 were enrolled in the present study. We obtained four measurements of serum procalcitonin levels and those of other inflammatory markers from each patient. Samples were taken for analysis on the day of diagnosis (thus before treatment commenced; D0 and 2 (D2, 14 (D14, and 56 days (D56 after intravenous immunoglobulin infusion. We obtained control group data at D0. The mean D0 serum procalcitonin levels of cKD patients (0.71±1.36 ng/mL and controls (0.67±1.06 ng/mL were significantly higher than those of iKD patients (0.26±0.26 ng/mL (P=0.014 and P=0.041, resp.. No significant difference in mean procalcitonin level was evident among groups at any subsequent time. In conclusion, the serum procalcitonin level of patients with acute-stage cKD was significantly higher than that of iKD patients.

Setting-up of remote reactor LAB and tapping into CARRN for distance education and training in nuclear field

Energy Technology Data Exchange (ETDEWEB)

Park, Eugene [The Nelson Mandeal African Institute of Science and Technology, Arusha (Tanzania, United Republic of)

2013-07-01

For a developing country embarking on a research reactor project, building adequate human resource capacity is one of the biggest challenges. Tanzania has been considering a research reactor for some time. The success of future research reactor project impinges on vigorous education and training of necessary personnel to operate and fully utilize the facility. In Africa, underutilization of research reactors is a chronic issue. It is not only misuse of valuable resources but also poses potential safety and security concerns. To mitigate such concerns and to promote education and training, Central African Research Reactor Network (CARRN) was formed in June of 2011. Borrowing from Jordan's success, this paper presents customised curricula to take advantage of CARRN for distance education and training in nuclear field.

Setting-up of remote reactor LAB and tapping into CARRN for distance education and training in nuclear field

International Nuclear Information System (INIS)

Park, Eugene

2013-01-01

For a developing country embarking on a research reactor project, building adequate human resource capacity is one of the biggest challenges. Tanzania has been considering a research reactor for some time. The success of future research reactor project impinges on vigorous education and training of necessary personnel to operate and fully utilize the facility. In Africa, underutilization of research reactors is a chronic issue. It is not only misuse of valuable resources but also poses potential safety and security concerns. To mitigate such concerns and to promote education and training, Central African Research Reactor Network (CARRN) was formed in June of 2011. Borrowing from Jordan's success, this paper presents customised curricula to take advantage of CARRN for distance education and training in nuclear field

Nuclear reactor physics course for reactor operators

International Nuclear Information System (INIS)

Baeten, P.

2006-01-01

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

Reactor physics studies at the Zittau Training and research reactor ZLFR

Energy Technology Data Exchange (ETDEWEB)

Konschak, K.; Horche, W.; Honisch, H.; Berger, J. (Ingenieurhochschule Zittau (German Democratic Republic). Sektion Kraftwerksanlagenbau und Energieumwandlung); Doerschel, B. (Technische Univ., Dresden (German Democratic Republic). Sektion Physik)

1982-04-01

It is reported on experimental studies during the start-up period of the Zittau training and research reactor ZLFR. The critical mass obtained is in good agreement with the calculated value. It corresponds to a core charge of 90 fuel assemblies ECH-1. The shutdown reactivity of the safety rod and of the three control rods is 3.2% in total. The reactivity effects due to shuffling, internals, and configuration modifications as well as to intentional or unintentional changes in the operating conditions have been analyzed from the viewpoint of safe operation.

Radiation conditions at the training IRT-2000 and IR-100 reactors

International Nuclear Information System (INIS)

Fedorin, Eh.V.; Bronshtejn, I.Eh; Martynov, Yu.N.; Chistyakov, N.I.

1978-01-01

The experience is reviewed of radiation hygiene surveys and radiation safety provision during instructional processes on two training and research nuclear reactors of the IRT-2000 type (No. 1 and No. 2) and on an IR-200 reactor. From an analysis of individual dosimetry data the conclusion is made that the trainees and personnel are exposed mainly to external gamma-radiation and also, to a minor degree, to thermal neutrons and beta-radiation. It has been found that a high level of radiation safety is ensured on the training and research so that research and instruction activities are conducted at annual levels of exposure substantially lower than 0.5 rem in the case of trainees and 5 rem in the case of personnel

New control and safety rod unit for the training reactor of the Dresden Technical University

International Nuclear Information System (INIS)

Adam, E.; Schab, J.; Knorr, J.

1983-01-01

The extension of the experimental training of students at the training reactor AKR of the Dresden Technical University requires the reconstruction of the reactor with a new control and safety rod unit. The specific conditions at the AKR led to a new variant. Results of preliminary experiments, design and mode of operation of the first unit as well as hitherto gained operation experiences are presented. (author)

Digital control application for the advanced boiling water reactor

International Nuclear Information System (INIS)

Fennern, L.E.; Pearson, T.; Wills, H.D.; Swire Rhodes, L.; Pearson, R.L.

1986-01-01

The Advanced Boiling Water Reactor (ABWR) is a 1300 MWe class Nuclear Power Plant whose design studies and demonstration tests are being performed by the three manufacturers, General Electric, Toshiba and Hitachi, under requirement specifications from the Tokyo Electric Power Company. The goals are to apply new technology to the BWR in order to achieve enhanced operational efficiencies, improved safety measures and cost reductions. In the plant instrumentation and control areas, traditional analog control equipment and wire cables will be replaced by distributed digital microprocessor based control units communicating with each other and the control room over fiber optic multiplexed data buses

[Clinical features and course of Kawasaki disease in central Tunisia: a study about 14 cases collected over a period of three years (2000-2002)].

Science.gov (United States)

Chemli, Jalel; Kchaou, Habib; Amri, Fethi; Belkadhi, Adel; Essoussi, Ahmed Sahloul; Gueddiche, Neji; Harbi, Abdelaziz

2005-08-01

To analyze the clinical features and course of Kawasaki disease in central Tunisia. We studied retrospectively 14 cases of children with Kawasaki disease collected in tunisian center during three years (2000-2002). The study is about 11 boys and 3 girls (sex - ratio: 3.6/1) aged from 6 months to 8 years (mean age : 4 years). Twelve patients had at least 5 diagnostic criteria of the illness, the two others had an incomplete form. We noted cardiac complications in seven patients treated belatedly, beyond 10 days of progression, because of atypical clinical presentations. All patients had all a middle caliber coronary aneurysm that was complicated by a thrombus in three cases, associated with pericarditis and minimal mitral insufficiency in a case and with a cardiac rhythm disturbance (block of branch) in another case. Besides the cardiac complications, several other visceral manifestation could be noted: joint symptoms in five cases, GI tract symptomes in three cases, neuro-meningeal in two cases and urinary trad symptomes in two other cases. Specific treatment (aspirin with antiinflammatory dose and intravenous immune globulin (IVIG)) has been instituted in all patients. The course was favorable for 12 patients with fast regression of clinical manifestation and progressive normalisation of biologic values. Two patients did not respond to the initial IVIG treatment, and had to recense received an additional course of IGIV but without clinical nor biological improvement. These two patients were treated with corticosteroids. Cardiac lesions disappeared completely in all patients even for those with thrombosis and in patients with IVIG-resistant Kawasaki disease. Only one patient had kept neurologic sequellae: aphasia, bevavioral problemes and partial epilepsy. Kawasaki disease is not rare in our region. Incomplete or atypical presentations are frequent and are a source of diagnostic delay. Coronary aneurysm due to the delay of treatment often regresses even in patients

Technical Basis for Physical Fidelity of NRC Control Room Training Simulators for Advanced Reactors

Energy Technology Data Exchange (ETDEWEB)

Minsk, Brian S.; Branch, Kristi M.; Bates, Edward K.; Mitchell, Mark R.; Gore, Bryan F.; Faris, Drury K.

2009-10-09

The objective of this study is to determine how simulator physical fidelity influences the effectiveness of training the regulatory personnel responsible for examination and oversight of operating personnel and inspection of technical systems at nuclear power reactors. It seeks to contribute to the U.S. Nuclear Regulatory Commission’s (NRC’s) understanding of the physical fidelity requirements of training simulators. The goal of the study is to provide an analytic framework, data, and analyses that inform NRC decisions about the physical fidelity requirements of the simulators it will need to train its staff for assignment at advanced reactors. These staff are expected to come from increasingly diverse educational and experiential backgrounds.

Japanese scoring systems to predict resistance to intravenous immunoglobulin in Kawasaki disease were unreliable for Caucasian Israeli children.

Science.gov (United States)

Arane, Karen; Mendelsohn, Kerry; Mimouni, Michael; Mimouni, Francis; Koren, Yael; Simon, Dafna Brik; Bahat, Hilla; Helou, Mona Hanna; Mendelson, Amir; Hezkelo, Nofar; Glatstein, Miguel; Berkun, Yackov; Eisenstein, Eli; Aviel, Yonatan Butbul; Brik, Riva; Hashkes, Philip J; Uziel, Yosef; Harel, Liora; Amarilyo, Gil

2018-05-24

This study assessed the validity of using established Japanese risk scoring methods to predict intravenous immunoglobulin (IVIG) resistance to Kawasaki disease in Israeli children. We reviewed the medical records of 282 patients (70% male) with Kawasaki disease from six Israeli medical centres between 2004-2013. Their mean age was 2.5 years. The risk scores were calculated using the Kobayashi, Sano and Egami scoring methods and analysed to determine if a higher risk score predicted IVIG resistance in this population. Factors that predicted a lack of response to the initial IVIG dose were identified. We found that 18% did not respond to the first IVIG dose. The three scoring methods were unable to reliably predict IVIG resistance, with sensitivities of 23-32% and specificities of 67-87%. Calculating a predictive score that was specific for this population was also unsuccessful. The factors that predicted a lacked of response to the first IVIG dose included low albumin, elevated total bilirubin and ethnicity. The established risk scoring methods created for Japanese populations with Kawasaki disease were not suitable for predicting IVIG resistance in Caucasian Israeli children and we were unable to create a specific scoring method that was able to do this. This article is protected by copyright. All rights reserved. This article is protected by copyright. All rights reserved.

Design and Analysis of Thorium-fueled Reduced Moderation Boiling Water Reactors

Science.gov (United States)

Gorman, Phillip Michael

The Resource-renewable Boiling Water Reactors (RBWRs) are a set of light water reactors (LWRs) proposed by Hitachi which use a triangular lattice and high void fraction to incinerate fuel with an epithermal spectrum, which is highly atypical of LWRs. The RBWRs operate on a closed fuel cycle, which is impossible with a typical thermal spectrum reactor, in order to accomplish missions normally reserved for sodium fast reactors (SFRs)--either fuel self-sufficiency or waste incineration. The RBWRs also axially segregate the fuel into alternating fissile "seed" regions and fertile "blanket" regions in order to enhance breeding and leakage probability upon coolant voiding. This dissertation focuses on thorium design variants of the RBWR: the self-sufficient RBWR-SS and the RBWR-TR, which consumes reprocessed transuranic (TRU) waste from PWR used nuclear fuel. These designs were based off of the Hitachi-designed RBWR-AC and the RBWR-TB2, respectively, which use depleted uranium (DU) as the primary fertile fuel. The DU-fueled RBWRs use a pair of axially segregated seed sections in order to achieve a negative void coefficient; however, several concerns were raised with this multi-seed approach, including difficulty with controlling the reactor and unacceptably high axial power peaking. Since thorium-uranium fuel tends to have much more negative void feedback than uranium-plutonium fuels, the thorium RBWRs were designed to use a single elongated seed to avoid these issues. A series of parametric studies were performed in order to find the design space for the thorium RBWRs, and optimize the designs while meeting the required safety constraints. The RBWR-SS was optimized to maximize the discharge burnup, while the RBWR-TR was optimized to maximize the TRU transmutation rate. These parametric studies were performed on an assembly level model using the MocDown simulator, which calculates an equilibrium fuel composition with a specified reprocessing scheme. A full core model was

Quality of Life and Behavioral Functioning in Dutch Children with a History of Kawasaki Disease

NARCIS (Netherlands)

Tacke, Carline E.; Haverman, Lotte; Berk, Birgit M.; van Rossum, Marion A.; Kuipers, Irene M.; Grootenhuis, Martha A.; Kuijpers, Taco W.

2012-01-01

Objective The authors evaluated health-related quality of life (HRQOL) and behavioral functioning in patients with a history of Kawasaki disease (KD). Study design A cross-sectional study was conducted at a tertiary referral center for KD follow-up in 280 patients (mean age 8.6 years, 60.0% male).

New measuring and protection system at VR-1 training reactor

International Nuclear Information System (INIS)

Kropik, M.; Jurickova, M.

2006-01-01

The contribution describes the new measuring and protection system of the VR-1 training reactor. The measuring and protection system upgrade is an integral part of the reactor I and C upgrade. The new measuring and protection system of the VR-1 reactor consists of the operational power measuring and the independent power protection systems. Both systems measure the reactor power and power rate, initiate safety action if safety limits are exceeded and send data (power, power rate, status, etc.) to the reactor control system. The operational power measuring system is a full power range system that receives signal from a fission chamber. The signal is evaluated according to the reactor power either in the pulse or current mode. The current mode utilizes the DC current and Campbell techniques. The new independent power protection system operates in the two highest reactor power decades. It receives signals from a boron chamber and evaluates it in the pulse mode. Both systems are computer based. The operational power measuring and independent power protection systems are diverse - different types and location of chambers, completely different hardware, software algorithms for the power and power rate calculations, software development tools and teems for the software manufacturing. (author)

SILOETTE, a training centre for reactor physics at the Nuclear Research Centre of Grenoble

International Nuclear Information System (INIS)

Destot, M.

1983-10-01

The Reactor Department of Grenoble has created, based on Siloette, an activity of training in reactor physics, wich is running since 1975 to meet the important needs generated by the development of electronuclear power stations. Its essential goal is to provide an initiation to the basic physical phenomena which determine the operation of the reactors. For that purpose, a rather comprehensive program of practical works on reactor (SILOETTE) and on nuclear power station simulators (PWR, UNGG) is proposed besides lectures and conferences, general and specialized teaching on the reactor operation principle, kinetics, dynamics and thermics

A research reactor simulator for operators training and teaching

International Nuclear Information System (INIS)

De Carvalho, R. P.; Maiorino, J. R.

2006-01-01

This work describes a training simulator of Research Reactors (RR). The simulator is an interactive tool for teaching and operator training of the bases of the RR operation, reactor physics and thermal hydraulics. The Brazilian IEA-R1 RR was taken as the reference (default configuration). The implementation of the simulator consists of the modeling of the process and system (neutronics, thermal hydraulics), its numerical solution, and the implementation of the man-machine interface through visual interactive screens. The point kinetics model was used for the nuclear process and the heat and mass conservation models were used for the thermal hydraulic feed back in the average core channel. The heat exchanger and cooling tower were also modeled. The main systems were: the reactivity control system, including the automatic control, and the primary and secondary coolant systems. The Visual C++ was used to codes and graphics lay-outs. The simulator is to be used in a PC with Windows XP system. The simulator allows simulation in real time of start up, power maneuver, and shut down. (authors)

Myocardial performance and perfusion during exercise in patients with coronary artery disease caused by Kawasaki disease

International Nuclear Information System (INIS)

Paridon, S.M.; Ross, R.D.; Kuhns, L.R.; Pinsky, W.W.

1990-01-01

For a study of the natural history of coronary artery lesions after Kawasaki disease and their effect on myocardial blood flow reserve with exercise, five such patients underwent exercise testing on a bicycle. Oxygen consumption, carbon dioxide production, minute ventilation, and electrocardiograms were monitored continuously. Thallium-201 scintigraphy was performed for all patients. One patient stopped exercise before exhaustion of cardiovascular reserve but had no evidence of myocardial perfusion abnormalities. Four patients terminated exercise because of exhaustion of cardiovascular reserve; one had normal cardiovascular reserve and thallium scintiscans, but the remaining patients had diminished cardiovascular reserve. Thallium scintigrams showed myocardial ischemia in two and infarction in one. No patient had exercise-induced electrocardiographic changes. These results indicate that patients with residual coronary artery lesions after Kawasaki disease frequently have reduced cardiovascular reserve during exercise. The addition of thallium scintigraphy and metabolic measurements to exercise testing improved the detection of exercise-induced abnormalities of myocardial perfusion

Crystalline-Like Keratopathy after Intravenous Immunoglobulin Therapy with Incomplete Kawasaki Disease: Case Report and Literature Review

Directory of Open Access Journals (Sweden)

Elif Erdem

2013-01-01

Full Text Available A 7-year-old girl had presented with high body temperature and joint pain which continued for 3 days. Because of the prolonged history of unexplained fever, rash, bilateral nonpurulent conjunctival injection, oropharyngeal erythema, strawberry tongue, and extreme of age, incomplete Kawasaki disease was considered and started on an intravenous immunoglobulin infusion. Six days after this treatment, patient was referred to eye clinic with decreased vision and photophobia. Visual acuity was reduced to 20/40 in both eyes. Slit-lamp examination revealed bilateral diffuse corneal punctate epitheliopathy and anterior stromal haze. Corneal epitheliopathy seemed like crystal deposits. One day after presentation, mild anterior uveitis was added to clinical picture. All ocular findings disappeared in one week with topical steroid and unpreserved artificial tear drops. We present a case who was diagnosed as incomplete Kawasaki disease along with bilateral diffuse crystalline-like keratopathy. We supposed that unusual ocular presentation may be associated with intravenous immunoglobulin treatment.

Modern design and safety analysis of the University of Florida Training Reactor

International Nuclear Information System (INIS)

Jordan, K.A.; Springfels, D.; Schubring, D.

2015-01-01

Highlights: • A new safety analysis of the University of Florida Training Reactor is presented. • This analysis uses modern codes and replaces the NRC approved analysis from 1982. • Reduction in engineering margin confirms that the UFTR is a negligible risk reactor. • Safety systems are not required to ensure that safety limits are not breached. • Negligible risk reactors are ideal for testing digital I&C equipment. - Abstract: A comprehensive series of neutronics and thermal hydraulics analyses were conducted to demonstrate the University of Florida Training Reactor (UFTR), an ARGONAUT type research reactor, as a negligible risk reactor that does not require safety-related systems or components to prevent breach of a safety limit. These analyses show that there is no credible UFTR accident that would result in major fuel damage or risk to public health and safety. The analysis was based on two limiting scenarios, whose extremity bound all other accidents of consequence: (1) the large step insertion of positive reactivity and (2) the release of fission products due to mechanical damage to a spent fuel plate. The maximum step insertion of positive reactivity was modeled using PARET/ANL software and shows a maximum peak fuel temperature of 283.2 °C, which is significantly below the failure limit of 530 °C. The exposure to the staff and general public was calculated for the worst-case fission product release scenario using the ORIGEN-S and COMPLY codes and was shown to be 6.5% of the annual limit. Impacts on reactor operations and an Instrumentation & Control System (I&C) upgrade are discussed

Modern design and safety analysis of the University of Florida Training Reactor

Energy Technology Data Exchange (ETDEWEB)

Jordan, K.A., E-mail: kjordan@ufl.edu [University of Florida, 106 UFTR Bldg., PO Box 116400, Gainesville, FL 32611-6400 (United States); Springfels, D., E-mail: dspringfels@ufl.edu [University of Florida, 106 UFTR Bldg., PO Box 116400, Gainesville, FL 32611-6400 (United States); Schubring, D., E-mail: dlschubring@ufl.edu [University of Florida, 202 Nuclear Science Building, PO Box 118300, Gainesville, FL 32611-8300 (United States)

2015-05-15

Highlights: • A new safety analysis of the University of Florida Training Reactor is presented. • This analysis uses modern codes and replaces the NRC approved analysis from 1982. • Reduction in engineering margin confirms that the UFTR is a negligible risk reactor. • Safety systems are not required to ensure that safety limits are not breached. • Negligible risk reactors are ideal for testing digital I&C equipment. - Abstract: A comprehensive series of neutronics and thermal hydraulics analyses were conducted to demonstrate the University of Florida Training Reactor (UFTR), an ARGONAUT type research reactor, as a negligible risk reactor that does not require safety-related systems or components to prevent breach of a safety limit. These analyses show that there is no credible UFTR accident that would result in major fuel damage or risk to public health and safety. The analysis was based on two limiting scenarios, whose extremity bound all other accidents of consequence: (1) the large step insertion of positive reactivity and (2) the release of fission products due to mechanical damage to a spent fuel plate. The maximum step insertion of positive reactivity was modeled using PARET/ANL software and shows a maximum peak fuel temperature of 283.2 °C, which is significantly below the failure limit of 530 °C. The exposure to the staff and general public was calculated for the worst-case fission product release scenario using the ORIGEN-S and COMPLY codes and was shown to be 6.5% of the annual limit. Impacts on reactor operations and an Instrumentation & Control System (I&C) upgrade are discussed.

Transition of the Course Programs in the 40 Years History of Hitachi Institute of Technology

Science.gov (United States)

Miura, Osamu; Katsura, Koyo; Takahashi, Masahiko

In 2010, the Hitachi Institute of Technology reached the 40th anniversary. In the beginning, the institute stood at the product-out-oriented view point and carried out extensive technical education from basis to advanced technology. After the 1990s, transition of the business environment with the globalization caused that the needs of the engineer education required by the business sections have been transformed. As the result, the changes of needs have been reflected for course program of the institute. Nowadays, in addition to the conventional course programs, the engineer education programs for the business competency and human skill have also been focused.

The operating organization and the recruitment, training and qualification of personnel for research reactors. Safety guide

International Nuclear Information System (INIS)

2008-01-01

This Safety Guide provides recommendations on meeting the requirements on the operating organization and on personnel for research reactors. It covers the typical operating organization for research reactor facilities; the recruitment process and qualification in terms of education, training and experience; programmes for initial and continuing training; the authorization process for those individuals having an immediate bearing on safety; and the processes for their requalification and reauthorization

Training and qualification of licensed reactor operators at General Public Utilities Nuclear Corporation

International Nuclear Information System (INIS)

Long, R.L.; Coe, R.P.

1992-01-01

Following the Three Mile Island-2 (TMI-2) accident in 1979, the utility responsible for managing the facility has looked closely at the training and qualification of its reactor operators. Performance-based operator training programmes are now in place, as required by the United States National Academy for Nuclear Training. Operators also participate directly in the development of a professional code of behaviour. (UK)

Education and training activities at North Carolina State University's PULSTAR reactor

International Nuclear Information System (INIS)

Mayo, C.W.

1992-01-01

Research reactor utilization has been an integral part of the North Carolina State University's (NCSU's) nuclear engineering program since its inception. The undergraduate curriculum has a strong teaching laboratory component. Graduate classes use the reactor for selected demonstrations, experiments, and projects. The reactor is also used for commercial power reactor operator training programs, neutron radiography, neutron activation analysis (NAA), and sample and tracer activation for industrial short courses and services as part of the university's land grant mission. The PULSTAR reactor is a 1-MW pool-type reactor that uses 4% enriched UO 2 pellet fuel in Zircaloy II cladding. Standard irradiation facilities include wet exposure ports, a graphite thermal column, and a pneumatic transfer system. In the near term, general facility upgrades include the installation of signal isolation and computer data acquisition and display functions to improve the teaching and research interface with the reactor. In the longer term, the authors foresee studies of new core designs and the development of beam experiment design tools. These would be used to study modifications that may be desired at the end of the current core life and to undertake the development of new research instruments

The role of a small teaching reactor in education and training

International Nuclear Information System (INIS)

Bobek, L.M.; Mayer, J.A. Jr.

1992-01-01

It cannot be simply concluded that because an undergraduate nuclear engineering program has access to a higher power research reactor that the number of BS graduates will be proportionately larger than a program whose reactor operates at a much lower power level. What can be concluded is that although smaller in size and capability, low-power research reactors and the nuclear engineering programs they serve provide an important role in producing much-needed nuclear engineers and scientists at the undergraduate level. Designed and built by General Electric primarily as a teaching tool for nuclear engineering education, the nuclear reactor at Worcester Polytechnic Institute (WPI) first began operation in 1959. The reactor power level was upgraded from 1 to 10 kW in 1969, and its 20-yr operating license was renewed in 1983. With the support of DOE funds, the reactor was converted to low-enriched fuel in 1988. Under partial funding from the DOE University Reactor Instrumentation Program, the reactor control console will soon be replaced. Since a small research reactor is an ideal tool for providing basic and intermediate nuclear training, the incorporation of nuclear subjects into traditional disciplines will consequently enhance reactor facility usage. With its continued modernization, the WPI nuclear reactor facility will play a key role in meeting nuclear manpower needs while providing excellent and rewarding career opportunities for students in all disciplines for many years to come

Behaviors of chemical elements in the atmosphere, Kawasaki, Japan

International Nuclear Information System (INIS)

Oda, K.; Kikawada, Y.; Oi, T.

2008-01-01

A total of 19 elements in the samples of atmospheric deposition collected in Kawasaki, Japan, were determined by neutron activation analysis, ICPAES and flame photometry. The amounts of soil dust depositions were larger in springs and those of Sb and Zn depositions were larger in summers than in the other seasons. The values of the enrichment factors were higher for Sb and Zn than for the other elements determined throughout the sampling period. A factor analysis showed that the two elements were characterized as industrial components. Rubber products like tires that contain noncombustibles and rubber accelerators were a possible origin of high concentrations of Sb and Zn in the present samples. (author)

Atypical Kawasaki Disease Presenting as Intestinal Pseudo-obstruction

Directory of Open Access Journals (Sweden)

Mao-Meng Tiao

2006-01-01

Full Text Available Intestinal pseudo-obstruction in atypical Kawasaki disease (KD is rare. A boy aged 2 years and 6 months presented with a 7-day history of fever, coffee-ground vomit, and abdominal pain. Abdominal radiography and ultrasound showed a dilated duodenum. Peeling of the skin on his fingers and toes developed on hospitalization day 9. Echocardiogram revealed right and left coronary artery dilatation compatible with KD. He was treated with 2 g/kg intravenous immunoglobulin (IVIG, with rapid resolution of fever and relief of abdominal pain. Follow-up abdominal radiography and ultrasound showed improvement of bowel dilatation. This case illustrates that atypical KD can present with intestinal pseudo-obstruction. A high index of suspicion is required for early diagnosis, and prompt treatment with IVIG is recommended.

Training courses for the staff of the nuclear power station KRSKO conducted at the TRIGA reactor center in Ljubljana

International Nuclear Information System (INIS)

Pregl, G.; Najzer, M.

1976-01-01

The training program for the Nuclear Power Station Krsko was divided into two modules: fundamentals of nuclear engineering and specialized training according to duties that candidates are supposed to take at the power station. Basic training was organized at the TRIGA Reactor Center in Ljubljana in two different versions. The first version intended for plant operators and all engineers lasted for six months and included about 500 hours of classroom lessons and seminars and 31 laboratory experiments. The educational program was conventional. The following topics were covered: nuclear and atomic physics, reactor theory, reactor dynamics, reactor instrumentation and control, heat transfer in nuclear power plants, nuclear power plant systems, reactor materials, reactor safety, and radiation protection. Until now, two groups, consisting of 37 candidates altogether, have attended this basic course. Plans have been made to conduct two additional courses of about 20 students each for technicians other than operators. The program of this second version will be reduced, with the emphasis on reactor core physics and radiation protection. Classroom lessons will be strongly supported by laboratory experiments. (author)

Study on the present and future training of managers and operators for reactor facilities

International Nuclear Information System (INIS)

Hagemann, G.; Preuss, W.; Tietze, A.; Wuest, S.

1973-09-01

The study gives a survey on the training methods for the operating personnel of reactors in operation or under construction in the FRG and compares them with the training and testing methods of other countries, in particular the USA. (RW/AK) [de

Combined use of the RPI [Rensselaer Polytechnic Institute] reactor for training and critical experiments

International Nuclear Information System (INIS)

Harris, D.R.; Rohr, R.R.; Rodriguez-Vera, F.

1990-01-01

The Rensselaer Polytechnic Institute (RPI) reactor critical facility (RCF) has provided educational and research opportunities for RPI and other students for >25 yr. The RCF was built by the American Locomotive Company (ALCO) in the 1950s as a critical facility in support of the army package power reactor program, and, when ALCO went out of business in 1964, the RCF was acquired by RPI. Since that time, RPI has operated the RCF primarily in a teaching mode in the nuclear engineering department, although reactor research, activation analyses, and reactivity assays have been carried out as well. Until recently, the RCF was fueled by plates containing highly enriched uranium as a cermet in stainless steel. This highly enriched uranium (HEU) fuel was replaced recently by 4.81 wt% enriched UO 2 high-density pellets clad in stainless steel rods. The use of these SPERT (F1) fuel rods in the RCF provided a cost-effective method for conversion of the core from HEU to low-enriched uranium and for enhancement of the RCF training and research program. The RCF is the only facility in the United States that provides reactor training on a core containing fuel that is similar to that used in power industry light water reactors (LWRs). Moreover, the RCF is the only facility in the United States currently available for supplying critical experimental data in support of the LWR power industry. Thus, the RCF is in a unique position to carry out important training and research services consistent with RPI's nuclear engineering objectives

Reduced myocardial perfusion reserve in myocardium having coronary artery aneurysm of Kawasaki disease

International Nuclear Information System (INIS)

Yoon, S. N.; Lee, D. S.; Choi, J. Y.; Kil, H. R.; Jeong, Z. K.; Lee, M. C.; Ko, C. S.

1997-01-01

Kawasaki disease is a systemic vasculitis involving the coronary arteries at early childhood and cause coronary artery aneurysms and thrombotic occlusions. These coronary artery aneurysms were usually transformed later into stenotic or obstructive lesions, however, the majority of these aneurysms, even the giant ones, are known to be associated with normal epicardial coronary flow. Flow reserve is difficult to assess in aneurysmal arteries with echo or angiography. We performed this study to question if there are abnormalities in flow reserve in myocardial tissue with normal epicardial arterial flow on angiography in patients with Kawasaki disease, dipyridamole stress and rest Tc-99m-sestamibi SPECT were performed in 37 patients (28 boys, 9 girls, mean age 6.6 years). We compared SPECT findings with coronary angiography (CAG) findings in 21 patients who did both studies after finding abnormality on echocardiaography. On CAG, aneurysms were found in 26 arteries of 16 patients, i.e., 10 left main arteries, 6 left anterior descending arteries (LAD), 2 left circumflex arteries (LCX), and 8 right coronary arteries (RCA). Localized and segmental stenotic lesions were found in 11 arteries in 9 patients (LAD: 4, LCX: 1, RCA: 6). Eight of the 10 patients with aneurysms had no obvious stenosis. On stress-rest SPECT, 16(43%) out of 37 patients showed normal perfusion and the other 21(57%) showed reversible or persistent decrease. Among 11 stenotic artery territories, 3(27%) showed persistent and/or reversible perfusion defects. The other 8 were normal. Among 26 aneurysmal artery territories, 12 artery territories showe perfusion decrease. Three of the 5 patients with normal CAG showed persistent and/or transient perfusion defects. Among 14 artery territories with perfusion decrease in the 16 patients, 3(21%) could be localized to vascular territory having stenosis of supplying coronary arteries, 12(86%) were related to the coronary artery aneurysms. Two were not related to

Evidence of correlation between TGFBR2 gene expression mediated by NF-kB signaling pathways and Kawasaki disease in children.

Science.gov (United States)

Gao, Qinling; Yuan, Shuhua; Yuan, Dawei

2017-09-15

We explored the correlation between the TGFBR2 gene that is mediated by NF-kb signaling pathways and the pathogenesis of Kawasaki disease in children. In this study, 43 children with Kawasaki disease from April 2014 to January 2016 at our hospital were selected as the observation group, and 42 healthy children were selected as the control group. The mRNA expression levels of NF-kb gene and TGFBR2 gene in different groups were detected using fluorescence quantitative PCR. The protein expression levels of the NF-kb and TGFBR2 were detected using enzyme-linked immunosorbent assay (ELISA) in different groups. The expression levels of NF-kb and TGFBR2 in the observation group and the control group were detected using immunohistochemistry. Compared to the control group, the mRNA expression levels of NF-kb and TGFBR2 were 12.3 times and 27.5 times as high as those in the control group respectively and there were significant differences between the two groups (pkb and TGFBR2 in the control group (0.87±0.12, 1.25±0.18) ug/l and those in the observation group (3.27±0.17, 8.16±0.22) ug/l (pkB and TGFBR2 in children with Kawasaki disease were significantly higher than those in healthy subjects (pkB signaling pathways.

The prevention of coronary arterial abnormalities in Kawasaki disease: A meta-analysis of the corticosteroid effectiveness.

Science.gov (United States)

Yang, Tsung-Ju; Lin, Ming-Tai; Lu, Chun-Yi; Chen, Jong-Min; Lee, Ping-Ing; Huang, Li-Min; Wu, Mei-Hwan; Chang, Luan-Yin

2017-09-06

The use of corticosteroid in Kawasaki disease (KD) remains controversial among current guidelines. The objective of this study is to summarize the effectiveness and safety of corticosteroid to prevent coronary arterial lesions in Kawasaki disease, both as initial and rescue therapy. The Medline, EMBASE, Google scholar, Cochrane Central Register of Controlled Trials databases, ClinicalTrials.gov, and Japanese Institutional Repositories Online were searched for studies up to 31 March 2017. Studies that compared incidence of coronary artery lesions between regimens with corticosteroid and regimen without it in a well-defined controlled group were included. The incidence of coronary artery lesion was analyzed by meta-analysis. Nineteen studies published between 1999 and 2016 fulfilled eligibility criteria. There were 3591 patients included for analysis. There was a significant reduction in incidence of coronary artery lesions with usage of corticosteroid with a pooled odds ratio of 0.72 (95% CI 0.57-0.92; p = 0.01) than that without usage of corticosteroid. In general, a greater effect was seen in the patient received corticosteroid as initial and adjuvant therapy with intravenous immune globulin (pooled odds ratio 0.39, 95% CI 0.21-0.73, p = 0.007) than those who received corticosteroid as rescue therapy. The risk reduction was statistically significant in Japanese groups (OR 0.56, 95% CI 0.42-0.75 in fixed effects model) but not significant in non-Japanese groups (OR 1.45, 95% CI 0.91-2.30 in fixed effects model). We demonstrated an overall reduction in incidence of coronary artery lesions with the use of corticosteroid as initial and adjuvant treatment for Kawasaki disease. Copyright © 2017. Published by Elsevier B.V.

Team training using full-scale reactor coolant pump seal mock-ups

International Nuclear Information System (INIS)

McDonald, T.J.; Hamill, R.W.

1987-01-01

The use of full-scale reactor coolant pump (RCP) seal mock-ups has greatly enhanced Northeast Utilities' ability to effectively utilize the team training approach to technical training. With the advent of the Institute of Nuclear Power Operations accreditation come a new emphasis and standards for the integrated training of plant engineering personnel, maintenance mechanics, quality control personnel, and health physics personnel. The results of purchasing full-scale RCP mock-ups to pilot the concept of team training have far exceeded expectations and cost-limiting factors. The initial training program analysis identified RCP seal maintenance as a task that required training for maintenance department personnel. Due to radiation exposure considerations and the unavailability of actual plant equipment for training purposes, the decision was made to procure a mock-up of an RCP seal assembly and housing. This mock-up was designed to facilitate seal cartridge removal, disassembly, assembly, and installation, duplicating all internal components of the seal cartridge and housing area in exact detail

GE Hitachi's parts asset management solutions (PAMS)

International Nuclear Information System (INIS)

Varno, M.; Lancaster, K.; Detamore, B.; Dinh, H.; Danielsson, J.; Vitaback, F.

2014-01-01

To ensure operational excellence and improve plant reliability, GE Hitachi Nuclear Energy (GEH) has partnered with its customers to develop PARTS Asset Management Solutions (PAMS). PAMS is a comprehensive set of services that enable plants to proactively manage inventory, obtain after-market replacement parts quickly, and resolve obsolescence issues, ensuring operation of equipment is maintained. PAMS includes: - Electronics Exchange Service Program (EESP) - On-demand exchange service program for GE electronics parts that guarantees rapid shipment of parts, results in cost savings and eliminates all obsolescence risk. - Engineering Services (ES) - Service that finds replacement electronics parts for customers encountering obsolescence. - System Assessment Report (SAR) - Comprehensive, customised report for customer systems that provides all information needed to minimise part availability risk. - Inventory Management (IM) - Visual application based on OEM drawings and decades of industry operational experience that enables customers to proactively identify obsolescence and inventory management issues. - Material Solutions (MS) - Fixed price and lead time model that allows the customer to set-up blanket contracts or purchase orders for obtaining needed parts with a focus on reduced overall cycle time. This paper will provide an overview of PAMS and showcase a case study of the PAMS Digitized deployment for an existing GEH customer. (authors)

[Development of the community mental health system and activities of the community mental health team in Kawasaki City].

Science.gov (United States)

Ito, Masato

2012-01-01

Since the 1960s, Kawasaki City has been leading the nation in its efforts regarding community mental health practices. Public institutions such as the Psychiatric Rehabilitation Center in the central area of the city and the Mental Health and Welfare Center in the southern area have mainly developed the psychiatric rehabilitation system. However, since 2000, new mental health needs have emerged, as the target of mental health and welfare services has been diversified to include people with developmental disorders, higher brain dysfunction, or social withdrawal, in addition to those with schizophrenia. Therefore, Kawasaki City's plan for community-based rehabilitation was drawn up, which makes professional support available for individuals with physical, intellectual, and mental disabilities. As the plan was being implemented, in 2008, the Northern Community Rehabilitation Center was established by both the public and private sectors in partnership. After the community mental health teams were assigned to both southern and northern areas of the city, the community partnership has been developed not only for individual support but also for other objectives that required the partnership. Takeshima pointed out that the local community should be inclusive of the psychiatric care in the final stage of community mental health care in Japan. Because of the major policies regarding people with disabilities, the final stage has been reached in the northern area of Kawasaki City. This also leads to improvement in measures for major issues in psychiatry, such as suicide prevention and intervention in psychiatric disease at an early stage.

Technical features of steel structure construction by Kawasaki Steel; Kawasaki Seitetsu no kokozo gijutsu no tokucho

Energy Technology Data Exchange (ETDEWEB)

Kaneko, T.; Urata, I.; Okata, S. [Kawasaki Steel Corp., Tokyo (Japan)

1996-03-01

In the steel structure technology of Kawasaki Steel, the joint technique (e.g., welding) is added to them while developing or improving the products that meet the social needs as a material supplier. Moreover, the execution technique that manufactures materials or constructs them as an integrated structure, the structural analysis that conforms to the function and application of a structure, and the design technique on dynamic properties or durability such as earthquake resistance, fatigue, and corrosion resistance are synthetically expanded for engineering. In this paper, a building steel frame, non-residence building, bridge, and harbor structure as steel structure in the building and construction fields were described for each structure genre. The structural technology of a building steel frame is summarized to the products of pillar materials. An earthquake brace, using a dead soft steel, with high earthquake energy absorption capability and a damping wall were also developed. The design and execution technique of a large roof was systematized. The exchange technique of a road bridge RC floor and the technique of an unstiffened suspension bridge for pipeline were developed. A new technique was also developed for a suspension monorail track and offshore structure. 30 refs., 5 figs.

A simulator-based nuclear reactor emergency response training exercise.

Science.gov (United States)

Waller, Edward; Bereznai, George; Shaw, John; Chaput, Joseph; Lafortune, Jean-Francois

Training offsite emergency response personnel basic awareness of onsite control room operations during nuclear power plant emergency conditions was the primary objective of a week-long workshop conducted on a CANDU® virtual nuclear reactor simulator available at the University of Ontario Institute of Technology, Oshawa, Canada. The workshop was designed to examine both normal and abnormal reactor operating conditions, and to observe the conditions in the control room that may have impact on the subsequent offsite emergency response. The workshop was attended by participants from a number of countries encompassing diverse job functions related to nuclear emergency response. Objectives of the workshop were to provide opportunities for participants to act in the roles of control room personnel under different reactor operating scenarios, providing a unique experience for participants to interact with the simulator in real-time, and providing increased awareness of control room operations during accident conditions. The ability to "pause" the simulator during exercises allowed the instructors to evaluate and critique the performance of participants, and to provide context with respect to potential offsite emergency actions. Feedback from the participants highlighted (i) advantages of observing and participating "hands-on" with operational exercises, (ii) their general unfamiliarity with control room operational procedures and arrangements prior to the workshop, (iii) awareness of the vast quantity of detailed control room procedures for both normal and transient conditions, and (iv) appreciation of the increased workload for the operators in the control room during a transient from normal operations. Based upon participant feedback, it was determined that the objectives of the training had been met, and that future workshops should be conducted.

Utilization of the Dalat Research Reactor for Radioisotope Production, Neutron Activation Analysis, Research and Training

International Nuclear Information System (INIS)

Nguyen Nhi Dien; Duong Van Dong; Cao Dong Vu; Nguyen Xuan Hai

2013-01-01

The Dalat Nuclear Research Reactor (DNRR) is a 500 kW pool type reactor loaded with a mixed core of HEU (36% enrichment) and LEU (19.75% enrichment) fuel assemblies. The reactor is used as a neutron source for the purposes of radioisotopes production, neutron activation analysis, basic and applied research and training. The reactor is operated mainly in continuous runs of 108 hours for cycles of 3–4 weeks for the above mentioned purposes. The current status of safety, operation and utilization of the reactor is given and some aspects for improvement of commercial products and services of the DNRR are also discussed in this paper. (author)

Major Refurbishment of the University of Florida Training Reactor

International Nuclear Information System (INIS)

Joradn, Kelly; Berglund, Matthew; Shea, Brian

2013-01-01

The research reactor fleet is aging with few replacements being built. At the same time the technology for refurbishment of the older reactors has advanced well beyond that of currently installed equipment. The disparity between new and old technology results in an inability to find simple replacements for the older, highly integrated components. The lack of comprehensive guidance for digital equipment adds to the technical problems of installing individual replacement parts. Up to this point, no U. S. facilities have attempted a complete modernization effort because of the time commitment, financial burden, and licensing required for a total upgrade. The University of Florida Training Reactor is tackling this problem with a replacement of nearly all of the major facility sub-systems, including electrical distribution, reactor controls, nuclear instrumentation, security, building management, and environmental controls. This approach offers increased flexibility over the piece-by-piece replacement method by leveraging modern control systems based on global standards and capable of good data interchange with higher levels of redundancy. The UFTR reviewed numerous technologies to arrive at the final system architecture and this 'clean-slate' installation methodology. It is this concept of total system replacement and strict use of modular, open-standards technology that has allowed for a facility design that will be easy to install, maintain, and build upon over time

Major Refurbishment of the University of Florida Training Reactor

Energy Technology Data Exchange (ETDEWEB)

Joradn, Kelly; Berglund, Matthew; Shea, Brian [Univ., of Florida, Florida (United States)

2013-07-01

The research reactor fleet is aging with few replacements being built. At the same time the technology for refurbishment of the older reactors has advanced well beyond that of currently installed equipment. The disparity between new and old technology results in an inability to find simple replacements for the older, highly integrated components. The lack of comprehensive guidance for digital equipment adds to the technical problems of installing individual replacement parts. Up to this point, no U. S. facilities have attempted a complete modernization effort because of the time commitment, financial burden, and licensing required for a total upgrade. The University of Florida Training Reactor is tackling this problem with a replacement of nearly all of the major facility sub-systems, including electrical distribution, reactor controls, nuclear instrumentation, security, building management, and environmental controls. This approach offers increased flexibility over the piece-by-piece replacement method by leveraging modern control systems based on global standards and capable of good data interchange with higher levels of redundancy. The UFTR reviewed numerous technologies to arrive at the final system architecture and this 'clean-slate' installation methodology. It is this concept of total system replacement and strict use of modular, open-standards technology that has allowed for a facility design that will be easy to install, maintain, and build upon over time.

Predicting Coronary Artery Aneurysms in Kawasaki Disease at a North American Center: An Assessment of Baseline z Scores.

Science.gov (United States)

Son, Mary Beth F; Gauvreau, Kimberlee; Kim, Susan; Tang, Alexander; Dedeoglu, Fatma; Fulton, David R; Lo, Mindy S; Baker, Annette L; Sundel, Robert P; Newburger, Jane W

2017-05-31

Accurate risk prediction of coronary artery aneurysms (CAAs) in North American children with Kawasaki disease remains a clinical challenge. We sought to determine the predictive utility of baseline coronary dimensions adjusted for body surface area ( z scores) for future CAAs in Kawasaki disease and explored the extent to which addition of established Japanese risk scores to baseline coronary artery z scores improved discrimination for CAA development. We explored the relationships of CAA with baseline z scores; with Kobayashi, Sano, Egami, and Harada risk scores; and with the combination of baseline z scores and risk scores. We defined CAA as a maximum z score (zMax) ≥2.5 of the left anterior descending or right coronary artery at 4 to 8 weeks of illness. Of 261 patients, 77 patients (29%) had a baseline zMax ≥2.0. CAAs occurred in 15 patients (6%). CAAs were strongly associated with baseline zMax ≥2.0 versus Baseline zMax ≥2.0 had a C statistic of 0.77, good sensitivity (80%), and excellent negative predictive value (98%). None of the risk scores alone had adequate discrimination. When high-risk status per the Japanese risk scores was added to models containing baseline zMax ≥2.0, none were significantly better than baseline zMax ≥2.0 alone. In a North American center, baseline zMax ≥2.0 in children with Kawasaki disease demonstrated high predictive utility for later development of CAA. Future studies should validate the utility of our findings. © 2017 The Authors. Published on behalf of the American Heart Association, Inc., by Wiley.

Innovations and Enhancements for a Consortium of Big-10 University Research and Training Reactors. Final Report

International Nuclear Information System (INIS)

Brenizer, Jack

2011-01-01

The Consortium of Big-10 University Research and Training Reactors was by design a strategic partnership of seven leading institutions. We received the support of both our industry and DOE laboratory partners. Investments in reactor, laboratory and program infrastructure, allowed us to lead the national effort to expand and improve the education of engineers in nuclear science and engineering, to provide outreach and education to pre-college educators and students and to become a key resource of ideas and trained personnel for our U.S. industrial and DOE laboratory collaborators.

Assessment of coronary artery aneurysms in paediatric patients with Kawasaki disease by multidetector row CT angiography: feasibility and comparison with 2D echocardiography

International Nuclear Information System (INIS)

Chu, W.C.W.; Lam, W.W.M.; Mok, G.C.F.; Yam, M.; Sung, R.Y.T.

2006-01-01

Transthoracic ECHO is the locally accepted method for coronary surveillance of patients with Kawasaki disease but it may have limited visualization in the older child. To assess the feasibility of multidetector CT (MDCT) angiography in the follow-up of coronary artery aneurysms in children with previous Kawasaki disease. Six children (5 boys, 1 girl; mean age 11.5 years) with known Kawasaki disease and coronary artery involvement underwent CT coronary angiography using 16-detector MDCT. The visualized lengths and diameter of all coronary segments were measured. The number, size and location of coronary artery aneurysms were recorded and compared with recent ECHO. Twelve coronary artery aneurysms (seven saccular, five fusiform) were identified by MDCT angiography. One saccular aneurysm at the junction of the distal right coronary artery and posterior descending artery was not detected by ECHO while the remaining six in proximal segments were detected by both modalities. Two of five fusiform aneurysms were not detected by ECHO due to their small sizes. Excellent agreement was found between CT and ECHO for maximal diameter and length of the visualized aneurysms. MDCT angiography accurately defines coronary artery aneurysms. It is more sensitive for detecting aneurysms at distal coronary segments and fusiform aneurysms of small size

Upgrade of VR-1 training reactor I and C

International Nuclear Information System (INIS)

Kropik, M.; Matejka, K.; Chab, V.

2003-01-01

The contribution describes the upgrade of the VR-1 training reactor I and C (Instrumentation and Control). The reactor was put into operation in the 1990, and its I and C seems to be obsolete now. The new I and C utilises the same digital technology as the old one. The upgrade has been done gradually during holidays in order not to disturb the reactor utilisation during teaching and training. The first stage consisted in the human-machine interface and the control room upgrade in 2001. A new operator's desk, displays, indicators and buttons were installed. Completely new software and communication interface to the present I and C were developed. During the second stage in 2002, new control rod drivers and safety circuits were installed. The rod motors were replaced and necessary mechanical changes on the control rod mechanism, induced by the utilisation of the new motor, were done. The new safety circuits utilise high quality relays with forced contacts to guarantee high reliability of their operation. The third stage, the control system upgrade is being carried out now. The new control system is based on an industrial PC mounted in a 19 inch crate. The operating system of the PC is the Microsoft Windows XP with the real time support RTX of the VentureCom Company. A large amount of work has been devoted to the software requirements to specify all dependencies, modes and permitted actions, safety measures, etc. The Department took an active part in the setting of software requirements and later in verification and validation of the software and the whole control system. Finally, a new protection system consisting of power measuring and power protection channels will be installed in 2004 or 2005. (author)

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

Science.gov (United States)

Syarip; Po, L. C. C.

2018-05-01

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

Analytical hierarchy process for the selection of nuclear reactors for Mexico

International Nuclear Information System (INIS)

Martin-Del-Campo, C.; Nelson, P. F.; Francois, J. L.

2008-01-01

The Analytical Hierarchy Process (AHP) was applied as a decision making technique to select the next new nuclear power reactor for Mexico. The main objective is to select the most suitable nuclear reactor technology for Mexico, to start the bidding process within one or two years, and the reactor to initiate commercial operation by 2016. Four alternatives which comply with these specific restrictions were compared: the Advanced Boiling Water Reactor (AB WR) from General Electric, Hitachi and Toshiba; the European Pressurized Water Reactor (ERR) from AREVA; the pressurized water reactor - advanced passive plant, AP1000, from Westinghouse; and the Economic Simplified Boiling Water Reactor (ESBWR) from General Electric. The evaluation criteria include economic and safety indicator, some of them quantitative and others qualitative. Additional complexity to the solution of this problem is that there are stakeholders that can be involved in the definition of the evaluation criteria and in the definition of relative importance between them, according to each stakeholder interests or benefits. Only the two main stakeholders were considered, these are the Federal Commission of Electricity (Comision Federal de Electricidad, CFE) and the National Commission of Nuclear Safety and Safeguards (Comision Nacional de Seguridad Nuclear y Salvaguardias, CNSNS). Considering the evaluation criteria used and the authors' assessment of their importance, the ABWR was ranked the highest. Sensitivity analyses were performed in order to define the most suitable reactor for the needs of Mexico. (authors)

Experience in the recruitment, organization and training of operations and maintenance personnel for the Malaysian research reactor

International Nuclear Information System (INIS)

Jamal Khair Ibrahim.

1983-01-01

The TRIGA Reactor located at the Tun Ismail Atomic Research Centre (PUSPATI) Complex is owned and operated by the Nuclear Energy Unit of the Prime Minster's Department. The operations and maintenance personnel are part and parcel of the national civil service organization. As such, the requirement and remuneration of these personnel are handled by a central federal government personnel management agency in common with personnel from other federal government agencies. In addition, the reactor is the first and only one in Malaysia, a developing country, which is the process of committing herself towards a nuclear power programme. These factors coupled with the absence of an independent reactor operator licensing agency posed unique problems in the recruitment, organization, training and licensing of operations personnel for the facility. The paper discusses these factors and their bearing on the recruitment, training, licensing and career development prospects of the PUSPATI TRIGA Reactor operators. (author)

Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Culbert, W.H.

1985-10-01

This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliance with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit

Health related quality of life and perceptions of child vulnerability among parents of children with a history of Kawasaki disease

NARCIS (Netherlands)

van Oers, Hedy A.; Tacke, Carline E.; Haverman, Lotte; Kuipers, Irene M.; Maurice-Stam, Heleen; Kuijpers, Taco W.; Grootenhuis, Martha A.

2014-01-01

Kawasaki disease (KD) is an acute paediatric vasculitis. The psychosocial consequences of this sudden illness for parents are unknown. This study aimed to evaluate health related quality of life (HRQOL) and parental perceptions of child vulnerability (PPCV) in parents of children with KD, and to

Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Culbert, W.H.

1985-10-01

This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliance with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit.

Plant Engineering and Construction System with Knowledge Management: A Case Study in NPP Construction in Hitachi-GE NE

International Nuclear Information System (INIS)

Mochida, T.; Hamamoto, M.; Nakamitsu, N.

2016-01-01

Full text: Hitachi-GE Nuclear Energy, Ltd. (HGNE) has more than 40 years BWR plants construction experience. The company continues to develop plant engineering system and plant construction systems based on the experience and the lessons learned. Currently, these systems are integrated in a variety of knowledge bases using the latest information technology (IT). Their performance is continuously validated in the recent NPP constructions. Typical examples are shown as case studies for knowledge management. These plant engineering and construction management systems are essential to achieve the on-time and on-budget-goals in NPP construction projects. (author

Injury to Akamatsu (Pinus densiflora Sieb. et Zucc. ) forest in the vicinity of the smelting works at Hitachi

Energy Technology Data Exchange (ETDEWEB)

Okanoue, M

1958-03-01

In the summer of 1965, smoke from a smelter at Hitachi caused injury to a national forest approximately one to three km distant. The smelter had been equipped with control devices and no previous injuries had been reported. An investigation of meteorological conditions at the time of the emission revealed the presence of a temperature inversion between Mt. Kamimine (594 m) and Sukegawa (52 m). However, these inversions are not uncommon in the area. Presumably, poisonous gas was emitted from the smelter chimney as a result of equipment malfunction just at the time of unfavorable meteorological conditions.

Role of Antioxidants in Horse Serum-mediated Vasculitis in Swine: Potential Relevance to Early Treatment in Mitigation of Coronary Arteritis in Kawasaki Disease.

Science.gov (United States)

Philip, Saji; Lee, Wen-Chuan; Cherian, Kotturathu Mammen; Wu, Mei-Hwan; Lue, Hung-Chi

2017-08-01

Horse serum-induced immune complex coronary vasculitis in swine is the first experimental model to mimic most of the pictures of Kawasaki disease. Immune complex mechanism has been implicated as one of the possible mechanisms in the pathogenesis of vasculitis in Kawasaki disease. Antioxidants have a significant role in the reduction of cardiovascular diseases in both human and animal studies. We tried giving vitamins A, E, and C to treat immune complex vasculitis, in the hope of mitigating coronary vasculitis in Kawasaki disease. Our study group consisted of 30 pure bred male piglets of 2-3 months of age, and they were divided into test and control groups. The test (AEC) group (n = 20) received two doses of horse serum, 10 mL (0.65 g protein)/kg body weight at 5-day intervals, and oral vitamins A, E, and C once daily for 14 days. The control group (n = 10) was further divided into the saline group (n = 3) receiving two doses of normal saline and the horse serum group (n = 7) receiving two doses of horse serum at 5-day intervals. Piglets were observed for the rashes and coronary artery dimensions. Both the AEC and the control horse serum group developed rashes after horse serum infusions, but the AEC group developed significantly fewer rashes, and no rashes were seen in the saline group. The control horse serum group (mean ± standard deviation = 2.13 ± 0.72) showed significant coronary artery dilatation, whereas there was no significant dilatation in the AEC group (mean ± standard deviation = 0.81 ± 0.58) or the control saline group (p = 0.002). Serum sickness is a prototype of immune complex vasculitis, and the severity can be ameliorated with antioxidants. A trial of therapeutic dosages of vitamins A, E, and C in acute phase of Kawasaki disease, may be effective in mitigation of coronary artery lesion in addition to intravenous immunoglobulin and aspirin. Copyright © 2017. Published by Elsevier B.V.

Plant maintenance and advanced reactors issue, 2008

Energy Technology Data Exchange (ETDEWEB)

Agnihotri, Newal [ed.

2009-09-15

The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: Technologies of national importance, by Tsutomu Ohkubo, Japan Atomic Energy Agency, Japan; Modeling and simulation advances brighten future nuclear power, by Hussein Khalil, Argonne National Laboratory, Energy and desalination projects, by Ratan Kumar Sinha, Bhabha Atomic Research Centre, India; A plant with simplified design, by John Higgins, GE Hitachi Nuclear Energy; A forward thinking design, by Ray Ganthner, AREVA; A passively safe design, by Ed Cummins, Westinghouse Electric Company; A market-ready design, by Ken Petrunik, Atomic Energy of Canada Limited, Canada; Generation IV Advanced Nuclear Energy Systems, by Jacques Bouchard, French Commissariat a l'Energie Atomique, France, and Ralph Bennett, Idaho National Laboratory; Innovative reactor designs, a report by IAEA, Vienna, Austria; Guidance for new vendors, by John Nakoski, U.S. Nuclear Regulatory Commission; Road map for future energy, by John Cleveland, International Atomic Energy Agency, Vienna, Austria; and, Vermont's largest source of electricity, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovation article is titled Intelligent monitoring technology, by Chris Demars, Exelon Nuclear.

Annual progress report of the University of Florida Training Reactor September 1, 1979-August 31, 1980

International Nuclear Information System (INIS)

Diaz, N.J.

1980-11-01

Reported are: reactor operation, modifications, maintenance and tests, changes to technical specifications and standard operating procedures, radioactive releases and environmental surveillance, and training utilization

First conceptual design of the experimental multi-purpose high temperature reactor

Energy Technology Data Exchange (ETDEWEB)

Tsunoda, T [Fuji Electric Co. Ltd., Tokyo (Japan)

1976-02-01

A part of the multi-purpose high temperature reactor (VHTR) was designed by the First Atomic Power Industry Group (FAPIG). Both Fuji Electric Co., Ltd. and Kawasaki Heavy Industries, Ltd. of the FAPIG group took charge of the design of main parts of the reactor Kobe Steel, Ltd., Ebara Manufacturing Co., Ltd., Shimizu Construction Co., Ltd. and the Nuclear Fuel Corp. have associated with this group. The reactor system includes a nuclear reactor and two cooling loops provided through intermediate heat exchangers in order to utilize the heat of helium gas delivered from the reactor outlet at 1,000 deg C. One is a reformer loop to produce the reducing gas for steel manufacture. The other is a testing loop for a reducing gas heater and a gas turbine. These loops transfer heat of about 25 MW at 930 deg C at rated capacity. The reformer can supply the reducing gas equivalent to the production of 100 tons per day sponge iron. A housing of the reactor is composed of a primary steel container, internal concrete and a secondary container made of reinforced concrete. The construction is based on the following principles. (1) For the very high temperature portion at 1,000 deg C, a non-metallic material such as graphite should be used. (2) The metallic construction shall be cooled with return gas below 400 deg C. (3) The steel pressure vessel shall be employed. (4) The design shall be based on the existing gas furnace.

Realizing CO2 emission reduction through industrial symbiosis: A cement production case study for Kawasaki

OpenAIRE

Hashimoto, Shizuka; Fujita, Tsuyoshi; Geng, Yong; Nagasawa, Emiri

2010-01-01

This article is one effort to examine the present and potential performances of CO2 emission reduction though industrial symbiosis by employing a case study approach and life cycle CO2 analysis for alternative industrial symbiosis scenarios. As one of the first and the best-known eco-town projects, Kawasaki Eco-town was chosen as a case study area. First, the current industrial symbiosis practices in this area are introduced. To evaluate the potential of reducing the total CO2 emission throug...

Simulators and their use in the training of CEGB reactor operations engineers

International Nuclear Information System (INIS)

Madden, V.J.; Tompsett, P.A.

1988-01-01

The development of simulators in the Central Electricity Generating Board's nuclear power training are traced, and, in describing the overall training programme of an advanced gas-cooled reactor operations engineer, the contribution made by a range of simulation devices from concept through to full-scope replica simulators is indicated. The capabilities of today's simulators are such that they are also making other contributions to the commissioning and safe operation of nuclear power plants. They are being successfully used for ergonomic and procedure validation work and the testing and commissioning of software for automatic control systems, and data and alarm processing systems. (author)

Lack of association between infection with a novel human coronavirus (HCoV), HCoV-NH, and Kawasaki disease in Taiwan

NARCIS (Netherlands)

Chang, Luan-Yin; Chiang, Bor-Luen; Kao, Chuan-Liang; Wu, Mei-Hwan; Chen, Pei-Jer; Berkhout, Ben; Yang, Hui-Ching; Huang, Li-Min

2006-01-01

We investigated whether infection with a novel human coronavirus (HCoV), called "New Haven coronavirus" (HCoV-NH)--which is similar to and likely represents the same species as another novel HCoV, HCoV-NL63--is associated with Kawasaki disease (KD) in Taiwan. Fifty-three patients with KD were

Computer modeling of the dynamic processes in the Maryland University Training Reactor - (MUTR)

International Nuclear Information System (INIS)

White, Bernard H. IV; Ebert, David

1988-01-01

The simulator described in this paper models the behaviour of the Maryland University Training Reactor (MUTR). The reactor is a 250 kW, TRIGA reactor. The computer model is based on a system of five primary equations and eight auxiliary equations. The primary equations consist of the prompt jump approximation, a heat balance equation for the fuel and the moderator, and iodine and xenon buildup equations. For the comparison with the computer program, data from the reactor was acquired by using a personal computer (pc) which contained a Strawberry Tree data acquisition Card, connected to the reactor. The systems monitored by the pc were: two neutron detectors, fuel temperature, water temperature, three control rod positions and the period meter. The time differenced equations were programmed in the basic language. It has been shown by this paper, that the MUTR power rise from low power critical to high power, can be modelled by a relatively simple computer program. The program yields accurate agreement considering the simplicity of the program. The steady state error between the reactor and computer power is 4.4%. The difference in steady state temperatures, 112 deg. C and 117 deg. C, of the reactor and computer program, respectively, also yields a 4.5% error. Further fine tuning of the coefficients will yield higher accuracies

Genusa Bepu methodologies for the safety analysis of BWRs; Metodologias Bepu de Genusa para el analisis de seguridad de reactores BWR

Energy Technology Data Exchange (ETDEWEB)

Trueba, M.; Garcia, J.; Goodson, C.; Ibarra, L.

2016-08-01

This article describes the BEPU methodologies developed by General Electric-Hitachi (GEH) for the evaluation of the BWR reactor safety analysis based on the TRACG best-estimate code. These methodologies are applicable to a wide range of events, operational transients (AOO), anticipated transients without scram (ATWS), loss of coolant accidents (LOCA) and instability events; to different BWR types operating commercially. General Electric (GE( designs and other vendors, including Generation III+ESBWR; to the new operation strategies, and to all types of BWR fuel. Their application achieves, among other benefits, a better understanding of the overall plant response and an improvement in margins to the operating limits; thus, the increase of flexibility in reactor operation and reduction in generation costs. (Author)

Septated pericarditis associated with Kawasaki disease: a brief case report.

Science.gov (United States)

Sonçaği, Arzu; Devrim, Ilker; Karagöz, Tevfik; Dilber, Embiya; Celiker, Alpay; Ozen, Seza; Seçmeer, Gülten

2007-01-01

Kawasaki disease (KD) is primarily the systemic vasculitis of childhood that affects mainly the medium-sized arteries, such as the coronary arteries. KD is the leading cause of acquired heart disease, whereas the incidence of rheumatic fever has declined. The most serious complication is coronary artery involvement. Among the children with KD who developed cardiac complications, pericarditis is a rare complication, with an incidence of 0.07%. We report our experience in a 5.5-year-old child with KD complicated with aneurysm of the left anterior descendant coronary artery and septated pericardial effusion, which has not been reported in the literature. The pericardial effusion disappeared very dramatically with intravenous immunoglobulin (IVIG) therapy. We would like to point out that septated pericardial effusion in cases of KD do not need any further therapy other than IVIG and high-dose acetylsalicylic acid.

Domestic manufacturing and reliability improvement of reactor water recirculation equipment

International Nuclear Information System (INIS)

Kobayashi, Hidekazu; Oi, Masao; Shida, Toichi; Yokomori, Takashi

1982-01-01

The reactor coolant recirculation system is one of the important systems to control the reactor output in BWR nuclear power plants. Its components require high reliability and maintainability as well as controllability. For many Japanese nuclear power plants, recirculation pumps, fluid couplings and others have been imported so far. Hitachi Ltd. has established a domestic manufacturing organization through the development and test of these equipment. The fundamental design conditions for these equipment are the improvement of the rate of utilization of plant facility, the capability to follow load, and output power stability. In this paper, the specifications, the investigation of moment of inertia and the design features of recirculation pumps, driving motors and variable frequency power supply systems are described. The paper also reports on the combination test implemented to evaluate the recirculation system. The combination test includes the test using water rheostat for the power source facility and the loading test for a recirculation pump. The application of those system equipment to an actual plant was analyzed and evaluated on a basis of the test data obtained. The result showed that the equipment can achieve the rate of change of reactor power of 30%/min. Those equipment have been employed for No. 2 reactor plant of the Fukushima No. 2 Nuclear Power Station, the Tokyo Electric Power Co., Inc. (Wakatsuki, Y.)

Special course for global nuclear human resource development in cooperation with Hitachi-GE nuclear energy in Tokyo institute of technology

International Nuclear Information System (INIS)

Ujita, H.; Futami, T.; Saito, M.; Murata, F.; Shimizu, M.

2012-01-01

Many Asian countries are willing to learn Japanese nuclear power plants experiences, and are interested in introducing nuclear power generation to meet their future energy demand. Special course for Global Nuclear Human Resource Development was established in April, 2011 in the Department of Nuclear Engineering at Graduate School of Tokyo Institute of Technology in cooperation with Hitachi-GE Nuclear Energy. Purpose of the special course is to develop global nuclear engineers and researchers not only in the Tokyo Institute of Technology but also in the educational institutes of Southeast Asian countries

Kawasaki Disease with Retropharyngeal Edema following a Blackfly Bite

Directory of Open Access Journals (Sweden)

Toru Watanabe

2014-01-01

Full Text Available We describe a patient with Kawasaki disease (KD and retropharyngeal edema following a blackfly bite. An 8-year-old boy was referred to our hospital because of a 3-day-history of fever and left neck swelling and redness after a blackfly bite. Computed tomography of the neck revealed left cervical lymph nodes swelling with edema, increased density of the adjacent subcutaneous tissue layer, and low density of the retropharyngeum. The patient was initially presumed to have cervical cellulitis, lymphadenitis, and retropharyngeal abscess. He was administered antibiotics intravenously, which did not improve his condition. The patient subsequently exhibited other signs of KD and was diagnosed with KD and retropharyngeal edema. Intravenous immunoglobulin therapy and oral flurbiprofen completely resolved the symptoms and signs. A blackfly bite sometimes incites a systemic reaction in humans due to a hypersensitive reaction to salivary secretions, which may have contributed to the development of KD in our patient.

Recurrent Kawasaki disease: USA and Japan.

Science.gov (United States)

Maddox, Ryan A; Holman, Robert C; Uehara, Ritei; Callinan, Laura S; Guest, Jodie L; Schonberger, Lawrence B; Nakamura, Yosikazu; Yashiro, Mayumi; Belay, Ermias D

2015-12-01

Descriptive epidemiologic studies of recurrent and non-recurrent Kawasaki disease (KD) may identify other potentially important differences between these illnesses. Data from the USA and Japan, the Centers for Disease Control and Prevention (CDC) national KD surveillance(1984-2008) and the 17th Japanese nationwide survey (2001-2002), respectively, were analyzed to examine recurrent KD patients <18 years of age meeting the CDC KD case or atypical KD case definition. These patients were compared with non-recurrent KD patients. Of the 5557 US KD patients <18 years of age during 1984-2008, 97 (1.7%) were identified as having had recurrent KD. Among the US Asian/Pacific Islander KD patients, 3.5% had recurrent KD, which was similar to the percentage identified among KD patients (3.5%) in the Japanese survey. Compared with non-recurrent KD patients, KD patients [with recurrent KD] were more likely to be older, fulfill the atypical KD case definition, and have coronary artery abnormalities (CAA) despite i.v. immunoglobulin (IVIG) treatment. Differences in the age, race, and frequency of CAA exist between recurrent and non-recurrent KD patients. The increased association of CAA with recurrent KD suggests that more aggressive treatment strategies in conjunction with IVIG may be indicated for the second episode of KD. © 2015 Japan Pediatric Society.

Training simulator for nuclear power plant reactor control model and method

International Nuclear Information System (INIS)

Czerbuejewski, F.R.

1975-01-01

A description is given of a method and system for the real-time dynamic simulation of a nuclear power plant for training purposes, wherein a control console has a plurality of manual and automatic remote control devices for operating simulated control rods and has indicating devices for monitoring the physical operation of a simulated reactor. Digital computer means are connected to the control console to calculate data values for operating the monitoring devices in accordance with the control devices. The simulation of the reactor control rod mechanism is disclosed whereby the digital computer means operates the rod position monitoring devices in a real-time that is a fraction of the computer time steps and simulates the quick response of a control rod remote control lever together with the delayed response upon a change of direction

CAI and training system for the emergency operation procedure in the advanced thermal reactor, FUGEN

International Nuclear Information System (INIS)

Kozaki, T.; Imanaga, K.; Nakamura, S.; Maeda, K.; Sakurai, N.; Miyamoto, M.

2003-01-01

In the Advanced Thermal Reactor (ATR ) of the JNC, 'FUGEN', a symptom based Emergency Operating Procedure (EOF) was introduced in order to operate Fugen more safely and it became necessary for the plant operators to master the EOF. However it took a lot of time for the instructor to teach the EOP to operators and to train them. Thus, we have developed a Computer Aided Instruction (CAI) and Training System for the EOP, by which the operators can learn the EOP and can be trained. This system has two major functions, i.e., CAI and training. In the CAI function, there are three learning courses, namely, the EOP procedure, the simulation with guidance and Q and A, and the free simulation. In the training function, all of necessary control instruments (indicators, switches, annunciators and so forth) and physics models for the EOP training are simulated so that the trainees can be trained for all of the EOPs. In addition, 50 kinds of malfunction models are installed in order to perform appropriate accident scenarios for the EOP. The training of the EOP covers the range from AOO (Anticipated Operational Occurrence) to Over-DBAs (Design Based Accidents). This system is built in three personal computers that are connected by the computer network. One of the computers is expected to be used for the instructor and the other two are for the trainees. The EOP is composed of eight guidelines, such as 'Reactor Control' and 'Depression and Cooling', and the operation screens which are corresponded to the guidelines are respectively provided. According to the trial, we have estimated that the efficiency of the learning and the training would be improved about 30% for the trainee and about 75% for the instructor in the actual learning and training. (author)

Nuclear Capacity Building through Research Reactors

International Nuclear Information System (INIS)

2017-01-01

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

Physical security at research reactors

International Nuclear Information System (INIS)

Clark, R.A.

1977-01-01

Of the 84 non-power research facilities licensed under 10 CFR Part 50, 73 are active (two test reactors, 68 research reactors and three critical facilities) and are required by 10 CFR Part 73.40 to provide physical protection against theft of SNM and against industrial sabotage. Each licensee has developed a security plan required by 10 CFR Part 50.34(c) to demonstrate the means of compliance with the applicable requirements of 10 CFR Part 73. In 1974, the Commission provided interim guidance for the organization and content of security plans for (a) test reactors, (b) medium power research and training reactors, and (c) low power research and training reactors. Eleven TRIGA reactors, with power levels greater than 250 kW and all other research and training reactors with power levels greater than 100 kW and less than or equal to 5,000 kW are designated as medium power research and training reactors. Thirteen TRIGA reactors with authorized power levels less than 250 kW are considered to be low power research and training reactors. Additional guidance for complying with the requirements of 73.50 and 73.60, if applicable, is provided in the Commission's Regulatory Guides. The Commission's Office of Inspection and Enforcement inspects each licensed facility to assure that an approved security plan is properly implemented with appropriate procedures and physical protection systems

Multimedia Course on Nuclear Reactors Physics, Application to a Tailored On the Job Training Course

International Nuclear Information System (INIS)

Dies, Javier

2014-01-01

In order to improve education and training quality, a Multimedia on Nuclear Reactor Physics has been developed. In some institutions, this course is called Fundamentals of Nuclear Reactor Operation. Nowadays, this multimedia has about 800 slides and the text is in Spanish, English, French and Russian. Until now about 126 institutions from 53 countries have applied for the multimedia. The teacher uses the multimedia during his lectures. Students use it at home to study this course

IAEA Workshop (Training Course) on Codes and Standards for Sodium Cooled Fast Reactors. Working Material

International Nuclear Information System (INIS)

2010-01-01

The training course consisted of lectures and Q&A sessions. The lectures dealt with the history of the development of Design Codes and Standards for Sodium Cooled Fast Reactors (SFRs) in the respective country, the detailed description of the current design Codes and Standards for SFRs and their application to ongoing Fast Reactor design projects, as well as the ongoing development work and plans for the future in this area. Annex 1 contains the detailed Workshop program

Development of a training simulator to operators of the IEA-R1 research reactor

International Nuclear Information System (INIS)

Carvalho, Ricardo Pinto de

2006-01-01

This work reports the development of a Simulator for the IEA-R1 Research Reactor. The Simulator was developed with Visual C++ in two stages: construction of the mathematics models and development and configuration of graphics interfaces in a Windows XP executable. A simplified modeling was used for main physics phenomena, using a point kinetics model for the nuclear process and the energy and mass conservation laws in the average channel of the reactor for the thermal hydraulic process. The dynamics differential equations were solved by using finite differences through the 4th order Runge- Kutta method. The reactivity control, reactor cooling, and reactor protection systems were also modeled. The process variables are stored in ASCII files. The Simulator allows navigating by screens of the systems and monitoring tendencies of the operational transients, being an interactive tool for teaching and training of IEA-R1 operators. It also can be used by students, professors, and researchers in teaching activities in reactor and thermal hydraulics theory. The Simulator allows simulations of operations of start up, power maneuver, and shut down. (author)

FCGR2A Promoter Methylation and Risks for Intravenous Immunoglobulin Treatment Responses in Kawasaki Disease

Directory of Open Access Journals (Sweden)

Ho-Chang Kuo

2015-01-01

Full Text Available Kawasaki disease (KD is characterized by pediatric systemic vasculitis of an unknown cause. The low affinity immunoglobulin gamma Fc region receptor II-a (FCGR2A gene was reported to be involved in the susceptibility of KD. DNA methylation is one of the epigenetic mechanisms that control gene expression; thus, we hypothesized that methylation status of CpG islands in FCGR2A promoter associates with the susceptibility and therapeutic outcomes of Kawasaki disease. In this study, 36 KD patients and 24 healthy subjects from out-patient clinic were recruited. Eleven potential methylation sites within the targeted promoter region of FCGR2A were selected for investigation. We marked the eleven methylation sites from A to K. Our results indicated that methylation at the CpG sites G, H, and J associated with the risk of KD. CpG sites B, C, E, F, H, J, and K were found to associate with the outcomes of IVIG treatment. In addition, CpG sites G, J, and K were predicted as transcription factors binding sites for NF-kB, Myc-Max, and SP2, respectively. Our study reported a significant association among the promoter methylation of FCGR2A, susceptibility of KD, and the therapeutic outcomes of IVIG treatment. The methylation levels of CpG sites of FCGR2A gene promoter should be an important marker for optimizing IVIG therapy.

Necessity of research reactors

International Nuclear Information System (INIS)

Ito, Tetsuo

2016-01-01

Currently, only three educational research reactors at two universities exist in Japan: KUR, KUCA of Kyoto University and UTR-KINKI of Kinki University. UTR-KINKI is a light-water moderated, graphite reflected, heterogeneous enriched uranium thermal reactor, which began operation as a private university No. 1 reactor in 1961. It is a low power nuclear reactor for education and research with a maximum heat output of 1 W. Using this nuclear reactor, researches, practical training, experiments for training nuclear human resources, and nuclear knowledge dissemination activities are carried out. As of October 2016, research and practical training accompanied by operation are not carried out because it is stopped. The following five items can be cited as challenges faced by research reactors: (1) response to new regulatory standards and stagnation of research and education, (2) strengthening of nuclear material protection and nuclear fuel concentration reduction, (3) countermeasures against aging and next research reactor, (4) outflow and shortage of nuclear human resources, and (5) expansion of research reactor maintenance cost. This paper would like to make the following recommendations so that we can make contribution to the world in the field of nuclear power. (1) Communication between regulatory authorities and business operators regarding new regulatory standards compliance. (2) Response to various problems including spent fuel measures for long-term stable utilization of research reactors. (3) Personal exchanges among nuclear experts. (4) Expansion of nuclear related departments at universities to train nuclear human resources. (5) Training of world-class nuclear human resources, and succession and development of research and technologies. (A.O.)

Annual progress report of the University of Florida Training Reactor, September 1, 1981-August 31, 1982

International Nuclear Information System (INIS)

Diaz, N.J.; Vernetson, W.G.

1982-11-01

The University of Florida Training Reactor's overall utilization for the past reporting year has decreased by about 50% compared to the previous year, approaching the low levels of utilization characteristic of the previous two reporting years ending in August 1979 and August 1980 respectively. The energy generation also continues to be far below average historical levels and represents a drop of nearly 50% from the improved level of the previous year. The UFTR continues to operate with an outstanding safety record and in full compliance with regulatory requirements. The reactor and associated facilities continue to maintain a high in-state visibility and strong industry relationship. It is hoped that more indirect industry training will be accomplished in the upcoming year

Equipment for neutron measurements at VR-1 Sparrow training reactor

International Nuclear Information System (INIS)

Kolros, Antonin; Huml, Ondrej; Kos, Josef

2008-01-01

Full text: The VR-1 Sparrow training reactor is the experimental nuclear facility especially employed for education and teaching of students from different technical universities in the Czech Republic and other countries. Since 2005 the uniform all-purpose devices EMK310 have been used for measurement at reactor laboratory with different type of gas filled neutron detectors. The neutron detection system are employed for reactivity measurement, control rod calibration, critical experiment, study of delayed neutrons, study of nuclear reactor dynamics and study of detection systems dead time. The small dimension isotropic detectors are especially used for measurement of thermal neutron flux distribution inside the reactor core. The EMK-310 is a high performance, portable, three-channel fast amplitude analyzer designed for counting applications. It was developed for nuclear applications and made in close co-operation with firm TEMA Ltd. The precise rack eliminates electromagnetic disturbance and contains the control unit and four modules. The modules of high voltage supply and amplifier for gas filled detectors or scintillation probes are used in basic configuration. Software is tailored specifically to the reactor measurement and allows full online control. For applications involving the study of signals that may vary with the time, example study of delayed neutrons or nuclear reactor dynamics, the EMK-310 provides a Multichannel Scaling (MCS) acquisition mode. MCS dwell time can be set from 2 ms. Now, the new generation of digital multichannel analyzers DA310 is introduced. They have similarly attributes as EMK310 but the output information of unipolar signals from detector is more complete. The pipeline A/D converter with field programmable gate array (FPGA) is the hearth of the DA310 device. The resolution is 12 bits (4096 channels); the sample frequency is 80 MHz. The application for the neutron noise analysis is supposed. The correction method for non linearity

Development of natural circulation small and medium sized boiling water reactor: HSBWR-600

International Nuclear Information System (INIS)

Miki, Minoru; Horiuchi, Tetsuo; Yoshimoto, Yuichiro; Sumida, Isao; Murase, Michio; Akita, Minoru; Niino, Tsuyoshi

1988-01-01

In nuclear power generation, the development of large reactors has been promoted as the main energy source in Japan. However, world economy entered low growth age, and the growth of electric power demand slowed down. Accordingly, attention has been paid to the medium and small reactors that can cope with whatever needs by serializing their types in addition to the nuclear power plants of medium output matching to electric power demand. In order to cope with these new needs, the economical efficiency of medium and small reactors must be as close as possible to that of large reactors, and as the countermeasures to the demerits due to small size, those must be made into the plants having simplified systems and the safety easily acceptable to public. Hitachi Ltd. plans to develop the natural circulation type medium and small BWRs of 600 NWe output class, HSBWR-600, on the basis of the nuclear power plant technology based on the rich results of design and operation of BWRs obtained so far, and to rank them as one of the BWR series. The target of their development design, the circumstance of their development, the core design and the thermo-hydraulic characteristics, the reactor pressure vessel and in-core structures, the safety design, system design, building layout and the evaluation are reported. (Kako, I.)

The final report of ''on-the-job training'' on the CANDU reactor

International Nuclear Information System (INIS)

Kim, D.H.; Koh, B.J.

1983-01-01

This is the final Report for the technical ''on-the-job traning'' for the Wolsung CANDU nuclear power plant which is the first Pressurized Heavy Water Reactor setting up in Korea. The technical ''on-the-job traning'' was established to increase the capability for the nuclear safety evaluation in order to contribute the future safe operation of the CANDU nuclear power plant. The training has been excuted through three level courses as elementary, intermediate and ''on-the-job training'' at Wolsung power plant. The elementary course was introduction to the CANDU basics and fundamentals. The intermediate course was the more advanced course, and the detailed concepts and engineering explanations of the CANDU system had been instructed. The third course was the ''on-the-job training'' at the Wolsung plant site, which was the most emphasized course during the project. (Author)

An independent safety assessment of Department of Energy nuclear reactor facilities: Training of operating personnel and personnel selection

International Nuclear Information System (INIS)

Drain, J.F.

1981-02-01

This study has been prepared for the Department of Energy's Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee. Its purpose is to provide the Committee with background information on, and assessment of, the selection, training, and qualification of nuclear reactor operating personnel at DOE-owned facilities

Design of subjects training on reactor simulator and feasibility study - toward the empirical evaluation of interface design concept

International Nuclear Information System (INIS)

Yamaguchi, Y.; Furukawa, H.; Tanabe, F.

1998-01-01

On-going JAERI's project for empirical evaluation of the ecological interface design concept was first described. The empirical evaluation is planned to be proceeded through three consecutive steps; designing and actual implementation of the interface on reactor simulator, verification of the interface created, and the validation by the simulator experiment. For conducting the project, three different experimental resources are prerequisite, that are, data analysis method for identifying the operator's strategies, experimental facility including reactor simulator, and experimental subjects or subjects training method. Among the three experimental resources, subjects training method was recently designed and a simulator experiment was earned out in order to examine the feasibility of the designed training method. From the experiment and analysis of the experimental records, we could conclude that it is feasible that the experimental subjects having an appropriate technical basis can gain the sufficient competence for evaluation work of the interface design concept by using the training method designed. (author)

Summary report of the 7th reduced-moderation water reactor workshop

International Nuclear Information System (INIS)

Akie, Hiroshi; Nabeshima, Kunihiko; Uchikawa, Sadao

2005-08-01

As a research on the future innovative water reactor, the development of Reduced-Moderation Water Reactors (RMWRs) has been performed in Japan Atomic Energy Research Institute (JAERI). The workshop on RMWRs is aiming at information exchange between JAERI and other organizations such as universities, laboratories, utilities and vendors, and has been held every year since 1998. The 7th workshop was held on March 5, 2004 under the joint auspices of JAERI and North Kanto branch of Atomic Energy Society of Japan. The program of the workshop was composed of 5 lectures and an overall discussion time. The workshop started with the lecture by JAERI on the status and future program of PMWR research and development, followed by the two presentations by JAERI and Japan Nuclear Cycle Development Institute, respectively, on the investigation and evaluation of water cooled reactor in Feasibility Study Program on Commercialized Fast Reactor Systems. The lectures were also made on the Japan's nuclear fuel cycle and scenarios for RMWRs deployment by JAERI, and on the next generation reactor development activity by Hitachi, Ltd. The main subjects of the overall discussion time were Na cooled fast reactor, deployment effects of RMWRs and the future plan of the RMWR research and development. This report includes the original papers presented at the workshop and summaries of the questions and answers for each lecture, as well as of the discussion time. In addition in the Appendices, there are included presentation handouts of each lecture, program of the workshop and the participants list. (author)

Urinary Colorimetric Sensor Array and Algorithm to Distinguish Kawasaki Disease from Other Febrile Illnesses.

Directory of Open Access Journals (Sweden)

Zhen Li

Full Text Available Kawasaki disease (KD is an acute pediatric vasculitis of infants and young children with unknown etiology and no specific laboratory-based test to identify. A specific molecular diagnostic test is urgently needed to support the clinical decision of proper medical intervention, preventing subsequent complications of coronary artery aneurysms. We used a simple and low-cost colorimetric sensor array to address the lack of a specific diagnostic test to differentiate KD from febrile control (FC patients with similar rash/fever illnesses.Demographic and clinical data were prospectively collected for subjects with KD and FCs under standard protocol. After screening using a genetic algorithm, eleven compounds including metalloporphyrins, pH indicators, redox indicators and solvatochromic dye categories, were selected from our chromatic compound library (n = 190 to construct a colorimetric sensor array for diagnosing KD. Quantitative color difference analysis led to a decision-tree-based KD diagnostic algorithm.This KD sensing array allowed the identification of 94% of KD subjects (receiver operating characteristic [ROC] area under the curve [AUC] 0.981 in the training set (33 KD, 33 FC and 94% of KD subjects (ROC AUC: 0.873 in the testing set (16 KD, 17 FC. Color difference maps reconstructed from the digital images of the sensing compounds demonstrated distinctive patterns differentiating KD from FC patients.The colorimetric sensor array, composed of common used chemical compounds, is an easily accessible, low-cost method to realize the discrimination of subjects with KD from other febrile illness.

Research reactor job analysis - A project description

International Nuclear Information System (INIS)

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

Augmented TLR2 Expression on Monocytes in both Human Kawasaki Disease and a Mouse Model of Coronary Arteritis

OpenAIRE

Lin, I-Chun; Kuo, Ho-Chang; Lin, Ying-Jui; Wang, Feng-Shen; Wang, Lin; Huang, Shun-Chen; Chien, Shao-Ju; Huang, Chien-Fu; Wang, Chih-Lu; Yu, Hong-Ren; Chen, Rong-Fu; Yang, Kuender D.

2012-01-01

BACKGROUND: Kawasaki disease (KD) of unknown immunopathogenesis is an acute febrile systemic vasculitis and the leading cause of acquired heart diseases in childhood. To search for a better strategy for the prevention and treatment of KD, this study compared and validated human KD immunopathogenesis in a mouse model of Lactobacillus casei cell wall extract (LCWE)-induced coronary arteritis. METHODS: Recruited subjects fulfilled the criteria of KD and were admitted for intravenous gamma globul...

Application of JAERI research reactors to education

International Nuclear Information System (INIS)

Ogawa, Shigeru; Morozumi, Minoru

1987-01-01

At the dawning of the atomic age in Japan, training on reactor operation and reactor engineering experiments has been started in 1958 using JRR-1 (a 50 kW water boiler type reactor with liquid fuel), which was the first research reactor in Japan. The role of the training has been transferred to JRR-4 (a 3500 kW swimming pool type reactor with ETR type fuel) since 1969 due to the decommission of JRR-1. The training courses which have been held are: JRR-1 Short-Term Course for Operation (1958 ∼ 1963) General Course (1961 ∼ ) Reactor Engineering Course (1976 ∼ ) Training Course in Nuclear Technology (International course)(1986 ∼ ). And individual training concerning research reactors for the participants of scientist exchange program sponsored by Science and Technology Agency and of bilateral agreement have been initiated in 1985. The graduates of these courses work as staff members in various fields in nuclear industry. (author)

Magnetic analysis including the field due to vacuum vessel eddy currents in the Hitachi Tokamak (HT-2)

International Nuclear Information System (INIS)

Abe, Mitsushi; Takeuchi, Kazuhiro; Fukumoto, Hideshi; Otsuka, Michio

1989-01-01

A magnetic analysis to determine plasma surface position is applied to the magnetic data of the Hitachi Tokamak (HT-2). The analysis takes account of toroidal eddy currents on the vacuum vessel wall. Magnetic probes in HT-2 are placed on both sides of the wall (plasma side and outside), making it possible to determine magnitudes of eddy currents which flow in the toroidal direction. The magnitudes of the coil currents and eddy currents are determined so as to reproduce the measured magnetic fields, and to reconstruct flux surfaces and plasma surface are reconstructed. Taking into account the eddy currents, the determination errors of the plasma surface position are reduced by up to 1/2.3 during start-up and terminating phases, compared with the case without eddy currents. (author)

Training simulator for advanced gas-cooled reactor (AGR) shutdown sequence equipment

International Nuclear Information System (INIS)

Shankland, J.P.; Nixon, G.L.

1978-01-01

Successful shutdown of nuclear plant is of prime importance for both safety and economic reasons and large sums of money are spent on equipment to make shutdowns fully automatic, thus removing the possibility of operator errors. While this aim can largely be realized, one must consider the possibility of automatic equipment or plant failures when operators are required to take manual action, and off-line training facilities should be available to operating staff to minimize the risk of incorrect actions being taken. This paper presents the practice adopted at Hunterston 'B' Nuclear Power Station to solve this problem and concerns the computer-based training simulator for the Reactor Shutdown Sequence Equipment (RSSE) which was commissioned in January 1977. The plant associated with shutdown is briefly described and the reasoning which shows the need for a simulator is outlined. The paper also gives details of the comprehensive facilities available on the simulator and goes on to describe the form that shutdown training takes and the experience gained at this time. (author)

Recent technology for BWR operator training simulators

International Nuclear Information System (INIS)

Sato, Takao; Hashimoto, Shigeo; Kato, Kanji; Mizuno, Toshiyuki; Asaoka, Koichi.

1990-01-01

As one of the important factors for maintaining the high capacity ratio in Japanese nuclear power stations, the contribution of excellent operators is pointed out. BWR Operation Training Center has trained many operators using two full scope simulators for operation training modeling BWRs. But in order to meet the demands of the recent increase of training needs and the upgrading of the contents, it was decided to install the third simulator, and Hitachi Ltd. received the order to construct the main part, and delivered it. This simulator obtained the good reputation as its range of simulation is wide, and the characteristics resemble very well those of the actual plants. Besides, various new designs were adopted in the control of the simulator, and its handling became very easy. Japanese nuclear power plants are operated at constant power output, and the unexpected stop is very rare, therefore the chance of operating the plants by operators is very few. Accordingly, the training using the simulators which can simulate the behavior of the plants with computers, and can freely generate abnormal phenomena has become increasingly important. The mode and positioning of the simulators for operation training, the full scope simulator BTC-3 and so on are reported. (K.I.)

Preparing the construction of a school reactor

International Nuclear Information System (INIS)

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.)

Recurrent Kawasaki disease, United States and Japan

Science.gov (United States)

Maddox, Ryan A.; Holman, Robert C.; Uehara, Ritei; Callinan, Laura S.; Guest, Jodie L.; Schonberger, Lawrence B.; Nakamura, Yosikazu; Yashiro, Mayumi; Belay, Ermias D.

2015-01-01

Background Descriptive epidemiologic studies of recurrent and non-recurrent Kawasaki disease (KD) may identify other potentially important differences between these illnesses. Methods Data from the United States and Japan, the Centers for Disease Control and Prevention (CDC) national KD surveillance (1984–2008) and the 17th Japanese nationwide survey (2001–2002), respectively, were analyzed to examine recurrent KD patients <18 years of age meeting the CDC KD case or atypical KD case definition. These patients were compared to non-recurrent KD patients. Results Of the 5557 US KD patients <18 years of age during 1984–2008, 97 (1.7%) were identified as having had recurrent KD. Among the US Asian/Pacific Islander KD patients, 3.5% had recurrent KD, which was similar to the percentage identified among KD patients (3.5%) in the Japanese survey. Compared to non-recurrent KD patients, KD patients experiencing a recurrent KD episode were more likely to be older, fulfill the atypical KD case definition, and have coronary artery abnormalities (CAA) despite IVIG treatment. Conclusions Differences in the age, race, and frequency of CAA exist between recurrent and non-recurrent KD patients. The increased association of CAA with recurrent KD suggests that more aggressive treatment strategies in conjunction with IVIG may be indicated for the second episode of KD. PMID:26096590

Ulysse, mentor reactor

International Nuclear Information System (INIS)

Bouquin, B.; Rio, I.; Safieh, J.

1997-01-01

On July 23, 1961, the ULYSSE reactor began its first power rise. Designed at that time to train nuclear engineering students and reactor operators, this reactor still remains an indispensable tool for nuclear teaching and a choice instrument for scientists. (author)

Role of Antioxidants in Horse Serum-mediated Vasculitis in Swine: Potential Relevance to Early Treatment in Mitigation of Coronary Arteritis in Kawasaki Disease

Directory of Open Access Journals (Sweden)

Saji Philip

2017-08-01

Conclusion: Serum sickness is a prototype of immune complex vasculitis, and the severity can be ameliorated with antioxidants. A trial of therapeutic dosages of vitamins A, E, and C in acute phase of Kawasaki disease, may be effective in mitigation of coronary artery lesion in addition to intravenous immunoglobulin and aspirin.

Investigations of the reactivity temperature coefficient of the Dresden Technical University training and research reactor

International Nuclear Information System (INIS)

Adam, E.; Knorr, J.

1982-01-01

Approximate formulas are derived for determining the temperature coefficient of reactivity of the training and research reactor (AKR) of the Dresden Technical University. Values calculated on the basis of these approximations show good agreement with experimentally obtained results, thus confirming the applicability of the formulas to simple systems

Development of high performance core for large fast breeder reactors

International Nuclear Information System (INIS)

Inoue, Kotaro; Kawashima, Katsuyuki; Watari, Yoshio.

1982-01-01

Subsequently to the fast breeder prototype reactor ''Monju'', the construction of a demonstration reactor with 1000 MWe output is planned. This research aims at the establishment of the concept of a large core with excellent fuel breeding property and safety for a demonstration and commercial reactors. For the purpose, the optimum specification of fuel design as a large core was clarified, and the new construction of a core was examined, in which a disk-shaped blanket with thin peripheral edge is introduced at the center of a core. As the result, such prospect was obtained that the time for fuel doubling would be 1/2, and the energy generated in a core collapse accident would be about 1/5 as compared with a large core using the same fuel as ''Monju''. Generally, as a core is enlarged, the rate of breeding lowers. If a worst core collapse accident occurs, the scale of accident will be very large in the case of a ''Monju'' type large core. In an unhomogeneous core, an internal blanket is provided in the core for the purpose of improving the breeding property and safety. Hitachi Ltd. developed the concept of a large core unhomogeneous in axial direction and proposed it. The research on the fuel design for a large core, an unhomogeneous core and its core collapse accident is reported. (Kako, I.)

Interactive Virtual Reactor and Control Room for Education and Training at Universities and Nuclear Power Plants

International Nuclear Information System (INIS)

Satoh, Yoshinori; Li, Ye; Zhu, Xuefeng; Rizwan, Uddin

2014-01-01

Efficient and effective education and training of nuclear engineering students and nuclear workers are critical for the safe operation and maintenance of nuclear power plants. With an eye toward this need, we have focused on the development of 3D models of virtual labs for education, training as well as to conduct virtual experiments. These virtual labs, that are expected to supplement currently available resources, and have the potential to reduce the cost of education and training, are most easily developed on game-engine platforms. We report some recent extensions to the virtual model of the University of Illinois TRIGA reactor

Interactive Virtual Reactor and Control Room for Education and Training at Universities and Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Satoh, Yoshinori; Li, Ye; Zhu, Xuefeng; Rizwan, Uddin [University of Illinois, Urbana (United States)

2014-08-15

Efficient and effective education and training of nuclear engineering students and nuclear workers are critical for the safe operation and maintenance of nuclear power plants. With an eye toward this need, we have focused on the development of 3D models of virtual labs for education, training as well as to conduct virtual experiments. These virtual labs, that are expected to supplement currently available resources, and have the potential to reduce the cost of education and training, are most easily developed on game-engine platforms. We report some recent extensions to the virtual model of the University of Illinois TRIGA reactor.

Revitalization of reactor usage through reactor sharing

International Nuclear Information System (INIS)

Vernetson, W.G.

1986-01-01

The purpose of this work was to renew interest in using the University Florida Training Reactor (UFTR) for educational and training purposes outside the Nuclear Engineering Sciences (NES) and Environmental Engineering Sciences (EES) Departments at the University of Florida and for research by others outside the NES Department. The availability of the UFTR made possible through a US Department of Energy (DOE) Reactor Sharing Grant provided the mechanism to pursue generation of renewed interest at all levels both within the University of Florida and from other educational and corporate institutions

Standing on the shoulders of giants: production concepts versus production applications. The Hitachi Tool Engineering example Sobre ombros de gigantes: conceitos de produção versus aplicações na produção. O exemplo da Hitachi Tool Engineering

Directory of Open Access Journals (Sweden)

Eliyahu M. Goldratt

2009-09-01

Full Text Available This article analyzes the methodologies of Henry Ford, Taiichi Ohno, and Eliyahu Goldratt and presents explicitly the four principles of flow management according to these operations management philosophies. The differences among them are related to different instances of the same principles in different environments: Ford in his industry focusing on mass production of few (or one products, Ohno at Toyota with the Toyota production System (TPS, and Goldratt in a wide range of production environments. The concepts are illustrated and tested in a practical case of implementation in the Hitachi Tool Engineering company. Here, we have the classic case of an unlikely successful attempt to implement a methodology (Lean, and how the Theory of Constraints (TOC solved this issue. Finally, the limits for the solution proposed by Goldratt for operations management (DBR are described.Este artigo avalia as metodologias de Henry Ford, Taiichi Ohno e Elyahu Goldratt e apresenta de maneira explícita os quatros princípios de gestão do fluxo que estão por trás destas filosofias de gestão de operações. As diferenças entre estas três são traçadas para diferentes instâncias dos mesmos princípios em ambientes específicos: Ford em sua indústria, com foco na produção em massa de poucos (ou um produtos; Ohno na Toyota, com o Toyota Production System (TPS; e Goldratt, em uma classe ampla de ambientes de produção. Os conceitos são ilustrados e postos à prova no caso prático da Hitachi Tool Engineering. Este é o caso clássico de tentativa de implementação de uma metodologia (Lean que não se aplica e como isto foi resolvido pela Teoria das Restrições (TOC. Finalmente os limites da solução proposta por Goldratt para a gestão de operações (TPC são explicitados.

Calibration of new I and C at VR-1 training reactor

International Nuclear Information System (INIS)

Kropik, Martin; Jurickova, Monika

2011-01-01

The paper describes a calibration of the new instrumentation and control (I and C) at the VR-1 training reactor in Prague. The I and C uses uncompensated fission chambers for the power measurement that operate in a pulse or a DC current and a Campbell regime, according to the reactor power. The pulse regime uses discrimination for the avoidance of gamma and noise influence of the measurement. The DC current regime employs a logarithmic amplifier to cover the whole reactor DC current power range with only one electronic circuit. The system computer calculates the real power from the logarithmic data. The Campbell regime is based on evaluation of the root mean square (RMS) value of the neutron noise. The calculated power from Campbell range is based on the square value of the RMS neutron noise data. All data for the power calculation are stored in computer flash memories. To set proper data there, it was necessary to carry out the calibration of the I and C. At first, the proper discrimination value was found while examining the spectrum of the neutron signal from the chamber. The constants for the DC current and Campbell calculations were determined from an independent reactor power measurement. The independent power measuring system that was used for the calibration was accomplished by a compensated current chamber with an electrometer. The calculated calibration constants were stored in the computer flash memories, and the calibrated system was again successfully compared with the independent power measuring system. Finally, proper gamma discrimination of the Campbell system was carefully checked.

The application of MVC design pattern in Daya bay reactor neutrino experiments online safety training system

International Nuclear Information System (INIS)

Liu Guanchuan; Chu Yuanping

2011-01-01

The article made an introduction to MVC, which is an architectural pattern used in software engineering. It specified the advantages and disadvantages of MVC and also the application of MVC in Daya Bay nuclear reactor neutrino experiment online safety training system. (authors)

Development of Reactor Console Simulator for PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Mohd Idris Taib; Izhar Abu Hussin; Mohd Khairulezwan Abdul Manan; Nufarhana Ayuni Joha; Mohd Sabri Minhat

2012-01-01

The Reactor Console Simulator will be an interactive tool for operator training and teaching of PUSPATI TRIGA Reactor. Behaviour and characteristic for reactor console and reactor itself can be evaluated and understand. This Simulator will be used as complement for actual present reactor console. Implementation of man-machine interface is using computer screens, keyboard and mouse. Multiple screens are used to match the physical of present reactor console. LabVIEW software are using for user interface and mathematical calculation. Polynomial equation based on control rods calibration data as well as operation parameters record was used to calculate the estimated reactor console parameters. (author)

The next 20 years operation of the 36 years old Hungarian training reactor

International Nuclear Information System (INIS)

Aszodi, A.

2007-01-01

Hungary prepares for extending the design lifetime of the four VVER-440/213 type units; in that case they will finish operation between 2032 and 2037. Discussion on possible new nuclear units in Hungary was recently commenced. The paper describes actions in human resource management and knowledge management, and also the new safety analysis methods which were applied during the recent Periodic Safety Review of the Hungarian Training Reactor

Kawasaki disease with G6PD deficiency--report of one case and literature review.

Science.gov (United States)

Chen, Chia-Hao; Lin, Li-Yan; Yang, Kuender D; Hsieh, Kai-Sheng; Kuo, Ho-Chang

2014-06-01

Kawasaki disease (KD) is a systemic vasculitis primarily affecting children who are younger than 5 years. The most serious complications are coronary artery aneurysms and sequelae of vasculitis with the subsequent development of coronary artery aneurysm. According to the literature, intravenous immunoglobulin (IVIG) plus high-dose aspirin (acetylsalicylic acid) were standard treatment for KD, whereas low-dose aspirin (3-5 mg/kg/day) was used for thrombocytosis in KD via antiplatelet effect. However, aspirin has been reported to have hemolytic potential in individuals with glucose-6-phosphate dehydrogenase (G6PD) deficiency. We report a child with G6PD-deficiency who has KD, and review the literature. Copyright © 2012. Published by Elsevier B.V.

Replication and meta-analysis of GWAS identified susceptibility loci in Kawasaki disease confirm the importance of B lymphoid tyrosine kinase (BLK) in disease susceptibility

NARCIS (Netherlands)

Chang, Chia-Jung; Kuo, Ho-Chang; Chang, Jeng-Sheng; Lee, Jong-Keuk; Tsai, Fuu-Jen; Khor, Chiea Chuen; Chang, Li-Ching; Chen, Shih-Ping; Ko, Tai-Ming; Liu, Yi-Min; Chen, Ying-Ju; Hong, Young Mi; Jang, Gi Young; Hibberd, Martin L.; Kuijpers, Taco; Burgner, David; Levin, Michael; Burns, Jane C.; Davila, Sonia; Chen, Yuan-Tsong; Chen, Chien-Hsiun; Wu, Jer-Yuarn; Lee, Yi-Ching; Liang, Chi-Di; Hwang, Kao-Pin; Chang, Luan-Yin; Huang, Li-Min; Chen, Ming-Ren; Chi, Hsin; Huang, Fu-Yuan; Chiu, Nan-Chang; Lee, Meng-Luen; Huang, Yhu-Chering; Hwang, Betau; Lee, Pi-Chang; Yoo, Jeong-Jin; Park, In-Sook; Hong, Soo-Jong; Kim, Kwi-Joo; Kim, Jae-Jung; Sohn, Saejung; Young Jang, Gi; Ha, Kee-Soo; Nam, Hyo-Kyoung; Byeon, Jung-Hye; Yun, Sin Weon; Han, Myung Ki; Kuipers, Irene M.; Ottenkamp, Jaap J.; Biezeveld, Maarten

2013-01-01

The BLK and CD40 loci have been associated with Kawasaki disease (KD) in two genome-wide association studies (GWAS) conducted in a Taiwanese population of Han Chinese ancestry (Taiwanese) and in Japanese cohorts. Here we build on these findings with replication studies of the BLK and CD40 loci in

Utilization of nuclear research reactors

International Nuclear Information System (INIS)

1980-01-01

Full text: Report on an IAEA interregional training course, Budapest, Hungary, 5-30 November 1979. The course was attended by 19 participants from 16 Member States. Among the 28 training courses which the International Atomic Energy Agency organized within its 1979 programme of technical assistance was the Interregional Training Course on the Utilization of Nuclear Research Reactors. This course was held at the Nuclear Training Reactor (a low-power pool-type reactor) of the Technical University, Budapest, Hungary, from 5 to 30 November 1979 and it was complemented by a one-week Study Tour to the Nuclear Research Centre in Rossendorf near Dresden, German Democratic Republic. The training course was very successful, with 19 participants attending from 16 Member States - Bangladesh, Bolivia, Czechoslovakia, Ecuador, Egypt, India, Iraq, Korean Democratic People's Republic, Morocco, Peru, Philippines, Spain, Thailand, Turkey, Vietnam and Yugoslavia. Selected invited lecturers were recruited from the USA and Finland, as well as local scientists from Hungarian institutions. During the past two decades or so, many research reactors have been put into operation around the world, and the demand for well qualified personnel to run and fully utilize these facilities has increased accordingly. Several developing countries have already acquired small- and medium-size research reactors mainly for isotope production, research in various fields, and training, while others are presently at different stages of planning and installation. Through different sources of information, such as requests to the IAEA for fellowship awards and experts, it became apparent that many research reactors and their associated facilities are not being utilized to their full potential in many of the developing countries. One reason for this is the lack of a sufficient number of trained professionals who are well acquainted with all the capabilities that a research reactor can offer, both in research and

New digital control and power protection system of VR 1 training reactor

International Nuclear Information System (INIS)

Kropik, M.; Matejka, K.; Juoeickova, M.

2005-01-01

The contribution describes the new VR-1 training reactor control and power protection system at the Czech Technical University in Prague. The control system provides safety and control functions, calculates average values of the important variables and sends data and system status to the human-machine interface. The upgraded control system is based on a high quality industrial PC. The operating system of the PC is the Microsoft Windows XP with the real time support RTX of the VentureCom Company. The software was developed according to requirements in MS Visual C. The independent power protection system is a component of the reactor safety (protection) system with high quality and reliability requirements. The digital system is redundant; each channel evaluates the reactor power and the velocity of power changes and provides safety functions. The digital part of the channel is multiprocessor-based. The software was developed with respect to nuclear standards. The software design was coded in the C language regarding the NRC restrictions. Configuration management, verification and validation accompanied the software development. Both systems were thoroughly tested. Firstly, the non active tests were carried out. During these tests, the active core of the reactor was subcritical; the input signals were generated from HPIB and VXI controlled instruments to simulate different operational and safety events. The software for instruments control and tests evaluation utilized Agilent VEE development system. After the successful non active checking, the active tests followed. (author)

Safety and Efficacy of Warfarin Therapy in Kawasaki Disease.

Science.gov (United States)

Baker, Annette L; Vanderpluym, Christina; Gauvreau, Kimberly A; Fulton, David R; de Ferranti, Sarah D; Friedman, Kevin G; Murray, Jenna M; Brown, Loren D; Almond, Christopher S; Evans-Langhorst, Margaret; Newburger, Jane W

2017-10-01

To describe the safety and efficacy of warfarin for patients with Kawasaki disease and giant coronary artery aneurysms (CAAs, ≥8 mm). Giant aneurysms are managed with combined anticoagulation and antiplatelet therapies, heightening risk of bleeding complications. We reviewed the time in therapeutic range; percentage of international normalization ratios (INRs) in range (%); bleeding events, clotting events; INRs ≥6; INRs ≥5 and warfarin therapy was 7.2 years (2.3-13.3 years). Goal INR was 2.0-3.0 (n = 6) or 2.5-3.5 (n = 3), based on CAA size and history of CAA thrombosis. All patients were treated with aspirin; 1 was on dual antiplatelet therapy and warfarin. The median time in therapeutic range was 59% (37%-85%), and median percentage of INRs in range was 68% (52%-87%). INR >6 occurred in 3 patients (4 events); INRs ≥5 warfarin and aspirin, with INRs in range only two-thirds of the time. Future studies should evaluate the use of direct oral anticoagulants in children as an alternative to warfarin. Copyright © 2017 Elsevier Inc. All rights reserved.

Usefulness of 64-slice MDCT for follow-up of young children with coronary artery aneurysm due to Kawasaki disease: initial experience.

Science.gov (United States)

Peng, Yun; Zeng, Jinjin; Du, Zhongdong; Sun, Guoqiang; Guo, Huling

2009-03-01

To evaluate the initial application and value of 64-slice multidetector computed tomography as an alternative diagnostic modality in the follow-up of young children with coronary artery aneurysm due to Kawasaki disease. Twelve boys (mean age 5.1 years, range 1.8-7.8 years) for follow-up (time range from 1.1 to 5.1 years) of known Kawasaki disease and coronary artery aneurysm underwent 64-slice MDCT ECG-gated coronary angiography. All data were acquired without breath holding. Two pediatric radiologists independently assessed image quality and the diameter of all coronary segments were measured for each patient. The number, position, shape and size of each coronary artery aneurysm were observed and compared with those of ECHO performed previously. A total of 118/156 segments permitted visualization with diagnostic image quality, the CT measurements showed good inter-observer and intra-observer reliability, coefficients were 0.93 and 0.88, respectively. A total of 30 coronary artery aneurysms were identified with measured mean of 7.5+/-3.8 mm in diameter, and of 12.4+/-9.1 mm in longitudinal lengths.10 tumors were small, 8 tumors were medium and 12 tumors were giant aneurysm. The affected segments included LM7/12(58.3%), 9/12(75%) of LAD1, 4/12(33.3%) of LAD2, 2/12(16.7%) of LCX1; 6/12(50%) of RCA1, 9/12(75%) of RCA2 and 4/12(33.3%) of RCA3, including affected two segments in 9 tumors and three segments in 1 tumor. Calcifications were found in 5 aneurysms and 3/5 with thrombosis; six stenotic segments were found. ECHO failed to detect 8 tumors with 2/8 in LAD, 1/8 in LCX and 5/8 in RCA, and those included 4 small aneurysms. The use of 64-slice MDCT angiography proved valuable for monitoring young children with Kawasaki disease. However, further study is necessary to specify the sensitivity and specificity of MDCT in the follow-up.

Usefulness of 64-slice MDCT for follow-up of young children with coronary artery aneurysm due to Kawasaki disease: Initial experience

International Nuclear Information System (INIS)

Peng Yun; Zeng Jinjin; Du Zhongdong; Sun Guoqiang; Guo Huling

2009-01-01

To evaluate the initial application and value of 64-slice multidetector computed tomography as an alternative diagnostic modality in the follow-up of young children with coronary artery aneurysm due to Kawasaki disease. Twelve boys (mean age 5.1 years, range 1.8-7.8 years) for follow-up (time range from 1.1 to 5.1 years) of known Kawasaki disease and coronary artery aneurysm underwent 64-slice MDCT ECG-gated coronary angiography. All data were acquired without breath holding. Two pediatric radiologists independently assessed image quality and the diameter of all coronary segments were measured for each patient. The number, position, shape and size of each coronary artery aneurysm were observed and compared with those of ECHO performed previously. A total of 118/156 segments permitted visualization with diagnostic image quality, the CT measurements showed good inter-observer and intra-observer reliability, coefficients were 0.93 and 0.88, respectively. A total of 30 coronary artery aneurysms were identified with measured mean of 7.5 ± 3.8 mm in diameter, and of 12.4 ± 9.1 mm in longitudinal lengths.10 tumors were small, 8 tumors were medium and 12 tumors were giant aneurysm. The affected segments included LM7/12(58.3%), 9/12(75%) of LAD1, 4/12(33.3%) of LAD2, 2/12(16.7%) of LCX1; 6/12(50%) of RCA1, 9/12(75%) of RCA2 and 4/12(33.3%) of RCA3, including affected two segments in 9 tumors and three segments in 1 tumor. Calcifications were found in 5 aneurysms and 3/5 with thrombosis; six stenotic segments were found. ECHO failed to detect 8 tumors with 2/8 in LAD, 1/8 in LCX and 5/8 in RCA, and those included 4 small aneurysms. The use of 64-slice MDCT angiography proved valuable for monitoring young children with Kawasaki disease. However, further study is necessary to specify the sensitivity and specificity of MDCT in the follow-up.

Usefulness of 64-slice MDCT for follow-up of young children with coronary artery aneurysm due to Kawasaki disease: Initial experience

Energy Technology Data Exchange (ETDEWEB)

Peng Yun [Imaging Center, Beijing Children' s Hospital Affiliated to Capital Medical University, 56, Nanlishi Road, Xicheng District, Beijing 100045 (China)], E-mail: ppengyun@yahoo.com; Zeng Jinjin [Imaging Center, Beijing Children' s Hospital Affiliated to Capital Medical University, 56, Nanlishi Road, Xicheng District, Beijing 100045 (China); Du Zhongdong [Pediatric Cardiovascular Department, Beijing Children' s Hospital Affiliated to Capital Medical University, 56, Nanlishi Road, Xicheng District, Beijing 100045 (China); Sun Guoqiang [Imaging Center, Beijing Children' s Hospital Affiliated to Capital Medical University, 56, Nanlishi Road, Xicheng District, Beijing 100045 (China); Guo Huling [Pediatric Cardiovascular Department, Beijing Children' s Hospital Affiliated to Capital Medical University, 56, Nanlishi Road, Xicheng District, Beijing 100045 (China)

2009-03-15

To evaluate the initial application and value of 64-slice multidetector computed tomography as an alternative diagnostic modality in the follow-up of young children with coronary artery aneurysm due to Kawasaki disease. Twelve boys (mean age 5.1 years, range 1.8-7.8 years) for follow-up (time range from 1.1 to 5.1 years) of known Kawasaki disease and coronary artery aneurysm underwent 64-slice MDCT ECG-gated coronary angiography. All data were acquired without breath holding. Two pediatric radiologists independently assessed image quality and the diameter of all coronary segments were measured for each patient. The number, position, shape and size of each coronary artery aneurysm were observed and compared with those of ECHO performed previously. A total of 118/156 segments permitted visualization with diagnostic image quality, the CT measurements showed good inter-observer and intra-observer reliability, coefficients were 0.93 and 0.88, respectively. A total of 30 coronary artery aneurysms were identified with measured mean of 7.5 {+-} 3.8 mm in diameter, and of 12.4 {+-} 9.1 mm in longitudinal lengths.10 tumors were small, 8 tumors were medium and 12 tumors were giant aneurysm. The affected segments included LM7/12(58.3%), 9/12(75%) of LAD1, 4/12(33.3%) of LAD2, 2/12(16.7%) of LCX1; 6/12(50%) of RCA1, 9/12(75%) of RCA2 and 4/12(33.3%) of RCA3, including affected two segments in 9 tumors and three segments in 1 tumor. Calcifications were found in 5 aneurysms and 3/5 with thrombosis; six stenotic segments were found. ECHO failed to detect 8 tumors with 2/8 in LAD, 1/8 in LCX and 5/8 in RCA, and those included 4 small aneurysms. The use of 64-slice MDCT angiography proved valuable for monitoring young children with Kawasaki disease. However, further study is necessary to specify the sensitivity and specificity of MDCT in the follow-up.

Incidence, epidemiology and clinical features of Kawasaki disease in Catalonia, Spain.

Science.gov (United States)

Sánchez-Manubens, Judith; Antón, Jordi; Bou, Rosa; Iglesias, Estíbaliz; Calzada-Hernandez, Joan

2016-01-01

To assess the incidence, epidemiology and clinical features of Kawasaki disease (KD) in Catalonia (northeast region of Spain). This was an observational population-based study including all Paediatric Units in Catalonia, under both public and private management. Retrospective data retrieval was performed for 10 years (2004-2013). A 12-month (March 2013 to March 2014) prospective collection of new cases of KD was carried out to determine the incidence of KD. Data from 399 patients over the 10-year study period was analysed, revealing that 233 (58.4%) had complete KD, 159 (39.8) incomplete KD and 7 (1.7%) were considered atypical KD. Mean annual incidence was 3.5/105 children 10(th) day of illness, ages 8 yo and the presence of sterile piuria, aseptic meningitis, abdominal pain and uveitis at diagnosis were found to have higher risk of coronary aneurisms (CAA) (pIncidence, clinical features and treatment plans in our cohort are similar to those described in other European studies.

Quantitative assessment of urban and industrial symbiosis in Kawasaki, Japan.

Science.gov (United States)

Van Berkel, Rene; Fujita, Tsuyoshi; Hashimoto, Shizuka; Fujii, Minoru

2009-03-01

Colocated firms can achieve environmental benefit and competitive advantage from exchanging physical resources (known as industrial symbiosis) with each other or with residential areas (referenced here as urban symbiosis). Past research illustrated that economic and environmental benefits appear self-evident, although detailed quantification has only been attempted of symbioses for energy and water utilities. This article provides a complimentary case studyfor Kawasaki, Japan. The 14 documented symbioses connect steel, cement, chemical, and paperfirms and their spin-off recycling businesses. Seven key material exchanges divert annually at least 565 000 tons of waste from incineration or landfill. Four of these collectively present an estimated economic opportunity of 13.3 billion JPY (approximately 130 million USD) annually. Five symbioses involve utilization of byproduct and two sharing of utilities. The others are traditional or new recycling industries that do not specifically benefit from geographic proximity. The synergistic effect of urban and industrial symbiosis is unique. The legislative framework for a recycling-oriented society has contributed to realization of the symbioses, as has the availability of government subsidies through the Eco-Town program.

Overall plant concept for a tank-type fast reactor

International Nuclear Information System (INIS)

Yamaki, Hideo; Davies, S.M.; Goodman, L.

1984-01-01

Japanese nuclear industries are expressing interest in the merits of the tank-type FBR as a large plant (demonstration) after JOYO (experimental, in operation) and MONJU (prototype, under construction). In response to this growing interest in a tank-type FBR demonstration plant, Hitachi has initiated a conceptual study of a 1000 MWe tank plant concept in collaboration with GE and Bechtel. Key objectives of this study have been: to select reliable and competitive tank plant concepts, with emphases on a seismic-resistant and compact tank reactor system;to select reliable shutdown heat removal system;and to identify R and D items needed for early 1990s construction. Design goals were defined as follows: capital costs must be less than twice, and as close as practical to 1.5 those of equivalent LWR plants;earthquake resistant structures to meet stringent Japanese seismic conditions must be as simple and reliable as practical;safety must be maintained at LWR-equivalent risks;and R and D needs must be limited to minimum cost for the limited time allowed. This paper summarizes the overall plant concepts with some selected topics, whereas detailed descriptions of the reactor assembly and the layout design are found in separate papers

Full-scale prototyping of the Hitachi dual-purpose metal cask and verification of its heat transfer characteristics

International Nuclear Information System (INIS)

Kumagai, N.; Ishida, N.; Ootsuka, M.; Kamoshida, M.; Hiranuma, T.; Doumori, S.; Hoshikawa, T.; Shimizu, M.; Kashiwakura, J.; Hayashi, M.

2004-01-01

Hitachi has been developing dual-purpose metal casks for transport and storage of spent nuclear fuels. The Hitachi cask, HDP69B can store 69 BWR fuel assemblies. The cask features are as follows. 1) The fuel basket is assembled mainly with plates of borated stainless steel. The plates are not welded, but cross-inserted into each other like the dividers in an egg carton. Since the borated stainless steel has relatively low heat conductivity, aluminum alloy plates are inserted along with some stainless steel plates to enhance heat removal ability. 2) Cured resin blocks are fitted into the inner shell of the cask for neutron shielding of the cask body. The resin blocks are surrounded by an aluminum casing which transfers heat of stored fuel from the inner shell to the outer shell of the cask. The block type shield structure eliminates the need for welding the heat transfer fins to the inner and outer shells. The weldless structures of the HDP69B lead to its enhanced manufacturability, but they complicate the heat transfer characteristics because there are gaps between such components as the aluminum casing and inner/outer shells. We carried out full-scale prototyping of the HDP69B and ran a heat transfer test using the prototype. The purposes of the heat transfer test were to check the heat removal ability of the HDP69B and to verify the safety analysis model for heat removal. Results of the heat transfer test and optimized analysis model for heat transfer characteristics of the HDP69B are the focus of this paper. The heat transfer test is summarized as follows. Sixty nine heaters simulating the shape and heat power of spent fuel assemblies were inserted into the fuel basket. After replacing the inner atmosphere with 0.1 MPa of helium, the heat transfer test was started. About 7 days were required to equilibrate the temperature distribution. The temperature at the center of the basket was 194 C. The results confirmed the HDP69B had sufficient heat removal ability. The

International Project on Innovative Nuclear Reactors and Fuel Cycles: Introduction and Education and Training Activity

International Nuclear Information System (INIS)

Fesenko, G.; Kuznetsov, V.; Phillips, J.R.; Rho, K.; Grigoriev, A.; Korinny, A.; Ponomarev, A.

2015-01-01

The IAEA’s International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was established in 2000 through IAEA General Conference resolution with aim to ensure that sustainable nuclear energy is available to help meet the energy needs of the 21st century. INPRO seeks to bring together technology holders, users and newcomers to consider jointly the international and national actions required for achieving desired innovations in nuclear reactors and fuel cycles, with a particular focus on sustainability and needs of developing countries. It is a mechanism for INPRO Members to collaborate on topics of joint interest. INPRO activities are undertaken in close cooperation with Member States in the following main areas: Global Scenarios, Innovations, Sustainability Assessment and Strategies, Policy and Dialogue. The paper presents short introduction in INPRO and specifically the distant Education and Training INPRO activity on important topics of nuclear energy sustainability to audiences in different Member States. These activities can support capacity building and national human resource development in the nuclear energy sector. The main benefit of such training courses and workshops is that it is not only targeted to students, but also to lecturers of technical and nuclear universities. Moreover, young professionals working at nuclear energy departments, electric utilities, energy ministries and R&D institutions can participate in such training and benefit from it. (authors)

Kawasaki disease-associated coronary artery lesions with navigator echo-based. Respiratory-gated three dimensional coronary magnetic resonance angiography compared with echocardiography in young children

International Nuclear Information System (INIS)

Amino, Masayuki; Teraoka, Kunihiko; Hirano, Masaharu; Kawashima, Naoshi; Kakizaki, Dai; Ookubo, Yasuo; Sasaki, Kazuyoshi; Katuyama, Hiroaki

2004-01-01

Navigator echo-based respiratory-gated three dimensional coronary magnetic resonance angiography (3D-CMRA) was compared with echocardiography, to determine whether 3D-CMRA was useful for the evaluation of Kawasaki disease-associated coronary artery lesions. Sixteen consecutive patients (imaging was performed 17 times in total) who were given a diagnosis of Kawasaki's disease at the pediatric department of our hospital and examined for the precise examination of complicating coronary artery lesions on MRI using a navigator-echo technique because of their incapability of holding their breath during imaging were entered into the present study. A 1.5T MRI system was used. Gd-DOTA was given at a total volume of 0.1 mmol/kg. During imaging, CMRA visualized the left coronary arteries in all 17 cases and the right coronary arteries in 16 cases, but not in one case. The left main coronary trunk segment no.5 was demonstrated in all cases with CMRA, but not in 4 cases with echocardiography. The left anterior descending branch no.6 was visualized in 11 of the 17 cases with CMRA, but only in 5 cases with echocardiography. The left circumflex branch no.11 was observed in 6 cases with CMRA, but only in 2 cases with echocardiography. As for the right coronary arteries, branches no.1 and no.2 were observed in 16 and 9 cases with CMRA, respectively, and in 13 and 3 cases with echocardiography, respectively. Vascular diameters measured on CMRA were almost identical to those on echocardiography, within the range of arteries visualized. 3D-CMRA combined with a navigator echo technique appears to be a useful tool for the observation of coronary artery lesions associated with Kawasaki's disease because it is superior in lesion visualization to echocardiography. (author)

Optimization of a Chemical Reaction Train

Directory of Open Access Journals (Sweden)

Bahar Sansar

2010-01-01

Full Text Available This project consists of the optimization of a chemical reactor train. The reactor considered here is the continuous stirred tank reactor (CSTR, one of the reactor models used in engineering. Given the design equation for the CSTR and the cost function for a reactor, the following values are determined; the optimum number of reactors in the reaction train, the volume of each reactor and the total cost.

The role of the IPR-R1 TRIGA Mark I research reactor in nuclear education and training in Brazil

Energy Technology Data Exchange (ETDEWEB)

Ferreira, Andrea V.; Mesquita, Amir Z.; Maretti Junior, Fausto; Souza, Rose Mary G.P.; Dalle, Hugo M.; Paiano, Silvestre, E-mail: avf@cdtn.br, E-mail: amir@cdtn.br, E-mail: fmj@cdtn.br, E-mail: souzarm@cdtn.br, E-mail: dallehm@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2011-07-01

The revival of the Brazilian nuclear program has anticipated a large demand for training in nuclear technology. The Nuclear Technology Development Center (CDTN), a research institute of the Brazilian Nuclear Energy Commission (CNEN), offers the Operator Training Course on Research Reactors (CTORP). This course has existed since 1974 and about 258 workers were certificated by CTORP. This article describes the activities of CTORP and presents a proposal for its activities expansion in order to provide the current demand in the nuclear technology. Experimental research projects programs would be created in the postgraduate course at CDTN. In addition to the normal reactor physics topics addressed by CTORP, new subjects such as thermal hydraulic and instrumentation should be added and discussed too. (author)

The role of the IPR-R1 TRIGA Mark I research reactor in nuclear education and training in Brazil

International Nuclear Information System (INIS)

Ferreira, Andrea V.; Mesquita, Amir Z.; Maretti Junior, Fausto; Souza, Rose Mary G.P.; Dalle, Hugo M.; Paiano, Silvestre

2011-01-01

The revival of the Brazilian nuclear program has anticipated a large demand for training in nuclear technology. The Nuclear Technology Development Center (CDTN), a research institute of the Brazilian Nuclear Energy Commission (CNEN), offers the Operator Training Course on Research Reactors (CTORP). This course has existed since 1974 and about 258 workers were certificated by CTORP. This article describes the activities of CTORP and presents a proposal for its activities expansion in order to provide the current demand in the nuclear technology. Experimental research projects programs would be created in the postgraduate course at CDTN. In addition to the normal reactor physics topics addressed by CTORP, new subjects such as thermal hydraulic and instrumentation should be added and discussed too. (author)

Training courses on the use of neutron detection systems carried out on the ISIS research reactor

International Nuclear Information System (INIS)

Lescop, Bernard; Foulon, Francois

2013-06-01

Training courses on the use of the neutron detection systems for the control of the nuclear reactors are carried out by the National Institute for Nuclear Science using the ISIS research reactor. The study and the comprehension of the operation of these systems are facilitated by the use a research reactor in order to observe the electronic signals in real conditions. Thus, ISIS reactor offers a wide range of neutron fluxes and the level of power can be easily set to any value from zero to nominal power (700 kW). Different kinds of detectors (counters, ionization chambers), which operate in the different modes of detection (pulse, current and Campbelling) can be placed in the periphery of the core for the courses. The electronic signal can be analyzed at each step of the detection process. One goal of the courses is to understand the role of each component of the detection system: detector, cable and each electronic module. A comparison with the nuclear instrumentation used by the instrumentation and control of ISIS reactor is also made. This comparison is very useful to understand the role of the neutron instrumentation in terms of safety, availability, reliability and maintainability. (authors)

Self-Sustaining Thorium Boiling Water Reactors

Directory of Open Access Journals (Sweden)

Ehud Greenspan

2012-10-01

Full Text Available A thorium-fueled water-cooled reactor core design approach that features a radially uniform composition of fuel rods in stationary fuel assembly and is fuel-self-sustaining is described. This core design concept is similar to the Reduced moderation Boiling Water Reactor (RBWR proposed by Hitachi to fit within an ABWR pressure vessel, with the following exceptions: use of thorium instead of depleted uranium for the fertile fuel; elimination of the internal blanket; and elimination of absorbers from the axial reflectors, while increasing the length of the fissile zone. The preliminary analysis indicates that it is feasible to design such cores to be fuel-self-sustaining and to have a comfortably low peak linear heat generation rate when operating at the nominal ABWR power level of nearly 4000 MWth. However, the void reactivity feedback tends to be too negative, making it difficult to have sufficient shutdown reactivity margin at cold zero power condition. An addition of a small amount of plutonium from LWR used nuclear fuel was found effective in reducing the magnitude of the negative void reactivity effect and enables attaining adequate shutdown reactivity margin; it also flattens the axial power distribution. The resulting design concept offers an efficient incineration of the LWR generated plutonium in addition to effective utilization of thorium. Additional R&D is required in order to arrive at a reliable practical and safe design.

Pressurized water reactor simulator. Workshop material

International Nuclear Information System (INIS)

2003-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 reactor department simulator from the Moscow Engineering and Physics Institute, the Russian Federation is presented in the IAEA Training Course Series No. 21 'WWER-1000 Reactor Simulator' (2002). Course material for workshops using a boiling water reactor simulator developed for the IAEA by Cassiopeia Technologies Incorporated of Canada (CTI) is presented in the IAEA publication: Training Course Series No.23 'Boiling Water Reactor Simulator' (2003). This report consists of course material for workshops using a pressurized water reactor simulator

Assessment of the effectiveness of training technology transfer activities at soviet-designed reactors

International Nuclear Information System (INIS)

Haber, S.; Shurberg, D.; Yoder, J.; Draper, D.

2003-01-01

The U.S. Department of Energy (DOE) has been working with personnel at Soviet-Designed Reactors (SDRs) to enhance management and operational safety by upgrading many areas of plant operations to levels that meet established international standards. Since 1992 this work has included activities related to training. The work initially focussed on the establishment of nuclear training centers in Russia and Ukraine and the transfer of U.S. training methodologies but has since expanded to include all Russian and Ukrainian nuclear power stations and training centers as well as SDRs within other countries. A key component to the work has been the determination of programmatic effectiveness. Of specific interest has been the success of the transfer of U.S. training methodologies to SDRs so the capability exists for independent expansion of training efforts. Of equal importance has been the question of whether the training programs being developed are having the desired impact on facility safety performance. While progress has been made in the evaluation of the impact of training on facility safety performance, the question has not yet been fully answered. The issue has been further confounded due to wide-ranging and concurrent changes being made beyond training to many aspects of facility operations and maintenance. This paper focuses on the selection of a strategy to upgrade and, as necessary, develop training programs to assist in the improvement of SDR safety. Difficulties encountered in the development of assessment strategies across all SDRs that are being worked with are discussed. In addition, measures collected related to the success of the overall program efforts and data indicating the success of the DOE efforts in the transfer and adoption by SDRs of an effective training methodology are outlined. (author)

Reactor use in nuclear engineering programs

International Nuclear Information System (INIS)

Murray, R.L.

1975-01-01

Nuclear reactors for dual use in training and research were established at about 50 universities in the period since 1950, with assistance by the U. S. Atomic Energy Commission and the National Science Foundation. Most of the reactors are in active use for a variety of educational functions--laboratory teaching of undergraduates and graduate students, graduate research, orientation of visitors, and nuclear power plant reactor operator training, along with service to the technical community. As expected, the higher power reactors enjoy a larger average weekly use. Among special programs are reactor sharing and high-school teachers' workshops

PWR training from conception to criticality

International Nuclear Information System (INIS)

Molloy, B.

1993-01-01

Since the accident at the Three Mile Island Pressurized Water Reactor in 1979, training of reactor personnel has been critically evaluated and reviewed. In the United Kingdom, the building of the first Pressurized Water Reactor at Sizewell in Suffolk, has brought staff training into sharp relief also. This article looks at the training program, set up in response to concerns over safety, which has been evolving over the last ten years. Simulators are widely used so that staff, especially reactor operators, are thoroughly conversant with operational technology long before reactor commissioning takes place. (UK)

DCS emulator development for the ACR-1000 simulator

International Nuclear Information System (INIS)

Nakashima, Y.; Trueman, R.; Ishii, K.

2010-01-01

Nuclear Power Plant (NPP) simulators are the main means for operator training and as such are a crucial part of the NPP operation life-cycle. Hitachi, Ltd., Information and Control Systems Company (henceforth 'Hitachi') is the preferred DCS and DCS emulator developer and supplier for the ACR-1000 NPP control system. Hitachi's concept for the DCS (distributed control system) portion of the ACR-1000 simulator is 'total emulation of the DCS' by software. This paper will review the current status of the technical development and the major project milestones. (author)

Performance of small reactors at universities for teaching, research, training and service (TRTS): thirty five years' experience with the Dalhousie University SLOWPOKE-2 reactor

Energy Technology Data Exchange (ETDEWEB)

Chatt, A., E-mail: a.chatt@dal.ca [Dalhousie Univ., Trace Analysis Research Centre, Dept. of Chemistry, Halifax, Nova Scotia (Canada)

2013-07-01

The Dalhousie University SLOWPOKE-2 Reactor (DUSR) facility, operated during 1976-2011, was the only research reactor in Atlantic Canada as well as the only one associated with a chemistry department in a Canadian university. The most outstanding features of the facility included: a rapid (100 ms) cyclic pneumatic sample transfer system, a permanently installed Cd-site, and a Compton-suppression gamma-ray spectrometer. The usage encompassed fundamental as well as applied studies in various fields using neutron activation analysis (NAA). The facility was used for training undergraduate/graduate students, postdoctoral fellows, technicians, and visiting scientists, and for cooperative projects with other universities, research organizations and industries. (author)

New studies of the natural convection around a fuel rod of the BME training reactor with PIV/LIF technique

International Nuclear Information System (INIS)

Szijarto, R.; Aszodi, A.; Yamaji, B.

2011-01-01

In this paper the model of a fuel pin of the Training Reactor of Budapest University of Technology and Economics was investigated with Particle Image Velocimetry and Laser Induced Fluorescence measurement methods. An experimental setup was designed, built and optimized to investigate the natural convection around a model of a fuel pin of the Training Reactor. The processes were analysed using an electrically heated rod, which models the geometry of the fuel rods in the Training Reactor. The heated length of the model is the same as the active length of the real fuel rods. The rod is placed in a glass tank with a shape of a square-based prism. An additional cooling system ensures constant flow conditions around the rod. The setup consists of an additional flow channel box, the equivalent diameter of which is equal to the equivalent diameter of the real fuel assembly. Simultaneous measurements of velocity and temperature fields were performed in different vertical positions for both cases of natural convection with and without the flow channel box. The effect of the presence of the channel was analyzed, and a laminarizating influence was observed. The local heat transfer coefficient was calculated for every measurement. The two dimensional measurement techniques gave extensive results, the structure of the hydraulic and thermal boundary layer were fully analyzed. (Authors)

Remote controlled stud bolt handling device for reactor pressure vessel

International Nuclear Information System (INIS)

Shindo, Takenori; Shigehiro, Katsuya; Ito, Morio; Okada, Kenji

1988-01-01

In nuclear power stations, at the time of regular inspection, the works of opening and fixing the upper covers of reactor pressure vessels are carried out for inspecting the inside of reactor pressure vessels and exchanging fuel rods. These upper covers are fastened with many stud bolts, therefore, the works of opening and fixing require a large amount of labor, and are done under the restricted condition of wearing protective clothings and masks. Babcock Hitachi K.K. has completed the development of a remotely controlled automatic bolt tightenig device for this purpose, therefore, its outline is reported. The conventional method of these works and the problems in it are described. The design of the new device aimed at the parallel execution of cleaning screw threads, loosening and tightening nuts, and taking off and putting on nuts and washers, thus contributing to the shortening of regular inspection period, the reduction of the radiation exposure of workers, and the decrease of the number of workers. The function, reliability and endurance of the new device were confirmed by the verifying test using a device made for trial. The device is composed of a stand, a rail and four stations each with a cleaning unit, a stud tensioner and a nut handling unit. (K.I.)

Safety evaluation report related to the renewal of the operating license for the training and research reactor at the University of Maryland (Docket No. 50-166)

International Nuclear Information System (INIS)

1984-03-01

This Safety Evaluation Report for the application filed by the University of Maryland (UMD) for a renewal of operating license R-70 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Maryland and is located at a site in College Park, Prince Georges County, Maryland. The staff concludes that this training reactor facility can continue to be operated by UMD without endangering the health and safety of the public

Reduced enrichment fuel and its reactivity effects in the University Training Reactor Moata

International Nuclear Information System (INIS)

Wilson, D.J.

1983-08-01

Concern for nuclear proliferation is likely to preclude future supply of highly enriched uranium fuel for research reactors such as the University Training Reactor Moata. This study calculates the fuel densities necessary to maintain the reactivity per plate of the present high enrichment (90 per cent 235 U) fuel for a range of lower enrichments assuming that no geometry changes are allowed. The maximum uranium density for commercially available aluminium-type research reactor fuels is generally considered to be about 1.7 g cm -3 . With this density limitation, the minimum enrichment to maintain present reactivity per plate is about 35 per cent 235 U. For low enrichment (max. 20 per cent 235 U) fuel, the required U density is about 2.9 g cm -3 , which is beyond the expected range for UAl/sub x/-Al but within that projected for the longer term development and full qualification for U 3 O 8 -Al. Medium enrichment (nominally 45 per cent 235 U) Al/sub x/-Al would be entirely satisfactory as an immediate replacement fuel, requiring no modifications to the reactor and operating procedures, and minimal reappraisal of safety issues. Included in this study are calculations of the fuel coefficients at various enrichments, the effect of replacing standard fuel plates or complete elements with 45 per cent enriched fuel, and the reactivity to be gained by replacing 12-plate with 13-plate elements

WWER-1000 reactor simulator. Workshop material

International Nuclear Information System (INIS)

2003-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series 12, 'Reactor Simulator Development' (2001). Course material for workshops using a pressurized water reactor (PWR) Simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada is presented in the IAEA publication: Training Course Series No. 22 'Pressurized Water Reactor Simulator' (2003) and Training Course Series No. 23 'Boiling Water Reactor Simulator' (2003). This report consists of course material for workshops using the WWER-1000 Reactor Department Simulator from the Moscow Engineering and Physics Institute, Russian Federation. N. V. Tikhonov and S. B. Vygovsky of the Moscow Engineering and Physics Institute prepared this report for the IAEA

Boiling water reactor simulator. Workshop material

International Nuclear Information System (INIS)

2003-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and workshop material and sponsors workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 simulator from the Moscow Engineering and Physics Institute, Russian Federation is presented in the IAEA publication: Training Course Series No. 21 'WWER-1000 Reactor Simulator' (2002). Course material for workshops using a pressurized water reactor (PWR) simulator developed by Cassiopeia Technologies Incorporated, Canada, is presented in the IAEA publication: Training Course Series No. 22 'Pressurized Water Reactor Simulator' (2003). This report consists of course material for workshops using a boiling water reactor (BWR) simulator. Cassiopeia Technologies Incorporated, developed the simulator and prepared this report for the IAEA

Evaluation of echogenicity of the heart in Kawasaki disease.

Science.gov (United States)

Nagata, Hazumu; Yamamura, Kenichiro; Uike, Kiyoshi; Nakashima, Yasutaka; Hirata, Yuichiro; Morihana, Eiji; Mizuno, Yumi; Ishikawa, Shiro; Hara, Toshiro

2014-08-01

Pathologic studies of the heart in patients with Kawasaki disease (KD) revealed vasculitis, valvulitis, myocarditis, and pericarditis. However, there have been no studies on the quantitative determination of multi-site echogenicity of the heart in KD patients. It is also undetermined whether the degree of echogenicity of each site of the heart in patients with KD might be related to the response to intravenous immunoglobulin (IVIG) treatment. In 81 KD patients and 30 control subjects, we prospectively analyzed echogenicity of the heart. Echogenicity was measured in four sites: coronary artery wall (CAW), mitral valve (MV), papillary muscle (PM), and ascending aortic wall (AAo wall) by the calibrated integrated backscatters (cIBs). The cIB values of all measurement sites at acute phase in KD patients were significantly higher than those in control subjects (KD patients vs control subjects; CAW, 19.8 ± 6.2 dB vs 14.5 ± 2.0 dB, p IVIG nonresponders were significantly higher than those in responders. Conclusion: Echogenicity of the heart in KD patients at the acute phase increased not only in the coronary artery wall but also in other parts of the heart. Echogenicity of CAW might be helpful in determining the unresponsiveness of IVIG treatment.

The reactor trainer: state-of-the-art classroom learning

International Nuclear Information System (INIS)

Stater, R.G.

1996-01-01

The Reactor Trainer is a professional, PC based, graphically enhanced, training resource specifically developed and customized for Class Room teaching of and learning about, reactor behavior. This unique, and focused, learning-target sets The Trainer apart from the panorama of the more common PC plant simulator. Its educational scope extends along a logical learning path, starting with important fundamental behavioral concepts of delayed neutrons, neutron multiplying factors, and reactor rate, moving to simple reactor transients in real time, and culminating with more complex operational evolutions. The Trainer empowers the Instructor with a dynamic Class Room demonstrator and the student with a superior hands-on learning tool. The Trainer's versatility encompasses a wide variety of educational needs, including initial operator training, requalification training, Shift Technical Advisor training, and other advanced or specialized training. In addition, The Reactor Trainer enhances prerequisite preparation of operator candidates for full-scale control room training and, in so doing, PC economics relieves full-scale simulator hours. (author)

Monju operator training report. Training results and upgrade of the operation training simulator in 2002 YF

International Nuclear Information System (INIS)

Koyagoshi, Naoki; Sasaki, Kazuichi; Sawada, Makoto; Kawanishi, Tomotake; Yoshida, Kazuo

2003-09-01

The prototype fast breeder reactor, Monju, has been performing deliberately the operator training which is composed of the regulated training required by the government and the self-training. The training used a full scope type simulator (MARS: Monju Advanced Reactor Simulator) plays an important role among of the above mentioned trainings and greatly contributes to the Monju operator training for Monju restarting. This report covers the activities of Monju operator training in 2002 FY, i.e. the training results and the remodeling working of the MARS in progress since 1999. (1) Eight simulator training courses were carried out 46 times and 180 trainees participated. Additionally, both the regulated training and self-training were held total 10 times by attended 34 trainees, as besides simulator training. (2) Above training data was reduced compare with the last year's data (69 times (338 trainees)) due to the indispensable training courses in Monju operator training were changed by reorganized operator's number and decreasing of training times owing to remodeling working of the simulator was conducted. (3) By means of upgrading of the MARS completed in 2002 FY, its logic arithmetic time was became speedier and its instructing function was improved remarkably, thus, the simulator training was became to be more effective. Moreover, it's planning to do both remodeling in the next year as the final working: remodeling of reactor core model with the aim of improvement simulating accuracy and corresponding to the sodium leakage measures. Regarding on the Monju training results and simulator's remodeling so far finished, please referring JNC report number of JNC TN 4410 2002-001 Translation of Monju Simulator Training owing Monju Accident and Upgrade of MARS''. (author)

Studies of thermal-hydraulics and plant systems for actinide burning fast reactor concept

International Nuclear Information System (INIS)

Yamazaki, Seiichiro; Misumi, Masahiro; Izaki, Makoto; Koike, Hiroyuki; Tanaka, Ryokichi

1984-01-01

As one of the methods to dispose long life actinide nuclides, the actinide burning fast reactor using only actinide wastes as the fuel has been proposed. Kawasaki Heavy Industries Ltd. carried out the conceptual examination on the ABFR cooled with helium gas, cooperating with Japan Atomic Energy Research Institute, and its feasibility and problems were clarified. In this report, the setting-up of various fundamental dimensions by the parameter survey of the thermal and flowing performance of the core, the examination of the thermal and flowing characteristics of the core based on the detailed power distribution, and the examination of the plant system centering around the main cooling system are outlined. The fuel is composed of actinide oxide and diluent MgO. The diluent is used for obtaining proper excess reactivity, and MgO has been taken up also in foreign countries, considering the compatibility with actinide oxide, the easiness of reprocessing and manufacture. The fuel element is of pin type, and actinide oxide and MgO pellets are in a SUS 316 cladding tube. This ABFR can treat the wastes from ten 1000 MWe power reactors, and has the power output of about 1000 MWt. (Kako, I.)

PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Masood, Z.

2016-01-01

The PUSPATI TRIGA Reactor is the only research reactor in Malaysia. This 1 MW TRIGA Mk II reactor first reached criticality on 28 June 1982 and is located at the Malaysian Nuclear Agency premise in Bangi, Malaysia. This reactor has been mainly utilised for research, training and education and isotope production. Over the years several systems have been refurbished or modernised to overcome ageing and obsolescence problems. Major achievements and milestones will also be elaborated in this paper. (author)

Sharing of Rensselaer Polytechnic Institute Reactor Critical Facility (RCF)

International Nuclear Information System (INIS)

1995-01-01

The RPI Reactor Critical Facility (RCF) operated successfully over the period fall 1994 - fall 1995. During this period, the RCF was used for Critical Reactor Laboratory spring 1995 (12 students); Reactor Operations Training fall 1994 (3 students); Reactor Operations Training spring 1995 (3 students); and Reactor Operations Training fall 1995 (3 students). Thirty-two Instrumentation and Measurement students used the RCF for one class for hands-on experiments with nuclear instruments. In addition, a total of nine credits of PhD thesis work were carried out at the RCF. This document constitutes the 1995 Report of the Rensselaer Polytechnic Institute's Reactor Critical Facility (RCF) to the USNRC, to the USDOE, and to RPI management

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

International Nuclear Information System (INIS)

Matejka, Karel; Sklenka, Lubomir

1997-01-01

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

Design of a Control Room for Jordan Research and Training Reactor (JRTR)

Energy Technology Data Exchange (ETDEWEB)

Kim, Yong Jun; Suh, Sang Moon; Lee, Hyun Chul; Park, Je Yun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

Since the main role of JRTR(Jordan Research and Training Reactor) operating personnel is safe and reliable operation of the reactor, MCR(Main Control Room) and SCR(Supplementary Control Room) must provide them with sufficient information and controls needed to optimize their performance. Before the TMI accident, control room were generally designed just with intuitive common sense, without using any proper HFE(human factors engineering) practices. Many results derived from the analysis of TMI accident showed that a more comprehensive and systematic approaches to develop MCR design requirements were needed. Moreover changes of operators' role as a decision maker from a physical controller in rapid improvement of control system which resulted in higher automation clearly needed more featured regulatory requirements and guidelines. So many regulatory and industrial guidance for control room design have been developed by relevant institution and regulatory bodies. In this paper, a conceptual design of the JRTR control room in the effort of satisfying current regulatory requirements and guidelines are presented. And some information display design is also presented

Safety Evaluation Report related to the renewal of the operating license for the TRIGA training and research reactor at the University of Utah (Docket No. 50-407)

International Nuclear Information System (INIS)

1985-03-01

This Safety Evaluation Report for the application filed by the University of Utah (UU) for a renewal of operating license R-126 to continue to operate a training and research reactor facility has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the University of Utah and is located on its campus in Salt Lake City, Salt Lake County, Utah. The staff concludes that this training reactor facility can continue to be operated by UU without endangering the health and safety of the public

Kawasaki steam power plant of Tokyo Electric Power Co. and an example of geothermal power generation

Energy Technology Data Exchange (ETDEWEB)

1961-01-01

The first part of this discussion is devoted to a description of the Kawasaki steam power plant, installed by Tokyo Electric Co. to supply electricity to the Keihin industrial area. The output is 700 MW and it possesses a thermal efficiency of 36.9%. The plant is operated automatically by remote control. The latter section describes the status of a geothermal power station in Hakone. It outlines the steam distribution piping, the steam itself, the turbine and vapor/water separation equipment. With regard to technical problems, it is suggested that old wells having weak pressure can be restored by self-cleaning and that further improvement can be brought about by dynamiting the base of the borehole.

Reactivity worth measurement of the control blades of the University of Florida training reactor

International Nuclear Information System (INIS)

Quintero-Leyva, Barbaro

1997-01-01

A series of experiments were carried out in order to measure the reactivity worth of the safety and regulating blades of the University of Florida Training Reactor (UFTR) using the Inverse Kinetics, the Inverse Kinetics-Rod Drop method and the Power Ratio. The reactor's own instrumentation (compensated ion chamber) and an independent counting system (fission chamber) were used. A very smooth exponential decay of the flux was observed after 6s of the beginning of the transients using the reading of the reactor detector. The results of the measurements of the reactivity using both detectors were consistent and in good agreement. The compensated ion chamber showed a very smooth exponential behavior; this suggests that if we could record the power for a small sample time, say 0.1 s from the beginning of the transient, several additional research projects could be accomplished. First, precise intercomparison of the methods could be achieved if the statistics level is acceptable. Second, a precise description of the bouncing of the blades and its effects on the reactivity could be achieved. Finally, the design of a reactivity-meter could be based on such study. (author)

Storage experience in Hungary with fuel from research reactors

International Nuclear Information System (INIS)

Gado, J.; Hargitai, T.

1996-01-01

In Hungary several critical assemblies, a training reactor and a research reactor have been in operation. The fuel used in the research and training reactors are of Soviet origin. Though spent fuel storage experience is fairly good, medium and long term storage solutions are needed. (author)

The computer aided education and training system for accident management

International Nuclear Information System (INIS)

Yoneyama, Mitsuru; Masuda, Takahiro; Kubota, Ryuji; Fujiwara, Tadashi; Sakuma, Hitoshi

2000-01-01

Under severe accident conditions of a nuclear power plant, plant operators and technical support center (TSC) staffs will be under a amount of stress. Therefore, those individuals responsible for managing the plant should promote their understanding about the accident management and operations. Moreover, it is also important to train in ordinary times, so that they can carry out accident management operations effectively on severe accidents. Therefore, the education and training system which works on personal computers was developed by Japanese BWR group (Tokyo Electric Power Co.,Inc., Tohoku Electric Power Co. ,Inc., Chubu Electric Power Co. ,Inc., Hokuriku Electric Power Co.,Inc., Chugoku Electric Power Co.,Inc., Japan Atomic Power Co.,Inc.), and Hitachi, Ltd. The education and training system is composed of two systems. One is computer aided instruction (CAI) education system and the other is education and training system with a computer simulation. Both systems are designed to execute on MS-Windows(R) platform of personal computers. These systems provide plant operators and technical support center staffs with an effective education and training tool for accident management. TEPCO used the simulation system for the emergency exercise assuming the occurrence of hypothetical severe accident, and have performed an effective exercise in March, 2000. (author)

Reactor simulator development. Workshop material

International Nuclear Information System (INIS)

2001-01-01

The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in reactor operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. This publication consists of course material for workshops on development of such reactor simulators. Participants in the workshops are provided with instruction and practice in the development of reactor simulation computer codes using a model development system that assembles integrated codes from a selection of pre-programmed and tested sub-components. This provides insight and understanding into the construction and assumptions of the codes that model the design and operational characteristics of various power reactor systems. The main objective is to demonstrate simple nuclear reactor dynamics with hands-on simulation experience. Using one of the modular development systems, CASSIM tm , a simple point kinetic reactor model is developed, followed by a model that simulates the Xenon/Iodine concentration on changes in reactor power. Lastly, an absorber and adjuster control rod, and a liquid zone model are developed to control reactivity. The built model is used to demonstrate reactor behavior in sub-critical, critical and supercritical states, and to observe the impact of malfunctions of various reactivity control mechanisms on reactor dynamics. Using a PHWR simulator, participants practice typical procedures for a reactor startup and approach to criticality. This workshop material consists of an introduction to systems used for developing reactor simulators, an overview of the dynamic simulation

Training at the masters degree level in physics and technology of nuclear reactors in the uk

International Nuclear Information System (INIS)

Weaver, D.R.

2000-01-01

This paper discusses the current situation of university-based training for the nuclear power industry in the UK, drawing on information gathered as part of the survey for a review currently being undertaken by the Committee for Technical and Economic Studies on Nuclear Energy Development and Fuel Cycle (NDC) of the Nuclear Energy Agency (NEA) of the OECD. A particular focus will be the Physics and Technology of Nuclear Reactors MSc course at the University of Birmingham. In the past there were other similar MSc courses in the UK, but through the evolution of time the Birmingham course is now unique in its role of providing masters level training so specifically aimed at the commercial nuclear programme. Mention will, however, be made of other training at the postgraduate level elsewhere in the UK. A description is given of the need to consider a new form of relationship between industry and university in order to provide optimise the provision of masters level training. (author)

Thermohydraulics of reactors

International Nuclear Information System (INIS)

Delhaye, J.M.

2008-01-01

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

IV Training program for the staff of the laboratory for the RA reactor exploitation; IV Programi obuke osoblja Laboratorije za eksploataciju reaktora RA

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-07-01

All the staff members of the laboratory for RA reactor exploitation are obliged to learn the following: fundamental properties of the RA reactor, the role and functionality of the reactor components, basic and auxiliary reactor systems, basics of radioactivity, measures for preventing contamination. The personnel working in shifts must be acquainted with the regulations and instructions for reactor operation. Training programs for reactor operators, mechanics, electricians, instrumentators and dosimetrysts are described separately. Svi saradnici Laboratorije za eksploataciju reaktora RA moraju poznavati sledece oblasti: Osnovne karakeristike reaktora RA, princip rada, ulogu i funkcionisanje komponenti reaktora, osnovnih i pomocnih sistema reaktora; osnovne pojmove o radioaktivnom zracenju, mere za sprecavanje kontaminacije. Osoblje koje radi u smenama mora dodatno poznavati propise i uputstva za rad reaktora. Posebno je naveden program obuke operatora reaktora, mehanicara, electricara, instrumentatora, dozimetrista.

U.S. Department of Energy University Reactor Instrumentation Program Final Report for 1992-94 Grant for the University of Florida Training Reactor

International Nuclear Information System (INIS)

Vernetson, William G.

1999-01-01

Overall, the instrumentation obtained under the first year 1992-93 University Reactor Instrumentation Program grant assured that the goals of the program were well understood and met as well as possible at the level of support provided for the University of Florida Training Reactor facility. Though the initial grant support of $21,000 provided toward the purchase of $23,865 of proposed instrumentation certainly did not meet many of the facility's needs, the instrumentation items obtained and implemented did meet some critical needs and hence the goals of the Program to support modernization and improvement of reactor facilities such as the UFTR within the academic community. Similarly, the instrumentation obtained under the second year 1993-94 University Reactor Instrumentation Program grant again met some of the critical needs for instrumentation support at the UFTR facility. Again, though the grant support of $32,799 for proposed instrumentation at the same cost projection does not need all of the facility's needs, it does assure continued facility viability and improvement in operations. Certainly, reduction of forced unavailability of the reactor is the most obvious achievement of the University Reactor Instrumentation Program to date at the UFTR. Nevertheless, the ability to close out several expressed-inspection concerns of the Nuclear Regulatory Commission with acquisition of the low level survey meter and the area radiation monitoring system is also very important. Most importantly, with modest cost sharing the facility has been able to continue and even accelerate the improvement and modernization of a facility, especially in the Neutron Activation Analysis Laboratory, that is used by nearly every post-secondary school in the State of Florida and several in other states, by dozens of departments within the University of Florida, and by several dozen high schools around the State of Florida on a regular basis. Better, more reliable service to such a broad

Pressurized water reactor simulator. Workshop material. 2. ed

International Nuclear Information System (INIS)

2005-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development. And the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 reactor department simulator from the Moscow Engineering and Physics Institute, the Russian Federation is presented in the IAEA Training Course Series No. 21, 2nd edition, 'WWER-1000 Reactor Simulator' (2005). Course material for workshops using a boiling water reactor simulator developed for the IAEA by Cassiopeia Technologies Incorporated of Canada (CTI) is presented in the IAEA publication: Training Course Series No.23, 2nd edition, 'Boiling Water Reactor Simulator' (2005). This report consists of course material for workshops using a pressurized water reactor simulator

Guidance for training program evaluation

International Nuclear Information System (INIS)

1984-01-01

An increased concern about the training of nuclear reactor operators resulted from the incident at TMI-2 in 1979. Purpose of this guide is to provide a general framework for the systematic evaluation of training programs for DOE Category-A reactors. The primary goal of such evaluations is to promote continuing quality improvements in the selection, training and qualification programs

Parental anxiety associated with Kawasaki disease in previously healthy children.

Science.gov (United States)

Chahal, Nita; Clarizia, Nadia A; McCrindle, Brian W; Boydell, Katherine M; Obadia, Maya; Manlhiot, Cedric; Dillenburg, Rejane; Yeung, Rae S M

2010-01-01

The objective of this study was to explore the lived experience of parents of children diagnosed with Kawasaki disease (KD) and to identify factors associated with increased levels of parental anxiety. Three focus groups were conducted including 25 parents of 17 patients with KD, seven (41%) of whom had coronary artery complications. A conceptual model was developed to depict parental experiences and illustrate the key issues related to heightened anxiety. Themes identified included anxiety related to the child's sudden illness and delay in obtaining a correct diagnosis because of the lack of health care providers' awareness and knowledge regarding KD. Parents were frustrated by the lack of information available in lay language and the limited scientific knowledge regarding the long-term consequences of the disease. Parents also reported positive transformations and different perspective toward challenges in life. However, the parents of children with coronary artery complications expressed persistent anxiety even years after the acute phase of the illness due to the uncertainty of the long-term prognosis. There remains a critical need for richly textured research data on the perspective and experience of families of children with KD. Copyright 2010 National Association of Pediatric Nurse Practitioners. Published by Mosby, Inc. All rights reserved.

Research reactors and materials testing

International Nuclear Information System (INIS)

Vidal, H.

1986-01-01

Research reactors can be classified in three main groups according to the moderator which is used. Their technical characteristics are given and the three most recent research and materials testing reactors are described: OSIRIS, ORPHEE and the high-flux reactor of Grenoble. The utilization of research reactors is reviewed in four fields of activity: training, fundamental or applied research and production (eg. radioisotopes) [fr

Research Reactor Utilization at the University of Utah for Nuclear Education, Training and Services

International Nuclear Information System (INIS)

Jevremovic, T.; Choe, D.O.

2013-01-01

In the years of nuclear renaissance we all recognize a need for modernizing the approaches in fostering nuclear engineering and science knowledge, in strengthening disciplinary depth in students’ education for their preparation for workforce, and in helping them learn how to extend range of skills, develop habits of mind and subject matter knowledge. The education infrastructure at the University of Utah has been recently revised to incorporate the experiential learning using our research reactor as integral part of curriculum, helping therefore that all of our students build sufficient level of nuclear engineering literacy in order to be able to contribute productively to nuclear engineering work force or continue their education toward doctoral degrees. The University of Utah TRIGA Reactor built 35 years ago represents a university wide facility to promote research, education and training, as well as is used for various applications of nuclear engineering, radiation science and health physics. Our curriculum includes two consecutive classes for preparation of our students for research reactor operating license. Every year the US Nuclear Regulatory Commission’s representatives hold the final exam for our students. Our activities serve the academic community of the University of Utah, commercial and government entities, other universities and national laboratories as well. (author)

Radiation field studies at the training and research reactor AKR of the Dresden Technical University

International Nuclear Information System (INIS)

Leuschner, A.; Reiss, U.; Pretzsch, G.

1983-01-01

Results of radiation field studies in the experimental channels of the training and research reactor of the Technical University of Dresden are presented. The flux densities of thermal, intermediate and fast neutrons were determined by means of activation detectors., Gamma dose rates have been measured by thermoluminescent dosimeters. The measured results show symmetry with respect to the vertical axis of the reactor and allow to draw conclusions with regard to the efficiency of the individual layers of the shield. They are an essential basis of performing irradiation experiments in the experimental channels. The results of measurements were compared with those of shielding and design calculations. Taking into account the measuring errors and the approximations used in the computational models, no unexpected deviations have been observed. Hence, the measured and calculated results can be assessed to be in good agreement. (author)

TRIGA reactor characteristics

International Nuclear Information System (INIS)

Boeck, H.; Villa, M.

2007-01-01

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

Kawasaki Disease With Coronary Artery Aneurysms: Psychosocial Impact on Parents and Children.

Science.gov (United States)

Chahal, Nita; Jelen, Ahlexxi; Rush, Janet; Manlhiot, Cedric; Boydell, Katherine M; Sananes, Renee; McCrindle, Brian W

For those living with Kawasaki disease and coronary artery aneurysms, little is known about the psychosocial burden faced by parents and their children. Exploratory, descriptive, mixed-methods design examining survey and interview data about health-related uncertainty, intrusiveness, and self-efficacy. Parents' uncertainty was associated with missed diagnosis, higher income, and maternal education. Higher uncertainty scores among children were associated with absence of chest pain and lower number of echocardiograms. High intrusiveness scores among parents were associated with previous cardiac catheterization, use of anticoagulants, lower parent education and income, and missed diagnosis. High intrusiveness scores among children were associated with high paternal education. Children's total self-efficacy scores increased with chest pain and larger aneurysm size. Qualitative analysis showed two central themes: Psychosocial Struggle and Cautious Optimism. Negative illness impact is associated with a more intense medical experience and psychosocial limitations. Timely assessment and support are warranted to meet parents' and children's needs. Copyright © 2016 National Association of Pediatric Nurse Practitioners. Published by Elsevier Inc. All rights reserved.

[Giant coronary aneurysms in infants with Kawasaki disease].

Science.gov (United States)

Sánchez Andrés, Antonio; Salvador Mercader, Inmaculada; Seller Moya, Julia; Carrasco Moreno, José Ignacio

2017-08-01

Kawasaki disease (KD) is an acute vasculitis of unknown origin and predominant in males. The long-term effects of the disease depend on whether there are coronary lesions, particularly aneurysms. The prognosis of patients with giant aneurysms is very poor due to their natural progression to coronary thrombosis or severe obstructive lesions. A series of 8 cases is presented where the epidemiology and diagnostic methods are described. The treatment of the acute and long-term cardiovascular sequelae is also reviewed. A descriptive analysis was conducted on patients admitted to the Paediatric Cardiology Unit of La Fe University Hospital (Valencia) with KD and a coronary lesion. More than one artery was involved in all patients. Although early diagnosis was established in only two cases, none of the patients had severe impairment of ventricular function during the acute phase. Treatment included intravenous gammaglobulin and acetylsalicylic acid at anti-inflammatory doses during the acute phase. A combination of dual antiplatelet therapy and corticosteroids was given in cases of coronary thrombosis. The silent aneurysms continue to persist. KD is the most common cause of acquired heart disease in children. The delay in diagnosis is associated with a greater likelihood of coronary lesions that could increase the risk of cardiovascular events in adulthood. Thus, this subgroup requires close clinical monitoring for a better control of cardiovascular risk factors over time. Copyright © 2016 Asociación Española de Pediatría. Publicado por Elsevier España, S.L.U. All rights reserved.

Atypical Kawasaki Disease Presenting with Hemiparesis and Aphasia: A Case Report

Directory of Open Access Journals (Sweden)

Ali Nikkhah

2018-01-01

Full Text Available Kawasaki disease (KD is an inflammatory vasculitis. KD is classified into two groups based on clinical characteristics criteria, namely classic and incomplete. Cerebral vascular abnormality, especially arterial ischemic stroke (AIS is very rare and unusual in KD. Here, we report a 4-year-old boy who was referred to our tertiary pediatric center with abrupt right hemiparesis and aphasia. At admission time, he had febrile illness and was toxic. On physical examination, we found unilateral left submandibular lymphadenopathy. On neurologic examination, we obtained right sided hemiparesis with hemiparetic gait and aphasia. His deep tendon reflexes (DTRs of right extremities were exaggerated and his sensory system was intact. Based on these features, some differential diagnoses were suggested, such as acute encephalitis with focal signs, brain abscess, cerebral vasculitis, hemorrhagic insults, and ischemic stroke, etc. After a complete evaluation, especially brain MRI and MRA, our diagnosis was arterial ischemic stroke (AIS following atypical KD. Based on these findings, we administered intravenous immunoglobulin (IVIG 2 gm/kg and oral high dose aspirin (100 mg/kg/d. He responded to these anti-inflammatory treatments dramatically.

Perspectives on reactor safety

Energy Technology Data Exchange (ETDEWEB)

Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

1994-03-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

Perspectives on reactor safety

International Nuclear Information System (INIS)

Haskin, F.E.

1994-03-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

Impact of proposed research reactor standards on reactor operation

Energy Technology Data Exchange (ETDEWEB)

Ringle, J C; Johnson, A G; Anderson, T V [Oregon State University (United States)

1974-07-01

A Standards Committee on Operation of Research Reactors, (ANS-15), sponsored by the American Nuclear Society, was organized in June 1971. Its purpose is to develop, prepare, and maintain standards for the design, construction, operation, maintenance, and decommissioning of nuclear reactors intended for research and training. Of the 15 original members, six were directly associated with operating TRIGA facilities. This committee developed a standard for the Development of Technical Specifications for Research Reactors (ANS-15.1), the revised draft of which was submitted to ANSI for review in May of 1973. The Committee then identified 10 other critical areas for standards development. Nine of these, along with ANS-15.1, are of direct interest to TRIGA owners and operators. The Committee was divided into subcommittees to work on these areas. These nine areas involve proposed standards for research reactors concerning: 1. Records and Reports (ANS-15.3) 2. Selection and Training of Personnel (ANS-15.4) 3. Effluent Monitoring (ANS-15.5) 4. Review of Experiments (ANS-15.6) 5. Siting (ANS-15.7) 6. Quality Assurance Program Guidance and Requirements (ANS-15.8) 7. Restrictions on Radioactive Effluents (ANS-15.9) 8. Decommissioning (ANS-15.10) 9. Radiological Control and Safety (ANS-15.11). The present status of each of these standards will be presented, along with their potential impact on TRIGA reactor operation. (author)

Impact of proposed research reactor standards on reactor operation

International Nuclear Information System (INIS)

Ringle, J.C.; Johnson, A.G.; Anderson, T.V.

1974-01-01

A Standards Committee on Operation of Research Reactors, (ANS-15), sponsored by the American Nuclear Society, was organized in June 1971. Its purpose is to develop, prepare, and maintain standards for the design, construction, operation, maintenance, and decommissioning of nuclear reactors intended for research and training. Of the 15 original members, six were directly associated with operating TRIGA facilities. This committee developed a standard for the Development of Technical Specifications for Research Reactors (ANS-15.1), the revised draft of which was submitted to ANSI for review in May of 1973. The Committee then identified 10 other critical areas for standards development. Nine of these, along with ANS-15.1, are of direct interest to TRIGA owners and operators. The Committee was divided into subcommittees to work on these areas. These nine areas involve proposed standards for research reactors concerning: 1. Records and Reports (ANS-15.3) 2. Selection and Training of Personnel (ANS-15.4) 3. Effluent Monitoring (ANS-15.5) 4. Review of Experiments (ANS-15.6) 5. Siting (ANS-15.7) 6. Quality Assurance Program Guidance and Requirements (ANS-15.8) 7. Restrictions on Radioactive Effluents (ANS-15.9) 8. Decommissioning (ANS-15.10) 9. Radiological Control and Safety (ANS-15.11). The present status of each of these standards will be presented, along with their potential impact on TRIGA reactor operation. (author)

Training and training simulators for emergency situations in France

International Nuclear Information System (INIS)

Petit, G.

1990-01-01

The aim of this paper is to present principles and means set up by Electricite de France (E.D.F.) to provide the required tailor-made training. Today, recent advantages in computing capacities and software engineering along with the completion of Research and Development Training Division programs in the reactor safety (R+D) field (CATHARE, BETHSY..) give E.D.F. the opportunity to conceive and operate new tools for training which are described in the paper: RTGV-SEPIA: a simulator devoted to self training in SGTR field, thanks to a powerful expert system. SIPA: a 'generator of simulators' aiming at control and engineering studies and training, provided with a software able to give in real time a relevant description of complex topologies with diphasic flow patterns (up to a 12'' break in the primary coolant system of a reactor). (orig./DG) [de

Seasonality of Kawasaki Disease: A Global Perspective

Science.gov (United States)

Burns, Jane C.; Herzog, Lauren; Fabri, Olivia; Tremoulet, Adriana H.; Rodó, Xavier; Uehara, Ritei; Burgner, David; Bainto, Emelia; Pierce, David; Tyree, Mary; Cayan, Daniel

2013-01-01

Background Understanding global seasonal patterns of Kawasaki disease (KD) may provide insight into the etiology of this vasculitis that is now the most common cause of acquired heart disease in children in developed countries worldwide. Methods Data from 1970-2012 from 25 countries distributed over the globe were analyzed for seasonality. The number of KD cases from each location was normalized to minimize the influence of greater numbers from certain locations. The presence of seasonal variation of KD at the individual locations was evaluated using three different tests: time series modeling, spectral analysis, and a Monte Carlo technique. Results A defined seasonal structure emerged demonstrating broad coherence in fluctuations in KD cases across the Northern Hemisphere extra-tropical latitudes. In the extra-tropical latitudes of the Northern Hemisphere, KD case numbers were highest in January through March and approximately 40% higher than in the months of lowest case numbers from August through October. Datasets were much sparser in the tropics and the Southern Hemisphere extra-tropics and statistical significance of the seasonality tests was weak, but suggested a maximum in May through June, with approximately 30% higher number of cases than in the least active months of February, March and October. The seasonal pattern in the Northern Hemisphere extra-tropics was consistent across the first and second halves of the sample period. Conclusion Using the first global KD time series, analysis of sites located in the Northern Hemisphere extra-tropics revealed statistically significant and consistent seasonal fluctuations in KD case numbers with high numbers in winter and low numbers in late summer and fall. Neither the tropics nor the Southern Hemisphere extra-tropics registered a statistically significant aggregate seasonal cycle. These data suggest a seasonal exposure to a KD agent that operates over large geographic regions and is concentrated during winter

Over Twenty Years Of Experience In ITU TRIGA MARK-II Reactor

International Nuclear Information System (INIS)

Yavuz, Hasbi

2008-01-01

I.T.U. TRIGA MARK-II Training and Research Reactor, rated at 250 kW steady-state and 1200 MW pulsing power is the only research and training reactor owned and operated by a university in Turkey. Reactor has been operating since March 11, 1979; therefore the reactor has been operating successfully for more than twenty years. Over the twenty years of operation: - The tangential beam tube was equipped with a neutron radiography facility, which consists of a divergent collimator and exposure room; - A computerized data acquisition system was designed and installed such that all parameters of the reactor, which are observed from the console, could be monitored both in normal and pulse operations; - An electrical power calibration system was built for the thermal power calibration of the reactor; - Publications related with I.T.U. TRIGA MARK-II Training and Research Reactor are listed in Appendix; - Two majors undesired shutdown occurred; - The I.T.U. TRIGA MARK-II Training and Research Reactor is still in operation at the moment. (authors)

Research reactor support

International Nuclear Information System (INIS)

2005-01-01

Research reactors (RRs) have been used in a wide range of applications including nuclear power development, basic physics research, education and training, medical isotope production, geology, industry and other fields. However, many research reactors are fuelled with High Enriched Uranium (HEU), are underutilized and aging, and have significant quantities of spent fuel. HEU inventories (fresh and spent) pose security risks Unavailability of a high-density-reprocessable fuel hinders conversion and limits back-end options and represents a survival dilemma for many RRs. Improvement of interim spent fuel storage is required at some RRs. Many RRs are under-utilized and/or inadequately funded and need to find users for their services, or permanently shut down and eventually decommission. Reluctance to decommission affect both cost and safety (loss of experienced staff ) and many shut down but not decommissioned RR with fresh and/or spent fuel at the sites invoke serious concern. The IAEA's research reactor support helps to ensure that research reactors can be operated efficiently with fuels and targets of lower proliferation and security concern and that operators have appropriate technology and options to manage RR fuel cycle issues, especially on long term interim storage of spent research reactor fuel. Availability of a high-density-reprocessable fuel would expand and improve back end options. The International Atomic Energy Agency provides assistance to Member States to convert research reactors from High Enriched Uranium fuel and targets (for medical isotope production) to qualified Low Enriched Uranium fuel and targets while maintaining reactor performance levels. The assistance includes provision of handbooks and training in the performance of core conversion studies, advice for the procurement of LEU fuel, and expert services for LEU fuel acceptance. The IAEA further provides technical and administrative support for countries considering repatriation of its

Thermal limits validation of gamma thermometer power adaption in CFE Laguna Verde 2 reactor core

Energy Technology Data Exchange (ETDEWEB)

Cuevas V, G.; Banfield, J. [GE-Hitachi Nuclear Energy Americas LLC, Global Nuclear Fuel, Americas LLC, 3901 Castle Hayne Road, Wilmingtonm, North Carolina (United States); Avila N, A., E-mail: Gabriel.Cuevas-Vivas@ge.com [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km 42.5, Alto Lucero, Veracruz (Mexico)

2016-09-15

This paper presents the status of GEH work on Gamma Thermometer (GT) validation using the signals of the instruments installed in the Laguna Verde Unit 2 reactor core. The long-standing technical collaboration between Comision Federal de Electricidad (CFE), Global Nuclear Fuel - Americas LLC (GNF) and GE-Hitachi Nuclear Energy Americas LLC (GEH) is moving forward with solid steps to a final implementation of GTs in a nuclear reactor core. Each GT is integrated into a slightly modified Local Power Range Monitor (LPRM) assembly. Six instrumentation strings are equipped with two gamma field detectors for a total of twenty-four bundles whose calculated powers are adapted to the instrumentation readings in addition to their use as calibration instruments for LPRMs. Since November 2007, the six GT instrumentation strings have been operable with almost no degradation by the strong neutron and gamma fluxes in the Laguna Verde Unit 2 reactor core. In this paper, the thermal limits, Critical Power Ratio (CPR) and maximum Linear Heat Generation Rate (LHGR), of bundles directly monitored by either Traverse In-core Probes (TIPs) or GTs are used to establish validation results that confirm the viability of TIP system replacement with automatic fixed in-core probes (AFIPs, GTs, in a Boiling Water Reactor. The new GNF steady-state reactor core simulator AETNA02 is used to obtain power and exposure distribution. Using this code with an updated methodology for GT power adaption, a reduced value of the GT interpolation uncertainty is obtained that is fed into the LHGR calculation. This new method achieves margin recovery for the adapted thermal limits for use in the Economic Simplified Boiling Water Reactor (ESBWR) or any other BWR in the future that employs a GT based AFIP system for local power measurements. (Author)

Thermal limits validation of gamma thermometer power adaption in CFE Laguna Verde 2 reactor core

International Nuclear Information System (INIS)

Cuevas V, G.; Banfield, J.; Avila N, A.

2016-09-01

This paper presents the status of GEH work on Gamma Thermometer (GT) validation using the signals of the instruments installed in the Laguna Verde Unit 2 reactor core. The long-standing technical collaboration between Comision Federal de Electricidad (CFE), Global Nuclear Fuel - Americas LLC (GNF) and GE-Hitachi Nuclear Energy Americas LLC (GEH) is moving forward with solid steps to a final implementation of GTs in a nuclear reactor core. Each GT is integrated into a slightly modified Local Power Range Monitor (LPRM) assembly. Six instrumentation strings are equipped with two gamma field detectors for a total of twenty-four bundles whose calculated powers are adapted to the instrumentation readings in addition to their use as calibration instruments for LPRMs. Since November 2007, the six GT instrumentation strings have been operable with almost no degradation by the strong neutron and gamma fluxes in the Laguna Verde Unit 2 reactor core. In this paper, the thermal limits, Critical Power Ratio (CPR) and maximum Linear Heat Generation Rate (LHGR), of bundles directly monitored by either Traverse In-core Probes (TIPs) or GTs are used to establish validation results that confirm the viability of TIP system replacement with automatic fixed in-core probes (AFIPs, GTs, in a Boiling Water Reactor. The new GNF steady-state reactor core simulator AETNA02 is used to obtain power and exposure distribution. Using this code with an updated methodology for GT power adaption, a reduced value of the GT interpolation uncertainty is obtained that is fed into the LHGR calculation. This new method achieves margin recovery for the adapted thermal limits for use in the Economic Simplified Boiling Water Reactor (ESBWR) or any other BWR in the future that employs a GT based AFIP system for local power measurements. (Author)

Li2O-pebble type tritium breeding blanket for fusion experimental reactor, 1

International Nuclear Information System (INIS)

Tone, Tatsuzo; Iida, Hiromasa; Tanaka, Yoshihisa

1984-01-01

The fusion experimental reactor is the next stage device in Japan, which is planned to be constructed following the critical plasma experimental device JT-60 being constructed at present. The breeding blanket installed in nuclear fusion reactors is one of most important structures, and it is required to satisfy the fundamental performance of producing and continuously recovering tritium as the nuclear fusion fuel, and other requirement in good coordination. The Li 2 O pebble type breeding blanket that Kawasaki Heavy Industries Ltd. has examined is the concept for resolving the problems of the mass transfer and thermal stress cracking of Li 2 O, which are important in blanket design. In this paper, the concept and characteristics of this breeding blanket are discussed from the viewpoint of the breeding and continuous recovery of tritium, the ease of manufacture and the maintenance of soundness. The breeding blanket is composed of breeding region, tritium purge region, cooling region, plasma stabilizing conductors and blanket container. Li 2 O is excellent in its tritium breeding performance and heat conductivity. The functions required for the breeding blanket, the fundamental structure, the examples of breeding blanket concept, the selection of breeding blanket concept, the characteristics of Li 2 O pebble type blanket and its future prospect are described. (Kako, I.)

IAEA activities in nuclear reactors simulation for educational purposes

International Nuclear Information System (INIS)

Lyon, R.B.

1998-01-01

The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. Currently, the IAEA has two simulation programs: the Classroom-based Advanced Reactor Demonstrators package, and the Advanced Reactor Simulator. Both packages simulate the behaviour of BWR, PWR and HWR reactor types. For each package, the modeling approach and assumptions are broadly described, together with a general description of the operation of the computer programs. (author)

Development of an educational nuclear research reactor simulator

International Nuclear Information System (INIS)

Arafa, Amany Abdel Aziz; Saleh, Hassan Ibrahim; Ashoub, Nagieb

2014-01-01

This paper introduces the development of a research reactor educational simulator based on LabVIEW that allows the training of operators and studying different accident scenarios and the effects of operational parameters on the reactor behavior. Using this simulator, the trainee can test the interaction between the input parameters and the reactor activities. The LabVIEW acts as an engine implements the reactor mathematical models. In addition, it is used as a tool for implementing the animated graphical user interface. This simulator provides the training requirements for both of the reactor staff and the nuclear engineering students. Therefore, it uses dynamic animation to enhance learning and interest for a trainee on real system problems and provides better visual effects, improved communications, and higher interest levels. The benefits of conducting such projects are to develop the expertise in this field and save costs of both operators training and simulation courses.

Development of an educational nuclear research reactor simulator

Energy Technology Data Exchange (ETDEWEB)

Arafa, Amany Abdel Aziz; Saleh, Hassan Ibrahim [Atomic Energy Authority, Cairo (Egypt). Radiation Engineering Dept.; Ashoub, Nagieb [Atomic Energy Authority, Cairo (Egypt). Reactor Physics Dept.

2014-12-15

This paper introduces the development of a research reactor educational simulator based on LabVIEW that allows the training of operators and studying different accident scenarios and the effects of operational parameters on the reactor behavior. Using this simulator, the trainee can test the interaction between the input parameters and the reactor activities. The LabVIEW acts as an engine implements the reactor mathematical models. In addition, it is used as a tool for implementing the animated graphical user interface. This simulator provides the training requirements for both of the reactor staff and the nuclear engineering students. Therefore, it uses dynamic animation to enhance learning and interest for a trainee on real system problems and provides better visual effects, improved communications, and higher interest levels. The benefits of conducting such projects are to develop the expertise in this field and save costs of both operators training and simulation courses.

Impacts on power reactor health physics programs

International Nuclear Information System (INIS)

Meyer, B.A.

1991-01-01

The impacts on power reactor health physics programs form implementing the revised 10 CFR Part 20 will be extensive and costly. Every policy, program, procedure and training lesson plan involving health physics will require changes and the subsequent retraining of personnel. At each power reactor facility, hundreds of procedures and thousands of people will be affected by these changes. Every area of a power reactor health physics program will be affected. These areas include; ALARA, Respiratory Protection, Exposure Control, Job Coverage, Dosimetry, Radwaste, Effluent Accountability, Emergency Planning and Radiation Worker Training. This paper presents how power reactor facilities will go about making these changes and gives possible examples of some of these changes and their impact on each area of power reactor health physics program

Reactor operator screening test experiences

International Nuclear Information System (INIS)

O'Brien, W.J.; Penkala, J.L.; Witzig, W.F.

1976-01-01

When it became apparent to Duquesne Light Company of Pittsburgh, Pennsylvania, that the throughput of their candidate selection-Phase I training-reactor operator certification sequence was something short of acceptable, the utility decided to ask consultants to make recommendations with respect to candidate selection procedures. The recommendation implemented was to create a Nuclear Training Test that would predict the success of a candidate in completing Phase I training and subsequently qualify for reactor operator certification. The mechanics involved in developing and calibrating the Nuclear Training Test are described. An arbitration decision that resulted when a number of International Brotherhood of Electrical Workers union employees filed a grievance alleging that the selection examination was unfair, invalid, not job related, inappropriate, and discriminatorily evaluated is also discussed. The arbitration decision favored the use of the Nuclear Training Test

Pilot program: NRC severe reactor accident incident response training manual: US Nuclear Regulatory Commission response

International Nuclear Information System (INIS)

Sakenas, C.A.; McKenna, T.J.; Perkins, K.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

1987-02-01

This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. US Nuclear Regulatory Commission Response is the fifth in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes NRC response modes, organizations, and official positions; roles of other federal agencies are also described briefly. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

Assessment of the implementation of a neutron measurement system during the commissioning of the Jordan Research and Training Reactor

Energy Technology Data Exchange (ETDEWEB)

Bae, Sang Hoon; Suh, Sang Mun [Division of Research Reactor System Design, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Cha, Han Ju [Dept. of Electrical Engineering, Intelligent Power Conversion Laboratory, Chungnam National University, Daejeon (Korea, Republic of)

2017-04-15

The Jordan Research and Training Reactor (JRTR) is the first research reactor in Jordan, the commissioning of which is ongoing. The reactor is a 5-MWth, open-pool type, light-water-moderated, and cooled reactor with a heavy water reflector system. The neutron measurement system (NMS) applied to the JRTR employs a wide-range fission chamber that can cover from source range to power range. A high-sensitivity boron trifluoride counter was added to obtain more accurate measurements of the neutron signals and to calibrate the log power signals; the NMS has a major role in the entire commissioning stage. However, few case studies exist concerning the application of the NMS to a research reactor. This study introduces the features of the NMS and the boron trifluoride counter in the JRTR and shares valuable experiences from lessons learned from the system installation to its early commissioning. In particular, the background noise relative to the signal-to-noise ratio and the NMS signal interlock are elaborated. The results of the count rates with the neutron source and the effects of the discriminator threshold are summarized.

The Text of the Instrument Concerning the Agency's Assistance to Argentina for the Establishment of a Training Reactor Project

International Nuclear Information System (INIS)

1971-01-01

The text of the Agreement between the Agency and the Governments of Argentina and the Federal Republic of Germany concerning the Agency's assistance for the establishment of a training reactor project in Argentina is reproduced herein for the information of all Members. The Agreement entered into force on 13 March 1970.

The Text of the Instrument Concerning the Agency's Assistance to Argentina for the Establishment of a Training Reactor Project

Energy Technology Data Exchange (ETDEWEB)

NONE

1971-02-23

The text of the Agreement between the Agency and the Governments of Argentina and the Federal Republic of Germany concerning the Agency's assistance for the establishment of a training reactor project in Argentina is reproduced herein for the information of all Members. The Agreement entered into force on 13 March 1970.

Computer training aids for nuclear operator training

International Nuclear Information System (INIS)

Phillips, J.G.P.; Binns, J.B.H.

1983-01-01

The Royal Navy's Nuclear Propulsion School at HMS SULTAN which is responsible for training all ratings and officers who operate Submarine Pressurised Water Reactor plants, has available a varied selection of classroom simulator training aids as well as purpose built Submarine Manoeuvring Room simulators. The use of these classroom training aids in the twelve months prior to Autumn 1981 is discussed. The advantages and disadvantages of using relatively expensive computer based aids to support classroom instruction for students who do not investigate mathematically the dynamics of the Reactor Plant are identified. The conclusions drawn indicate that for students of limited academic ability the classroom simulators are disproportionately expensive in cost, maintenance load, and instructional time. Secondly, the experience gained in the use of the Manoeuvring Room Simulators to train future operators who have just finished the academic phase of their training is outlined. The possible pitfalls for the instructor are discussed and the lessons learnt, concluding that these simulators provide a valuable substitute for the live plant enabling trainees to be brought up to a common standard and reducing their on job training time to an acceptable level. (author)

IAEA activities in nuclear reactor simulation for educational purposes

International Nuclear Information System (INIS)

Lyon, R.B.

2001-01-01

The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. Two simulation programs are presented at this workshop: the Classroom-based Advanced Reactor Demonstrators package, and the Advanced Reactor Simulator. Both packages simulate the behaviour of BWR, PWR and HWR reactor types. For each package, the modeling approach and assumptions are broadly described, together with a general description of the operation of the computer programs. (author)

Advances in reactor physics education: Visualization of reactor parameters

International Nuclear Information System (INIS)

Snoj, L.; Kromar, M.; Zerovnik, G.

2012-01-01

Modern computer codes allow detailed neutron transport calculations. In combination with advanced 3D visualization software capable of treating large amounts of data in real time they form a powerful tool that can be used as a convenient modern educational tool for reactor operators, nuclear engineers, students and specialists involved in reactor operation and design. Visualization is applicable not only in education and training, but also as a tool for fuel management, core analysis and irradiation planning. The paper treats the visualization of neutron transport in different moderators, neutron flux and power distributions in two nuclear reactors (TRIGA type research reactor and a typical PWR). The distributions are calculated with MCNP and CORD-2 computer codes and presented using Amira software. (authors)

Research reactor standards and their impact on the TRIGA reactor community

International Nuclear Information System (INIS)

Richards, W.J.

1980-01-01

The American Nuclear Society has established a standards committee devoted to writing standards for research reactors. This committee was formed in 1971 and has since that time written over 15 standards that cover all aspects of research reactor operation. The committee has representation from virtually every group concerned with research reactors and their operation. This organization includes University reactors, National laboratory reactors, Nuclear Regulatory commission, Department of Energy and private nuclear companies and insurers. Since its beginning the committee has developed standards in the following areas: Standard for the development of technical specifications for research reactors; Quality control for plate-type uranium-aluminium fuel elements; Records and reports for research reactors; Selection and training of personnel for research reactors; Review of experiments for research reactors; Research reactor site evaluation; Quality assurance program requirements for research reactors; Decommissioning of research reactors; Radiological control at research reactor facilities; Design objectives for and monitoring of systems controlling research reactor effluents; Physical security for research reactor facilities; Criteria for the reactor safety systems of research reactors; Emergency planning for research reactors; Fire protection program requirements for research reactors; Standard for administrative controls for research reactors. Besides writing the above standards, the committee is very active in using communications with the nuclear regulatory commission on proposed rules or positions which will affect the research reactor community

University of Florida Training Reactor: Annual progress report, September 1, 1986-August 31, 1987

International Nuclear Information System (INIS)

Vernetson, W.G.

1987-11-01

The University of Florida Training Reactor's overall utilization for the past reporting year (September 1986 through August 1987) has returned to the increased levels of quality usage characteristic of the two years prior to the last reporting year when the maintenance outage to repair sticking control blades reduced availability for the year to near 50%. Indeed, the 91.5% availability factor for this reporting year is the highest in the last five years and probably in the 27 year history of the facility. As a final statement on the effectiveness of the corrective maintenance last year, the overall availability factor has been over 94% since returning to normal operations. The UFTR continues to experience a high rate of utilization in a broad spectrum of areas with total utilization continuing near the highest levels recorded in the early 1970's. This increase has been supported by a variety of usages ranging from research and educational utilization by users within the University of Florida as well as other researchers and educators around the state of Florida through the support of the DOE Reactor Sharing Program and several externally supported usages. Significant usage has also been devoted to facility enhancement where a key ingredient for this usage has been a stable management staff. Uses, reactor operation, maintenance, technical specifications, radioactive releases, and research programs are described in this report

Neutrons for research and training

International Nuclear Information System (INIS)

Villa, M.; Bichler, M.; Hameed, F.; Jericha, E.; Steinhauser, G.; Sterba, J.H.; Boeck, H.

2008-01-01

The 250 kW TRIGA Mark-II reactor operates since March 1962 at the Atomic Institute in Vienna, Austria. Its main tasks are nuclear education and training in the fields of neutron- and solid state physics, nuclear technology, reactor safety, radiochemistry, radiation protection and dosimetry, and low temperature physics and fusion research. Academic research is carried out by students in the above mentioned fields co-ordinated and supervised by about 80 staff members with the aim of a master- or PhD degree in one of the above mentioned areas. During the past 15 years about 600 students graduated through the Atomic Institute. The paper focuses on the results in neutron- and solid state physics and the co-operation between the low power TRIGA reactor with high flux neutron sources in Europe. The use of the TRIGA reactor at the Atomic Institute in Vienna as an irradiation facility in neutron activation analysis has a remarkable history. Present research work includes the recent determination of the precise half-life of 182 Hf and the participation in an archaeological long-term research programme. The TRIGA reactor operated by the Atomic Institute is now the only nuclear facility in Austria. Although Austria follows a dedicated anti-nuclear policy, the Atomic Institute enjoys a relatively undisturbed nuclear freedom in its nuclear activities. This allows us to use the research reactor not only for academic training but also for international training courses especially in nuclear technology. The presentation will outline typical training programmes and summarizes the experience with international training courses. (authors)

Estudo de validação das equações de Tanaka e de Kawasaki para estimar a excreção diária de sódio através da coleta da urina casual

Directory of Open Access Journals (Sweden)

José Geraldo Mill

2015-12-01

Full Text Available RESUMO: Objetivo: Validar as fórmulas de Tanaka e Kawasaki para cálculo do consumo de sal pela relação sódio/creatinina na urina casual. Métodos: Foram estudados 272 adultos (20 - 69 anos, 52,6% de mulheres com coleta urinária de 24 h e duas coletas casuais no mesmo dia (em jejum - casual 1 - e fora do jejum - casual 2. Antropometria, pressão arterial e coleta de sangue foram obtidos no mesmo dia. A concordância entre o consumo de sal estimado pela urina de 24 h e pela urina casual foi feita por Pearson (r e Bland & Altman. Resultados: O consumo médio de sal medido pela urina de 24 h foi de 10,4 ± 5,3 g/dia. A correlação entre a excreção de sódio na urina de 24 h e a estimada pela urina casual 1 ou 2, respectivamente, foi apenas moderada, tanto por Tanaka (r = 0,51 e r = 0,55; p < 0,001 como por Kawasaki (r = 0,52 e r = 0,54; p < 0,001. Observa-se subestimação crescente dos valores estimados em relação ao medido com o aumento do consumo de sal pela fórmula de Tanaka e, ao contrário, superestimação ao usar a fórmula de Kawasaki. As fórmulas estimam adequadamente o consumo diário de sal (diferença entre sal medido e estimado de, no máximo, 1 g/dia somente com consumo entre 9 - 12 g/dia (Tanaka e 12 - 18 g/dia (Kawasaki. Conclusão: A coleta de urina casual estima adequadamente o consumo de sal apenas nos indivíduos próximos à média populacional.

Atrioventricular depolarization differences identify coronary artery anomalies in Kawasaki disease.

Science.gov (United States)

Cortez, Daniel; Sharma, Nandita; Jone, Pei-Ni

2017-03-01

Kawasaki disease (KD) is the leading cause of acquired heart disease in children. Signal average electrocardiogram changes in patients during the acute phase of KD with coronary artery anomalies (CAA) include depolarization changes. We set out to determine if 12-lead-derived atrioventricular depolarization differences can identify CAA in patients with KD. A blinded, retrospective case-control study of patients with KD was performed. Deep Q waves, corrected QT-intervals (QTc), spatial QRS-T angles, T-wave vector magnitudes (RMS-T), and a novel parameter for assessment of atrioventricular depolarization difference (the spatial PR angle) and a two dimensional PR angle were assessed. Comparisons between groups were performed to test for significant differences. One hundred one patients with KD were evaluated, with 68 having CAA (67.3%, mean age 3.6 ± 3.0 years, 82.6% male), and 32 without CAA (31.7%, mean age 2.7 ± 3.2 years, 70.4% male). The spatial PR angle significantly discriminated KD patients with CAA from those without, 59.7° ± 31.1° versus 41.6° ± 11.5° (p differences, measured by the spatial or two dimensional PR angle differentiate KD patients with CAA versus those without. © 2016 Wiley Periodicals, Inc.

URI Program Final Report FY 2001 Grant for the University of Florida Training Reactor

International Nuclear Information System (INIS)

Vernetson, W.G.

2004-01-01

The purpose of the URI program is to upgrade and improve university nuclear research and training reactors and to contribute to strengthening the academic community's nuclear engineering infrastructure. It should be noted that the proposed UFTR facility instrumentation and equipment can generally be subdivided into three categories: (1) to improve reactor operations, (2) to improve existing facility/NAA Laboratory operations, and (3) to expand facility capability. All of these items were selected recognizing the objectives of the University Reactor Instrumentation Program to respond to the widespread needs in the academic reactor community for modernization and improvement of research and training reactor facilities, especially at large and diverse institutions such as the University of Florida. These needs have been particularly pressing at the UFTR which is the only such research and training reactor in the State of Florida which is undergoing rapid growth in a variety of technical areas. As indicated in Table 2, the first item is a security system control panel with associated wiring and detectors. The existing system is over 30 years old and has been the subject of repeated maintenance over the past 5 years. Some of its detection devices are no longer replaceable from stock. Modifications made many years ago make troubleshooting some parts of the system such as the backup battery charging subsystem essentially impossible, further increasing maintenance frequency to replace batteries. Currently, various parts of the system cable trays remain open for maintenance access further degrading facility appearance. In light of relicensing plans, this item is also a key consideration for housekeeping appearance considerations. The cost of a replacement ADEMCO Vista 20 security system including turnkey installation by a certified vendor was to be $2,206. Replacement of this system was expected to save up to 5 days of maintenance per year, decrease security alarm response

BOILER-SUPERHEATED REACTOR

Science.gov (United States)

Heckman, T.P.

1961-05-01

A nuclear power reactor of the type in which a liquid moderator-coolant is transformed by nuclear heating into a vapor that may be used to drive a turbo- generator is described. The core of this reactor comprises a plurality of freely suspended tubular fuel elements, called fuel element trains, within which nonboiling pressurized liquid moderator-coolant is preheated and sprayed through orifices in the walls of the trains against the outer walls thereof to be converted into vapor. Passage of the vapor ovcr other unwetted portions of the outside of the fuel elements causes the steam to be superheated. The moderatorcoolant within the fuel elements remains in the liqUid state, and that between the fuel elements remains substantiaily in the vapor state. A unique liquid neutron-absorber control system is used. Advantages expected from the reactor design include reduced fuel element failure, increased stability of operation, direct response to power demand, and circulation of a minimum amount of liquid moderatorcoolant. (A.G.W.)

Developments of HTGR thermofluid dynamic analysis codes and HTGR plant dynamic simulation code

International Nuclear Information System (INIS)

Tanaka, Mitsuhiro; Izaki, Makoto; Koike, Hiroyuki; Tokumitsu, Masashi

1983-01-01

In nuclear power plants as well as high temperature gas-cooled reactor plants, the design is mostly performed on the basis of the results after their characteristics have been grasped by carrying out the numerical simulation using the analysis code. Also in Kawasaki Heavy Industries Ltd., on the basis of the system engineering accumulated with gas-cooled reactors since several years ago, the preparation and systematization of analysis codes have been advanced, aiming at lining up the analysis codes for heat transferring flow and control characteristics, taking up HTGR plants as the main object. In this report, a part of the results is described. The example of the analysis applying the two-dimensional compressible flow analysis codes SOLA-VOF and SALE-2D, which were developed by Los Alamos National Laboratory in USA and modified for use in Kawasaki, to HTGR system is reported. Besides, Kawasaki has developed the control characteristics analyzing code DYSCO by which the change of system composition is easy and high versatility is available. The outline, fundamental equations, fundamental algorithms and examples of application of the SOLA-VOF and SALE-2D, the present status of system characteristic simulation codes and the outline of the DYSCO are described. (Kako, I.)

Nuclear reactor simulator

International Nuclear Information System (INIS)

Baptista, Vinicius Damas

1996-01-01

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

IAEA activities in nuclear reactor simulation for educational purposes

International Nuclear Information System (INIS)

Badulescu, A.; Lyon, R.

2001-01-01

The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. Currently, the IAEA has simulation programs available for distribution that simulate the behaviour of BWR, PWR and HWR reactor types. (authors)

The qualification of reactor operators

International Nuclear Information System (INIS)

Lima, J.M. de; Soares, H.V.

1981-01-01

The qualification and performance of nuclear power personnel have an important influence on the availability and safety operation of these plants. This paper describes the Brazilian rules and norms established by the CNEN-Brazilian Atomic Energy Comission, as well as policy of other countries concerning training requirements and experiences of nuclear power reactor operators. Some coments are made about the im pact of the march 1979 Three Mile Island accident on upgrading the reactor training requirements in U.S.A. and its international implication. (Author) [pt

Preparation fo nuclear research reactors operators

International Nuclear Information System (INIS)

Roedel, G.

1986-01-01

The experience obtained with the training of operators of nuclear research reactors is presented. The main tool used in the experiments is the IPR-R1 reactor, a TRIGA MARK I type, owned by Nuclear Technology Development Centre (CDTN) of NUCLEBRAS. The structures of the Research Reactors Operators Training Course and of the Radiological Protection Course, as well as the Operators Qualifying and Requalifying Program, all of them prepared at CDTN are also presented. Mention is made of the application of similar experiments to other groups, such as students coming from Nuclear Sciences and Techniques Course of the Federal University of Minas Gerais. (Author) [pt

Preparation of nuclear research reactors operators

International Nuclear Information System (INIS)

Roedel, G.

1986-01-01

The experience obtained with the training of operators of nuclear research reactors is presented. The main tool used in the experiments is the IPR-R1 reactor, a TRIGA MARK I type, owned by Nuclear Technology Development Centre (CDTN) of NUCLEBRAS. The structures of the Research Reactors Operators Training Course and of the Radiological Protection Course, as well as the Operators Qualifying and Requalifying Program, all of them prepared at CDTN, are also presented. Mention is made of the application of similar experiments to other groups, such as students coming from Nuclear Sciences and Techniques Course of the Federal University of Minas Gerais. (Author) [pt

Simulator training effectiveness: instructor training and qualifications

International Nuclear Information System (INIS)

Scholand, G.W.

1985-01-01

Nuclear power plant simulators have become the most important tool in training nuclear power plant operators. Yet, as these machines continue to become even more sophisticated, highly trained and experienced instructors with unique skills and insights are still essential in order to achieve effective and meaningful training. The making of a qualified simulator instructor involves training and techniques that exceed the traditional programs required of a Senior Reactor Operator (SRO). This paper discusses (i) the training necessary to produce a competent simulator instructor; and (ii) the continuing task of maintaining his or her proficiency. (author)

Laboratory instrumentation modernization at the WPI Nuclear Reactor Facility

International Nuclear Information System (INIS)

1995-01-01

With partial funding from the Department of Energy (DOE) University Reactor Instrumentation Program several laboratory instruments utilized by students and researchers at the WPI Nuclear Reactor Facility have been upgraded or replaced. Designed and built by General Electric in 1959, the open pool nuclear training reactor at WPI was one of the first such facilities in the nation located on a university campus. Devoted to undergraduate use, the reactor and its related facilities have been since used to train two generations of nuclear engineers and scientists for the nuclear industry. The low power output of the reactor and an ergonomic facility design make it an ideal tool for undergraduate nuclear engineering education and other training. The reactor, its control system, and the associate laboratory equipment are all located in the same room. Over the years, several important milestones have taken place at the WPI reactor. In 1969, the reactor power level was upgraded from 1 kW to 10 kW. The reactor's Nuclear Regulatory Commission operating license was renewed for 20 years in 1983. In 1988, under DOE Grant No. DE-FG07-86ER75271, the reactor was converted to low-enriched uranium fuel. In 1992, again with partial funding from DOE (Grant No. DE-FG02-90ER12982), the original control console was replaced

2012 review of French research reactors

International Nuclear Information System (INIS)

Estrade, Jerome

2013-01-01

Proposed by the French Reactor Operators' Club (CER), the meeting and discussion forum for operators of French research reactors, this report first gives a brief presentation of these reactors and of their scope of application, and a summary of highlights in 2012 for each of them. Then, it proposes more detailed presentations and reviews of characteristics, activities, highlights, objectives and results for the different types of reactors: neutron beam reactors (Orphee, High flux reactor-Laue-Langevin Institute or HFR-ILL), technological irradiation reactors (Osiris and Phenix), training reactors (Isis and Azur), reactors for safety research purposes (Cabri and Phebus), reactors for neutronic studies (Caliban, Prospero, Eole, Minerve and Masurca), and new research reactors (the RES facility and the Jules Horowitz reactor or JHR)

The development of NPP operational safety training courses

International Nuclear Information System (INIS)

Lee, Chang Kun; Lee, Duk Sun; Lee, Byung Sun; Lee, Won Koo; Juhn, Heng Run; Moon, Byung Soo; Cho, Min Sik; Lee, Han Young; Moon, Hak Won; Seo, Yeon Ho

1987-12-01

The objective of the project is to develop a training course text for the betterment of reactor operation and assurance of its safety in general by providing training materials of the advanced compact nuclear simulator which will become operation in September 1988. Main scope and contents of the project are as follows: - compilation of basic data related to simulator operation and maintenance as well as the comparative analysis with respect to simulator materials in foreign countries - method of training by simulator - review the training status by simulator in foreign countries - development of training course in the field of reactor safety It is expected that the results will be reflected to the actual training and retraining of the reactor operating crew so as to improve and update their capabilities in training fashion. (Author)

Directory of Nuclear Research Reactors 1994

International Nuclear Information System (INIS)

1995-08-01

The Directory of Nuclear Research Reactors is an output of the Agency's computerized Research Reactor Data Base (RRDB). It contains administrative, technical and utilization information on research reactors known to the Agency at the end of December 1994. The data base converted from mainframe to PC is written in Clipper 5.0 and the publication generation system uses Excel 4. The information was collected by the Agency through questionnaires sent to research reactor owners. All data on research reactors, training reactors, test reactors, prototype reactors and critical assemblies are stored in the RRDB. This system contains all the information and data previously published in the Agency's publication, Directory of Nuclear Research Reactor, as well as updated information

Safety evaluation report related to the renewal of the operating license for the Worcester Polytechnic Institute open-pool training reactor, Docket No. 50-134

International Nuclear Information System (INIS)

1982-12-01

This Safety Evaluation Report for the application filed by the Worcester Polytechnic Institute (WPI) for a renewal of Operating License R-61 to continue to operate the WPI 10-kW open-pool training reactor has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is owned and operated by the Worcester Polytechnic Institute and is located on the WPI campus in Worcester, Worcester County, Massachusetts. The staff concludes that the reactor facility can continue to be operated by WPI without endangering the health and safety of the public

Reactor operations at SAFARI-1

International Nuclear Information System (INIS)

Vlok, J.W.H.

2003-01-01

A vigorous commercial programme of isotope production and other radiation services has been followed by the SAFARI-1 research reactor over the past ten years - superimposed on the original purpose of the reactor to provide a basic tool for nuclear research, development and education to the country at an institutional level. A combination of the binding nature of the resulting contractual obligations and tighter regulatory control has demanded an equally vigorous programme of upgrading, replacement and renovation of many systems in order to improve the safety and reliability of the reactor. Not least among these changes is the more effective training and deployment of operations personnel that has been necessitated as the operational demands on the reactor evolved from five days per week to twenty four hours per day, seven days per week, with more than 300 days per year at full power. This paper briefly sketches the operational history of SAFARI-1 and then focuses on the training and structuring currently in place to meet the operational needs. There is a detailed step-by-step look at the operator?s career plan and pre-defined milestones. Shift work, especially the shift cycle, has a negative influence on the operator's career path development, especially due to his unavailability for training. Methods utilised to minimise this influence are presented. The increase of responsibilities regarding the operation of the reactor, ancillaries and experimental facilities as the operator progresses with his career are discussed. (author)

Communication and computer technologies for teaching physics in nuclear reactors

International Nuclear Information System (INIS)

Murua, C; Chautemps, A; Odetto, J; Keil, W; Trivino, S; Rossi, F; Perez Lucero, A

2012-01-01

In order to train personnel inn order to train personnel in Embalse Nuclear Power Plant, and provided that such training given primarily on the location of such a facility, we designed a pedagogical strategy that combined the use of conventional resources with new information technologies. Since the Nuclear Reactor RA-0 is an ideal tool for teaching Reactor Physics, priority was the use of it, both locally remotely. The teaching strategy is based on four pillar: -Lectures on the Power Plant (using a virtual classroom to support); -Remote monitoring of Ra-0 Nuclear Reactor parameters while operating (RA0REMOTO); -Use, through the Internet, of the Ra-0 Nuclear Reactor Simulator (RA0SIMUL); -Made in the Nuclear Reactor RA-0 of Reactor Physics practical. The work emphasizes RA0REMOTO and RA0SIMUL systems. The RA0REMOTO system is an appendix of the Electronic Data Acquisition System (SEAD) of the Nuclear Reactor RA-0. This system acquires signals from Reactor instrumentation and sends them to a server running the software that 'publish' the reactor parameters on the internet. Students may, during the lectures, monitor any parameter of the reactor while it operates, which allows teachers to compare theory with reality. RA0SIMUL is a simulator on the RA-0, which allows students to 'operate' a reactor analyzing the underlying physics concepts (author)

LABORATORY BIOMARKERS TO FACILITATE DIFFERENTIAL DIAGNOSIS BETWEEN MEASLES AND KAWASAKI DISEASE IN A PEDIATRIC EMERGENCY ROOM: A RETROSPECTIVE STUDY

Directory of Open Access Journals (Sweden)

Danilo Buonsenso

2018-05-01

Full Text Available This retrospective study was conducted to analyze clinical and laboratoristic parameters to individuate specific differences and facilitate differential diagnosis between Measles and Kawasaki Disease (KD at first evaluation in a emergency room. We found similar clinical features as duration of fever and number of KD criteria (p >0.5 but significant differences in white blood cell count, neutrophils, CRP and LDH levels (p < 0.001. LDH value ≥ 800 mg/dl had sensibility of 89% and specificity of 90% for Measles while CRP ≥ 3 mg/dl had sensibility 89% and specificity of 85% for KD. The combined use of CRP, LDH and AST showed accuracy of 86.67%.

PUSPATI Triga Reactor - First year in operation

International Nuclear Information System (INIS)

Nahrul Khair Rashid.

1983-01-01

First year operation of RTP reactor was mostly devoted to making in house training, setting up and testing the facilities in preparation for more routine operations. Generally the operations are categorized into 4 main purposes; experiment of research, teaching and training, demonstration, and testing and maintenance. These four purposes are elaborated in detail. Additions and modifications were performed in order to improve the safety of reactor operation. (A.J.)

SSC RIAR is the largest centre of research reactors

International Nuclear Information System (INIS)

Kalygin, V.V.

1997-01-01

The State Scientific Centre (SSC) ''Research Institute of Atomic Reactors'' (RIAR) is situated 100 km to the south-east from Moscow, in Dimitrovgrad, the Volga Region of the Russian Federation. SSC RIAR is the largest centre of research reactors in Russia. At present there are 5 types of reactor facilities in operation, including two NPP. One of the main tasks the Centre is the investigations on safety increase for power reactors. Broad international connections are available at the Institute. On the basis of the SSC RIAR during 3 years work has been done on the development of the branch training centre (TC) for the training of operation personnel of research and pilot reactors in Russia. (author). 3 tabs

SSC RIAR is the largest centre of research reactors

Energy Technology Data Exchange (ETDEWEB)

Kalygin, V V [State Scientific Centre, Research Inst. of Atomic Reactors (Russian Federation)

1997-10-01

The State Scientific Centre (SSC) ``Research Institute of Atomic Reactors`` (RIAR) is situated 100 km to the south-east from Moscow, in Dimitrovgrad, the Volga Region of the Russian Federation. SSC RIAR is the largest centre of research reactors in Russia. At present there are 5 types of reactor facilities in operation, including two NPP. One of the main tasks the Centre is the investigations on safety increase for power reactors. Broad international connections are available at the Institute. On the basis of the SSC RIAR during 3 years work has been done on the development of the branch training centre (TC) for the training of operation personnel of research and pilot reactors in Russia. (author). 3 tabs.

Integrated training support system for PWR operator training simulator

International Nuclear Information System (INIS)

Sakaguchi, Junichi; Komatsu, Yasuki

1999-01-01

The importance of operator training using operator training simulator has been recognized intensively. Since 1986, we have been developing and providing many PWR simulators in Japan. We also have developed some training support systems connected with the simulator and the integrated training support system to improve training effect and to reduce instructor's workload. This paper describes the concept and the effect of the integrated training support system and of the following sub-systems. We have PES (Performance Enhancement System) that evaluates training performance automatically by analyzing many plant parameters and operation data. It can reduce the deviation of training performance evaluation between instructors. PEL (Parameter and Event data Logging system), that is the subset of PES, has some data-logging functions. And we also have TPES (Team Performance Enhancement System) that is used aiming to improve trainees' ability for communication between operators. Trainee can have conversation with virtual trainees that TPES plays automatically. After that, TPES automatically display some advice to be improved. RVD (Reactor coolant system Visual Display) displays the distributed hydraulic-thermal condition of the reactor coolant system in real-time graphically. It can make trainees understand the inside plant condition in more detail. These sub-systems have been used in a training center and have contributed the improvement of operator training and have gained in popularity. (author)

CER. Research reactors in France

International Nuclear Information System (INIS)

Estrade, Jerome

2012-01-01

Networking and the establishment of coalitions between research reactors are important to guarantee a high technical quality of the facility, to assure well educated and trained personnel, to harmonize the codes of standards and the know-ledge of the personnel as well as to enhance research reactor utilization. In addition to the European co-operation, country-specific working groups have been established for many years, such as the French research reactor Club d'Exploitants des Reacteurs (CER). It is the association of French research reactors representing all types of research reactors from zero power up to high flux reactors. CER was founded in 1990 and today a number of 14 research reactors meet twice a year for an exchange of experience. (orig.)

The JASON reactor at the Royal Naval College: Silver Jubilee 6th November 1987

International Nuclear Information System (INIS)

Lakey, J.R.A.; Roust, C.B.

1988-01-01

The 10 kW Research and Training Reactor Jason has been used at the Royal Naval College for 25 years in support of the Naval Nuclear Submarine Propulsion Programme. The principal features of Jason, relevant to its training role are given, along with the specifications of Jason, instrumentation, maintenance and operational experience. The educational role of the reactor is described with respect to the Nuclear Reactor Course, Nuclear Advanced Course, and the Nuclear Radiation Protection Course. Future developments in operator training, advantages of the low power reactor, quality control of education and training, and research and development, are also discussed. (U.K.)

Multipurpose research reactors

International Nuclear Information System (INIS)

1988-01-01

The international symposium on the utilization of multipurpose research reactors and related international co-operation was organized by the IAEA to provide for information exchange on current uses of research reactors and international co-operative projects. The symposium was attended by about 140 participants from 36 countries and two international organizations. There were 49 oral presentations of papers and 24 poster presentations. The presentations were divided into 7 sessions devoted to the following topics: neutron beam research and applications of neutron scattering (6 papers and 1 poster), reactor engineering (6 papers and 5 posters), irradiation testing of fuel and material for fission and fusion reactors (6 papers and 10 posters), research reactor utilization programmes (13 papers and 4 posters), neutron capture therapy (4 papers), neutron activation analysis (3 papers and 4 posters), application of small reactors in research and training (11 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

Operating Experience Review(OER) and development of Issues Tracking System(ITS) for Jordan Research and Training Reactor(JRTR)

International Nuclear Information System (INIS)

Kim, Yong Jun; Lee, Hyun Chul

2011-01-01

The operation of the Jordan Research and Training Reactor which Korean consortium designs will start in March 2015. Though the power level of JRTR is different from the one of HANARO, a Korean research reactor, experience and expertise gained from the successful operation of the multipurpose research reactor, HANARO, would be applied for the design of JRTR because the basic operation principles of two reactors are almost same. From the point of human factors view, Operating Experience Review (OER) has the accurate purpose of reflecting accumulated knowledge to a new design and this activity are required to perform in the beginning stage of the control room designs in nuclear facilities. OER is to identify human factors engineering (HFE) issues related to safety. The issues from operating experience provide a basis for improving the plant design in a timely way. Identified issues are reported to an issues tracking system (ITS) so as to manage and resolve issues. HFE related safety issues are to be extracted from OER. The purpose of this paper is to present the scope and methods of OER for the JRTR design. In addition, a new ITS is proposed. The ITS is effective for issue management and has simplified states for issue development and small numbers of steps for issue control

Virtual environments simulation in research reactor

Science.gov (United States)

Muhamad, Shalina Bt. Sheik; Bahrin, Muhammad Hannan Bin

2017-01-01

Virtual reality based simulations are interactive and engaging. It has the useful potential in improving safety training. Virtual reality technology can be used to train workers who are unfamiliar with the physical layout of an area. In this study, a simulation program based on the virtual environment at research reactor was developed. The platform used for virtual simulation is 3DVia software for which it's rendering capabilities, physics for movement and collision and interactive navigation features have been taken advantage of. A real research reactor was virtually modelled and simulated with the model of avatars adopted to simulate walking. Collision detection algorithms were developed for various parts of the 3D building and avatars to restrain the avatars to certain regions of the virtual environment. A user can control the avatar to move around inside the virtual environment. Thus, this work can assist in the training of personnel, as in evaluating the radiological safety of the research reactor facility.

Atypical desquamation in a 2.5-year-old boy with Kawasaki disease: A case report.

Science.gov (United States)

Adib, Ali; Fazel, Ali; Nabavizadeh, Seyed Hesamedin; Alyasin, Sohaila; Kashef, Sara

2017-02-01

Kawasaki disease (KD) is a vasculitis that mostly affects children under 5 years of age. This article presents a 2.5-year-old boy who presented with 6 days of fever, generalized maculopapular rash, bilateral non-exudative conjunctivitis, cracked lips, right cervical lymphadenopathy, erythematous extremities, and perianal desquamation. Laboratory studies showed leukocytosis and sterile pyuria. Because diagnosis of KD was proved, oral acetylsalicylic acid with the anti-inflammatory dose and intravenous immunoglobulin were started for him. On the seventh day of admission time, he developed desquamation and erythema on the site of his right cervical lymphadenopathy as well as periungual scaling. About three weeks after starting the treatment, scaling of the cervical lymphadenopathy and periungual area stopped. Echocardiography was performed for him three times: at the time of diagnosis, four weeks, and 6 months later and revealed normal coronary arteries. We report this sign, desquamation on the site of cervical lymphadenopathy, as a new finding.

Incomplete Kawasaki disease with recurrent skin peeling: a case report with the review of literature.

Directory of Open Access Journals (Sweden)

Parmar R

2003-01-01

Full Text Available Kawasaki disease (KD is an acute systemic vasculitis of unknown aetiology that has largely replaced rheumatic heart disease as a cause of acquired heart disease in children of many developed countries. We report a case of incomplete KD in a five-year-old girl. The diagnosis of incomplete KD was made after exclusion of conditions with similar presentation. She was treated with intravenous immunoglobulin following which she made an uneventful recovery but demonstrated thrombocytosis in the second week of convalescence. During the six-month follow up period, she had two episodes of recurrent skin peeling a phenomenon, which is recently reported with KD but not with atypical or incomplete KD. It is important for the treating physicians to become aware of the incomplete KD as prompt diagnosis and early treatment of these patients with intravenous immunoglobulin is vital for the prevention of lethal coronary complications. Physicians need to have a "high index of suspicion" for KD and even, higher for IKD.

Training reactor operators and shift supervisors

International Nuclear Information System (INIS)

Schwarz, O.

1980-01-01

To establish a central institution run by power plant operators to harmonize the training of power plant operating personnel was raised, and put into practice, quite early in the Federal Republic of Germany. A committee devoted to training plant crews, which had been set up by the organizations of German electricity utilities responsible for operating power plants, was changed into a Kraftwerksschule e.V. (Power Plant School) in 1963. This school runs training courses, along standard lines, for operating personnel of thermal power plants, especially for operators and power plant supervisors, in close cooperation with power plant operators. As the peaceful utilization of nuclear energy expanded, also the training of nuclear power plant operators was included in 1969. Since September 1977, the center has had a simulator of a PWR nuclear power plant, since January 1978 also that of a BWR plant available for training purposes. Besides routine operation the trainees also learn to control those incidents which occur only very rarely in real nuclear power plants. (orig./UA) [de

Development of Research Reactor Simulator and Its Application to Dynamic Test-bed

International Nuclear Information System (INIS)

Kwon, Kee Choon; Park, Jae Chang; Lee, Seung Wook; Bang, Dane; Bae, Sung Won

2014-01-01

We developed HANARO and the Jordan Research and Training Reactor (JRTR) real-time simulator for operating staff training. The main purpose of this simulator is operator training, but we modified this simulator as a dynamic test-bed to test the reactor regulating system in HANARO or JRTR before installation. The simulator configuration is divided into hardware and software. The simulator hardware consists of a host computer, 6 operator stations, a network switch, and a large display panel. The simulator software is divided into three major parts: a mathematical modeling module, which executes the plant dynamic modeling program in real-time, an instructor station module that manages user instructions, and a human machine interface (HMI) module. The developed research reactors are installed in the Korea Atomic Energy Research Institute nuclear training center for reactor operator training. To use the simulator as a dynamic test-bed, the reactor regulating system modeling software of the simulator was replaced by a hardware controller and the simulator and target controller were interfaced with a hard-wired and network-based interface

Development of Research Reactor Simulator and Its Application to Dynamic Test-bed

Energy Technology Data Exchange (ETDEWEB)

Kwon, Kee Choon; Park, Jae Chang; Lee, Seung Wook; Bang, Dane; Bae, Sung Won [KAERI, Daejeon (Korea, Republic of)

2014-08-15

We developed HANARO and the Jordan Research and Training Reactor (JRTR) real-time simulator for operating staff training. The main purpose of this simulator is operator training, but we modified this simulator as a dynamic test-bed to test the reactor regulating system in HANARO or JRTR before installation. The simulator configuration is divided into hardware and software. The simulator hardware consists of a host computer, 6 operator stations, a network switch, and a large display panel. The simulator software is divided into three major parts: a mathematical modeling module, which executes the plant dynamic modeling program in real-time, an instructor station module that manages user instructions, and a human machine interface (HMI) module. The developed research reactors are installed in the Korea Atomic Energy Research Institute nuclear training center for reactor operator training. To use the simulator as a dynamic test-bed, the reactor regulating system modeling software of the simulator was replaced by a hardware controller and the simulator and target controller were interfaced with a hard-wired and network-based interface.

Diagnosis of electric equipment at the Dalat Nuclear Research Reactor

International Nuclear Information System (INIS)

Nguyen Truong Sinh

1999-01-01

The Dalat Nuclear Research Reactor (DNRR) is a pool type of its kind in the world: Soviet-designed core and control system harmoniously integrated into the left-over infrastructure of the former American-made TRIGA MARK II reactor, which includes the reactor tank and shielding, graphite reflector, beam tubes and thermal column. The reactor is mainly used for radioisotope and radiopharmaceutical production, elemental analysis using neutron activation techniques, neutron beam exploitation, silicon doping, and reactor physics experimentation. For safe operation of the reactor maintenance work has been carried out for the reactor control and instrumentation, reactor cooling, ventilation, radiomonitoring, mechanical, normal electric supply systems as well as emergency electric diesel generators and the water treatment station. Technical management of the reactor includes periodical maintenance as required by technical specifications, training, re-training and control of knowledge for reactor staff. During recent years, periodic preventive maintenance (PPM) has been carried out for the electric machines of the technological systems. (author)

Genetic variants of CD209 associated with Kawasaki disease susceptibility.

Directory of Open Access Journals (Sweden)

Ho-Chang Kuo

Full Text Available BACKGROUND: Kawasaki disease (KD is a systemic vasculitis with unknown etiology mainly affecting children in Asian countries. Dendritic cell-specific intercellular adhesion molecule-3 grabbing non-integrin (DC-SIGN, CD209 in humans was showed to trigger an anti-inflammatory cascade and associated with KD susceptibility. This study was conducted to investigate the association between genetic polymorphisms of CD209 and the risk KD. METHODS: A total of 948 subjects (381 KD and 567 controls were recruited. Nine tagging SNPs (rs8112310, rs4804800, rs11465421, rs1544766, rs4804801, rs2287886, rs735239, rs735240, rs4804804 were selected for TaqMan allelic discrimination assay. Clinical phenotypes, coronary artery lesions (CAL and intravenous immunoglobulin (IVIG treatment outcomes were collected for analysis. RESULTS: Significant associations were found between CD209 polymorphisms (rs4804800, rs2287886, rs735240 and the risk of KD. Haplotype analysis for CD209 polymorphisms showed that A/A/G haplotype (P = 0.0002, OR = 1.61 and G/A/G haplotype (P = 0.0365, OR = 1.52 had higher risk of KD as compared with G/G/A haplotype in rs2287886/rs735239/rs735240 pairwise allele analysis. There were no significant association in KD with regards to CAL formation and IVIG treatment responses. CONCLUSION: CD209 polymorphisms were responsible for the susceptibility of KD, but not CAL formation and IVIG treatment responsiveness.

Genetic Variants of CD209 Associated with Kawasaki Disease Susceptibility

Science.gov (United States)

Kuo, Ho-Chang; Huang, Ying-Hsien; Chien, Shu-Chen; Yu, Hong-Ren; Hsieh, Kai-Sheng; Hsu, Yu-Wen; Chang, Wei-Chiao

2014-01-01

Background Kawasaki disease (KD) is a systemic vasculitis with unknown etiology mainly affecting children in Asian countries. Dendritic cell-specific intercellular adhesion molecule-3 grabbing non-integrin (DC-SIGN, CD209) in humans was showed to trigger an anti-inflammatory cascade and associated with KD susceptibility. This study was conducted to investigate the association between genetic polymorphisms of CD209 and the risk KD. Methods A total of 948 subjects (381 KD and 567 controls) were recruited. Nine tagging SNPs (rs8112310, rs4804800, rs11465421, rs1544766, rs4804801, rs2287886, rs735239, rs735240, rs4804804) were selected for TaqMan allelic discrimination assay. Clinical phenotypes, coronary artery lesions (CAL) and intravenous immunoglobulin (IVIG) treatment outcomes were collected for analysis. Results Significant associations were found between CD209 polymorphisms (rs4804800, rs2287886, rs735240) and the risk of KD. Haplotype analysis for CD209 polymorphisms showed that A/A/G haplotype (P = 0.0002, OR = 1.61) and G/A/G haplotype (P = 0.0365, OR = 1.52) had higher risk of KD as compared with G/G/A haplotype in rs2287886/rs735239/rs735240 pairwise allele analysis. There were no significant association in KD with regards to CAL formation and IVIG treatment responses. Conclusion CD209 polymorphisms were responsible for the susceptibility of KD, but not CAL formation and IVIG treatment responsiveness. PMID:25148534

Predictors of nonresponse to intravenous immunoglobulin therapy in Kawasaki disease

Directory of Open Access Journals (Sweden)

Hyo Min Park

2013-02-01

Full Text Available &lt;b&gt;Purpose:&lt;/b&gt; It has been reported that 10% to 20% of children with Kawasaki disease (KD will not respond to intravenous immunoglobulin (IVIG treatment. In this study, we aimed to identify useful predictors of therapeutic failure in children with KD. &lt;b&gt;Methods:&lt;/b&gt; We examined 309 children diagnosed with KD at the Kyungpook National University Hospital and the Inje University Busan Paik Hospital between January 2005 and June 2011. We retrospectively reviewed their medical records and analyzed multiple parameters in responders and nonresponders to IVIG. &lt;b&gt;Results:&lt;/b&gt; Among the 309 children, 30 (9.7% did not respond to IVIG. They had significantly higher proportion of neutrophils, and higher levels of aspartate aminotransferase, alanine aminotransferase (ALT, total bilirubin, and N-terminal fragment of B-type natriuretic peptide than did responders. IVIGnonresponders had a significantly longer duration of hospitalization, and more frequently experienced coronary artery lesion, and sterile pyuria. No differences in the duration of fever at initial treatment or, clinical features were noted. &lt;b&gt;Conclusion:&lt;/b&gt; Two independent predictors (ALT?#248;4 IU/L, total bilirubin?#240;.9 mg/dL for nonresponse were confirmed through multivariate logistic regression analysis. Thus elevated ALT and total bilirubin levels might be useful in predicting nonresponse to IVIG therapy in children with KD.

Advanced light-water reactors

International Nuclear Information System (INIS)

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

1990-01-01

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

Use of Lagrangian transport models and Sterilized High Volume Sampling to pinpoint the source region of Kawasaki disease and determine the etiologic agent

Science.gov (United States)

Curcoll Masanes, Roger; Rodó, Xavier; Anton, Jordi; Ballester, Joan; Jornet, Albert; Nofuentes, Manel; Sanchez-Manubens, Judith; Morguí, Josep-Anton

2015-04-01

Kawasaki disease (KD) is an acute, coronary artery vasculitis of young children, and still a medical mystery after more than 40 years. A former study [Rodó et al. 2011] demonstrated that certain patterns of winds in the troposphere above the earth's surface flowing from Asia were associated with the times of the annual peak in KD cases and with days having anomalously high numbers of KD patients. In a later study [Rodó et al. 2014], we used residence times from an Air Transport Model to pinpoint the source region for KD. Simulations were generated from locations spanning Japan from days with either high or low KD incidence. In order to cope with stationarity of synoptic situations, only trajectories for the winter months, when there is the maximum in KD cases, were considered. Trajectories traced back in time 10 days for each dataset and location were generated using the flexible particle Lagrangian dispersion model (FLEXPART Version 8.23 [Stohl et al. 2005]) run in backward mode. The particles modeled were air tracers, with 10,000 particles used on each model run. The model output used was residence time, with an output grid of 0.5° latitude × longitude and a time resolution of 3 h. The data input used for the FLEXPART model was gridded atmospheric wind velocity from the European Center for Medium-Range Weather Forecasts Re-Analysis (ERA-Interim at 1°). Aggregates of winter period back-trajectories were calculated for three different regions of Japan. A common source of wind air masses was located for periods with High Kawasaki disease. Knowing the trajectories of winds from the air transport models, a sampling methodology was developed in order to capture the possible etiological agent or other tracers that could have been released together. This methodology is based on the sterilized filtering of high volumes of the transported air at medium tropospheric levels by aircraft sampling and a later analyze these filters with adequate techniques. High purity

Training experience at Experimental Breeder Reactor II

International Nuclear Information System (INIS)

Driscoll, J.W.; McCormick, R.P.; McCreery, H.I.

1978-01-01

The EBR-II Training Group develops, maintains,and oversees training programs and activities associated with the EBR-II Project. The group originally spent all its time on EBR-II plant-operations training, but has gradually spread its work into other areas. These other areas of training now include mechanical maintenance, fuel manufacturing facility, instrumentation and control, fissile fuel handling, and emergency activities. This report describes each of the programs and gives a statistical breakdown of the time spent by the Training Group for each program. The major training programs for the EBR-II Project are presented by multimedia methods at a pace controlled by the student. The Training Group has much experience in the use of audio-visual techniques and equipment, including video-tapes, 35 mm slides, Super 8 and 16 mm film, models, and filmstrips. The effectiveness of these techniques is evaluated in this report

A central European training course on reactor physics and kinetics - the 'Eugene Wigner Course' - Organisers view

International Nuclear Information System (INIS)

Boeck, H.; Villa, M.; Matejka, K.; Sklenka, L.; Miglierini, M.; Sukods, C.

2004-01-01

Initiated by the 5th Framework Program of the European Commission, the European Nuclear Engineering Network (ENEN) is preparing the future European Nuclear Education schemes, degrees and requirements. To fully utilize the benefits of international cooperation and to promote the knowledge of students in nuclear engineering a 2.5 weeks course has been held, both in spring 2003 and 2004. The main emphasis of the course is to perform reactor physics and kinetics experiments on three different research- and training reactors in three different locations (Vienna, Prague, Budapest). The experimental work is preceded by theoretical lectures aiming to prepare the students for the experiments (Bratislava). The students' work will be evaluated, and upon success the students will get a certificate. The finally accepted credit (ECTS) value will be determined by the students' home university. The ENEN-recommended value is between 6 and 8 ECTS. The more detailed description of the course will be given in the full paper. (author)

Pilot program: NRC severe reactor accident incident response training manual. Overview and summary of major points

International Nuclear Information System (INIS)

McKenna, T.J.; Martin, J.A. Jr.; Giitter, J.G.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Watkins

1987-02-01

Overview and Summary of Major Points is the first in a series of volumes that collectively summarize the U.S. Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume describes elementary perspectives on severe accidents and accident assessment. Other volumes in the series are: Volume 2-Severe Reactor Accident Overview; Volume 3- Response of Licensee and State and Local Officials; Volume 4-Public Protective Actions-Predetermined Criteria and Initial Actions; Volume 5 - U.S. Nuclear Regulatory Commission. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. The volumes have been organized into these training modules to accommodate the scheduling and duty needs of participating NRC staff. Each volume is accompanied by an appendix of slides that can be used to present this material

University Reactor Instrumentation Program

International Nuclear Information System (INIS)

Vernetson, W.G.

1992-11-01

Recognizing that the University Reactor Instrumentation Program was developed in response to widespread needs in the academic community for modernization and improvement of research and training reactors at institutions such as the University of Florida, the items proposed to be supported by this grant over its two year period have been selected as those most likely to reduce foreed outages, to meet regulatory concerns that had been expressed in recent years by Nuclear Regulatory Commission inspectors or to correct other facility problems and limitations. Department of Energy Grant Number DE-FG07-90ER129969 was provided to the University of Florida Training Reactor(UFTR) facility through the US Department of Energy's University Reactor Instrumentation Program. The original proposal submitted in February, 1990 requested support for UFTR facility instrumentation and equipment upgrades for seven items in the amount of $107,530 with $13,800 of this amount to be the subject of cost sharing by the University of Florida and $93,730 requested as support from the Department of Energy. A breakdown of the items requested and total cost for the proposed UFTR facility instrumentation and equipment improvements is presented

Acute kidney injury and cholestasis associated with Kawasaki disease in a 9-year-old: Case report.

Science.gov (United States)

Martínez Vázquez, José Allan; Sánchez García, Carlos; Rodríguez Muñoz, Lorena; Martínez Ramírez, Rogelio Osvaldo

2017-12-15

Kawasaki disease (KD) is a systemic vasculitis frequent in children younger than 5 years of age. It involves coronary arteries and other medium-sized vessels. There also exists evidence of inflammatory and proliferative changes affecting the biliary tract and lymphocyte infiltration of the renal interstitial. We describe the case of a 9-year-old girl who developed high-grade fever, bilateral non-purulent conjunctivitis, «strawberry» tongue, desquamation of the fingers and toes, cholestatic syndrome, edema and elevated serum creatinine. KD is a diagnostic challenge for the pediatrician. In every patient with high-grade fever, cholestasis and acute kidney injury, KD should be included in the differential diagnosis, even though more research is necessary to evaluate this atypical association. Copyright © 2017 Elsevier España, S.L.U. and Sociedad Española de Reumatología y Colegio Mexicano de Reumatología. All rights reserved.

RA reactor operation and maintenance in 1992, Part 1

International Nuclear Information System (INIS)

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

1992-01-01

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

Reactor handbook. 2. rev. ed.

International Nuclear Information System (INIS)

Lederer, B.J.; Wildberg, D.W.

1992-01-01

On the basis of the guidelines on expert knowledge, the book discusses the subjects of atomic physics, heat transfer, nuclear power plants, reactor materials, radiation protection, reactor safety, reactor instrumentation, and reactor operation, with special regard to nuclear power plants with LWR-type reactors. The book is intended for shift personnel, especially gang bosses, reactor operators, and control station operators: for this reason a practical and rather popular style has been chosen. However, the book will also be a manual for other operating personnel, personnel of producer companies, expert organisations, authorities, and students. It can be used as a textbook for staff training, a manual for the practice, and as accompanying book for teaching at nuclear engineering schools. (orig.) With 173 figs [de

FISA 2009 - 7th European Commission conference on EURATOM research and training in reactor systems. Conference proceedings

International Nuclear Information System (INIS)

Goethem, G. van; Manolatos, P.; Hugon, M.; Bhatnagar, V.; Deffrennes, M.; Webster, S.

2010-01-01

The main achievements of the first series of projects under EURATOM FP-7 for nuclear research and training activities (2007 to 2011) were discussed. Approximately 500 participants were registered at FISA 2009 and at the 7 post-conference workshops, representing a wide audience of nuclear scientists and decision makers coming from 32 countries worldwide. The focus of the conference was on scientific and technological research in the following areas: nuclear plant life management for existing reactors (Generation II), severe accident management (Generation III), assessment of future nuclear fission systems (Generation IV), partitioning and transmutation systems (innovative fuels), access to large research infrastructures, and nuclear education and training. Special attention was devoted to the societal and industrial goals of GIF: sustainability, industrial competitiveness, safety and reliability, proliferation resistance. (orig.)

Hemodynamic Based Coronary Artery Aneurysm Thrombosis Risk Stratification in Kawasaki Disease Patients

Science.gov (United States)

Grande Gutierrez, Noelia; Mathew, M.; McCrindle, B.; Kahn, A.; Burns, J.; Marsden, A.

2017-11-01

Coronary artery aneurysms (CAA) as a result of Kawasaki Disease (KD) put patients at risk for thrombosis and myocardial infarction. Current AHA guidelines recommend CAA diameter >8 mm or Z-score >10 as the criterion for initiating systemic anticoagulation. Our hypothesis is that hemodynamic data derived from computational blood flow simulations is a better predictor of thrombosis than aneurysm diameter alone. Patient-specific coronary models were constructed from CMRI for a cohort of 10 KD patients (5 confirmed thrombosis cases) and simulations with fluid structure interaction were performed using the stabilized finite element Navier-Stokes solver available in SimVascular. We used a closed-loop lumped parameter network (LPN) to model the heart and vascular boundary conditions coupled numerically to the flow solver. An automated parameter estimation method was used to match LPN values to clinical data for each patient. Hemodynamic data analysis resulted in low correlation between Wall Shear Stress (WSS)/ Particle Residence Time (PRT) and CAA diameter but demonstrates the positive correlation between hemodynamics and adverse patient outcomes. Our results suggest that quantifying WSS and PRT should enable identification of regions at higher risk of thrombosis. We propose a quantitative method to non-invasively assess the abnormal flow in CAA following KD that could potentially improve clinical decision-making regarding anticoagulation therapy.

Identification of candidate diagnostic serum biomarkers for Kawasaki disease using proteomic analysis

Science.gov (United States)

Kimura, Yayoi; Yanagimachi, Masakatsu; Ino, Yoko; Aketagawa, Mao; Matsuo, Michie; Okayama, Akiko; Shimizu, Hiroyuki; Oba, Kunihiro; Morioka, Ichiro; Imagawa, Tomoyuki; Kaneko, Tetsuji; Yokota, Shumpei; Hirano, Hisashi; Mori, Masaaki

2017-01-01

Kawasaki disease (KD) is a systemic vasculitis and childhood febrile disease that can lead to cardiovascular complications. The diagnosis of KD depends on its clinical features, and thus it is sometimes difficult to make a definitive diagnosis. In order to identify diagnostic serum biomarkers for KD, we explored serum KD-related proteins, which differentially expressed during the acute and recovery phases of two patients by mass spectrometry (MS). We identified a total of 1,879 proteins by MS-based proteomic analysis. The levels of three of these proteins, namely lipopolysaccharide-binding protein (LBP), leucine-rich alpha-2-glycoprotein (LRG1), and angiotensinogen (AGT), were higher in acute phase patients. In contrast, the level of retinol-binding protein 4 (RBP4) was decreased. To confirm the usefulness of these proteins as biomarkers, we analyzed a total of 270 samples, including those collected from 55 patients with acute phase KD, by using western blot analysis and microarray enzyme-linked immunosorbent assays (ELISAs). Over the course of this experiment, we determined that the expression level of these proteins changes specifically in the acute phase of KD, rather than the recovery phase of KD or other febrile illness. Thus, LRG1 could be used as biomarkers to facilitate KD diagnosis based on clinical features. PMID:28262744

Perspectives on reactor safety. Revision 1

International Nuclear Information System (INIS)

Haskin, F.E.; Hodge, S.A.

1997-11-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

Perspectives on reactor safety. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

1997-11-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

A Prediction Study of Aluminum Alloy Oxidation of the Fuel Cladding in Jordan Research and Training Reactor

Energy Technology Data Exchange (ETDEWEB)

Tahk, Y. W.; Oh, J. Y.; Lee, B. H.; Seo, C. G.; Chae, H. T.; Yim, J. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2010-10-15

U{sub 3}Si{sub 2}-Al dispersion fuel with Al cladding will be used for Jordan Research and Training Reactor (JRTR). Aluminum alloy cladding experiences the oxidation layer growth on the surface during the reactor operation. The formation of oxides on the cladding affects fuel performance by increasing fuel temperature. According to the current JRTR fuel management scheme and operation strategy for 5 MW power, a fresh fuel is discharged after 900 effective full power days (EFPD) with 18 cycles of 50 days loading. For the proper prediction of the aluminum oxide thickness of fuel cladding during the long residence time, a reliable model is needed. In this work, several oxide thickness prediction models are compared with the measured data from in-pile test by RERTR program. Moreover, specific parametric studies and a preliminary prediction of the aluminum alloy oxidation using the latest model are performed for JRTR fuel

TRIGA reactor main systems

International Nuclear Information System (INIS)

Boeck, H.; Villa, M.

2007-01-01

This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

Overcoming the effects of stress on reactor operator performance

International Nuclear Information System (INIS)

He Xuhong; Wei Li; Zhao Bingquan

2003-01-01

Reactor operators may be exposed to significant levels of stress during plant emergencies and their performance may be affected by the stress. This paper first identified the potential sources of stress in the nuclear power plant, then discussed the ways in which stress is likely to affect the reactor operators, and finally identified several training approaches for reducing or eliminating stress effects. The challenges for effective stress reducing training may seem daunting, yet the challenges are real and must be addressed. This paper reviewed researches in training design, knowledge and skill acquisition, and training transfer point to a number of strategies that can be used to address these challenges and lead to more effective training and development. (author)

Overcoming the effects of stress on reactor operator performance

Energy Technology Data Exchange (ETDEWEB)

He Xuhong; Wei Li; Zhao Bingquan [Tsinghua Univ., Nuclear Power Plant Simulation Training Center, Beijing (China)

2003-03-01

Reactor operators may be exposed to significant levels of stress during plant emergencies and their performance may be affected by the stress. This paper first identified the potential sources of stress in the nuclear power plant, then discussed the ways in which stress is likely to affect the reactor operators, and finally identified several training approaches for reducing or eliminating stress effects. The challenges for effective stress reducing training may seem daunting, yet the challenges are real and must be addressed. This paper reviewed researches in training design, knowledge and skill acquisition, and training transfer point to a number of strategies that can be used to address these challenges and lead to more effective training and development. (author)

Operation and utilizations of Dalat nuclear research reactor

International Nuclear Information System (INIS)

Hien, P.Z.

1988-01-01

The reconstructed Dalat nuclear research reactor was commissioned in March 1984 and up to September 1988 more than 6200 hours of operation at nominal power have been recorded. The major utilizations of the reactor include radioisotope production, activation analysis, nuclear data research and training. A brief review of the utilizations of the reactor is presented. Some aspects of reactor safety are also discussed. (author)

Arkansas Tech University TRIGA nuclear reactor

International Nuclear Information System (INIS)

Sankoorikal, J.; Culp, R.; Hamm, J.; Elliott, D.; Hodgson, L.; Apple, S.

1990-01-01

This paper describes the TRIGA nuclear reactor (ATUTR) proposed for construction on the campus of Arkansas Tech University in Russellville, Arkansas. The reactor will be part of the Center for Energy Studies located at Arkansas Tech University. The reactor has a steady state power level of 250 kW and can be pulsed with a maximum reactivity insertion of $2.0. Experience gained in dismantling and transporting some of the components from Michigan State University, and the storage of these components will be presented. The reactor will be used for education, training, and research. (author)

Characteristics and Fate of Systemic Artery Aneurysm after Kawasaki Disease.

Science.gov (United States)

Hoshino, Shinsuke; Tsuda, Etsuko; Yamada, Osamu

2015-07-01

To determine the long-term outcome of systemic artery aneurysms (SAAs) after Kawasaki disease (KD). We investigated the characteristics and the fate of SAAs in 20 patients using medical records and angiograms. The age of onset of KD ranged from 1 month to 20 months. The interval from the onset of KD to the latest angiogram ranged from 16 months to 24 years. The regression rate of peripheral artery aneurysm and the frequency of stenotic lesions were analyzed by the Kaplan-Meier method in 11 patients who had undergone initial angiography within 4 months. The mean duration of fever was 24 ± 12 days. All 20 patients had at least 1 symmetric pair of aneurysms in bilateral peripheral arteries, and 16 patients had multiple SAAs. The distributions of SAAs was as follows: brachial artery, 30; common iliac artery, 20; internal iliac artery, 21; abdominal aortic aneurysm, 7; and others, 29. The frequencies of regression of SAA and of the occurrence of stenotic lesions at 20 years after the onset of KD were 51% and 25%, respectively (n = 42). The diameter of all SAAs in the acute phase leading to stenotic lesions in the late period was >10 mm. SAAs occurred symmetrically and were multiple in younger infants and those with severe acute vasculitis. The fate of SAAs resembles that of coronary artery aneurysms, and depends on the diameter during the acute phase. Larger SAAs can lead to stenotic lesions in the late period. Copyright © 2015 Elsevier Inc. All rights reserved.

RA reactor operation and maintenance in 1996, Part 1

International Nuclear Information System (INIS)

Sotic, O.; Cupac, S.; Sulem, B.; Zivotic, Z.; Mikic, N.; Tanaskovic, M.

1996-01-01

During the previous period RA reactor was not operated because the Committee of Serbian ministry for health and social care has cancelled the operation licence in August 1984. The reason was the non existing emergency cooling system and lack of appropriate filters in the special ventilation system. The planned major tasks were fulfilled: building of the new emergency cooling system, reconstruction of the existing ventilation system, and renewal of the reactor power supply system. The existing RA reactor instrumentation was dismantled. Renewal of the reactor instrumentation was started but but it is behind the schedule because the delivery of components from USSR was stopped for political reasons. Since the RA reactor is shutdown since 1984, it is high time for decision making of its future status. Possible solutions for the future status of the RA reactor discussed in this report are: renewal of reactor components for the reactor restart, conservation of the reactor (temporary shutdown) or permanent reactor shutdown. Control and maintenance of the reactor instrumentation and devices was done regularly but dependent on the availability of the spare parts and financial means. Training of the existing personnel and was done regularly, but the new staff has no practical training since the reactor is not operated. Lack of financial support influenced strongly the status of RA reactor [sr

The determination of the thermal neutron and gamma fluxes at the Maryland University Training Reactor using thermoluminescent dosimetry

International Nuclear Information System (INIS)

Karceski, Jeffrey David; Ebert, David D.; Munno, Frank J.

1988-01-01

Determination of the dose received by a material in a mixed gamma and neutron field is of paramount concern to any research reactor owner. This dose can be separated into three distinguishable parts using standard thermoluminescent dosimetry (TLD) responses: 1) thermal neutron dose, 2) fission gamma dose, and 3) fission product gamma dose. For the Maryland University Training Reactor (MUTR), these respective fluences were determined for each of the associated experimental facilities. Quantifying the magnitude of the gamma and thermal neutron exposures at various reactor power levels was accomplished using Li-6F and Li-7F TLDs, respectively. These two types of dosimetry were chosen given the following considerations: 1) there is no existing standard established for fluence determination in a mixed field, 2) the LiF TLDs have a wide range of sensitivity to radiation, from 0.01 mR to 10,000 R, and 3) LiF TLDs are easy to read given the proper equipment. Standardization of the gamma/neutron doses was accomplished using the 500,000 Rad/hr Co-60 gamma source also located at the University of Maryland. (author)

76 FR 70778 - Advisory Committee on Reactor Safeguards; Notice of Meeting

Science.gov (United States)

2011-11-15

... Regarding Concentration Averaging and Encapsulation of Low-Level Radioactive Waste (Open)--The Committee... Branch Technical Position on Concentration Averaging and Encapsulation of Low-Level Radioactive Waste. 1... Hitachi Nuclear Energy Licensing Topical Report NEPC-33173P-A, Supplement 2, Parts 1, 2, and 3, ``Analysis...

Development of technologies for nuclear reactors of small and medium sized; Desarrollo de Tecnologias para Reactores Nucleares de pequeno y medio tamano

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-08-15

This meeting include: countries presentations, themes and objectives of the training course, reactor types, design, EPR, APR1400, A P 1000, A PWR, ATMEA 1, VVER-1000, A PWR, ATMEA 1, VVER 1200, Boiling Water Reactor, A BWR, A BWR -II, ESBUR, Ke ren, AREVA, Heavy Water Reactor, Candu 6, Acr-1000, HWR, Bw, Iris, CAREM NuCcale, Smart, KLT-HOS, Westinghouse small modular Reactor, Gas Cooled Reactors, PBMR, React ores enfriados con metales liquidos, Hs, Prism,Terra Power, Hyper ion, appliance's no electric as de energia, Generation IV Reactors,VHTR, Gas Fast Reactor, Sodium Fast Reactor, Molten salt Reactor, Lfr, Water Cooled Reactor, Technology Assessment Process, Fukushima accident.

Magnox Electric Littlebrook reactor inspection and repair rehearsal facility

International Nuclear Information System (INIS)

Barnes, S.A.; Clayton, R.; Gaydon, B.G.; Ramsey, B.H.

1996-01-01

Magnox reactors, although designed to be maintenance free during their operational life, have nevertheless highlighted the need for test rig facilities to train operators in the methods and techniques of reactor inspection and repair. The history of the facility for reactor engineering development (FRED) is described and its present role as a repair rehearsal facility noted. Advances in computer graphics may, in future, mean that such operator training will be virtual reality rather than analog reality based; however the need for such rigs to commission techniques and equipment and to establish performance and reliability is likely to continue. (UK)

Physics and kinetics of TRIGA reactor

International Nuclear Information System (INIS)

Boeck, H.; Villa, M.

2007-01-01

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

Service to the Electric Utility Industry by the Ford Nuclear Reactor, University of Michigan

International Nuclear Information System (INIS)

Burn, R.R.; Simpson, P.A.; Cook, G.M.

1993-01-01

Since 1977, the staff of the University of Michigan's Ford Nuclear Reactor has been providing irradiation, testing, analytical, and training services to electric utilities and to suppliers of the nuclear electric utility industry. This paper discusses the reactor's irradiation facilities; reactor programs and utilization; materials testing programs; neutron activation analysis activities; and training programs conducted

The Text of the Instrument concerning the Agency's Assistance to Mexico for the Establishment of a Training Reactor Project

Energy Technology Data Exchange (ETDEWEB)

NONE

1972-06-05

The texts of the Agreement between the Agency the the Governments of the Federal Republic of Germany and Mexico concerning the Agency's assistance for the establishment of a training reactor project in Mexico, and of a letter relating thereto which the Resident Representative of the Federal Republic of Germany addressed to the Director General, are reproduced herein for the information of all Members. The Agreement entered into force on 21 December 1971.

Development of high conversion boiling water reactor

International Nuclear Information System (INIS)

Yamashita, Jun-ichi; Mochida, Takaaki; Uchikawa, Sadao.

1988-01-01

It is expected that the period of LWRs being the main source of electric power supply becomes long, therefore, the development of next generation LWRs placing emphasis on the effective utilization of uranium resources and the improvement of economical efficiency is necessary. In this paper, as the next generation BWRs subsequent to ABWRs, the concept of the core of high conversion type BWRs is reported, in which emphasis is placed on the saving of natural uranium resources by raising the rate of conversion to plutonium. This core is that of realizing the high rate of conversion by utilizing the void in the core, which is the feature of BWRs, and the case of making the change of the core structure relatively small by using cross type control rods and the case of changing the core structure for further heightening the rate of conversion and making control rods into cluster type are described. In order to meet the demand like this, Hitachi Ltd. has engaged in the development of the concept of the core of next generation LWRs. In the high conversion type BWRs, there is not large change in the reactor system and turbine system from the current BWRs. The features and the concept of the core of high conversion type BWRs are described. (Kako, I.)

Simulating Neutronic Core Parameters in a Research and Test Reactor

International Nuclear Information System (INIS)

Selim, H.K.; Amin, E.A.; Koutb, M.E.

2011-01-01

The present study proposes an Artificial Neural Network (ANN) modeling technique that predicts the control rods positions in a nuclear research reactor. The neutron, flux in the core of the reactor is used as the training data for the neural network model. The data used to train and validate the network are obtained by modeling the reactor core with the neutronic calculation code: CITVAP. The type of the network used in this study is the feed forward multilayer neural network with the backpropagation algorithm. The results show that the proposed ANN has good generalization capability to estimate the control rods positions knowing neutron flux for a research and test reactor. This method can be used to predict critical control rods positions to be used for reactor operation after reload

Pilot program: NRC severe reactor accident incident response training manual: Public protective actions: Predetermined criteria and initial actions

International Nuclear Information System (INIS)

Martin, J.A. Jr.; McKenna, T.J.; Miller, C.W.; Hively, L.M.; Sharpe, R.W.; Giitter, J.G.; Watkins, R.M.

1987-02-01

This pilot training manual has been written to fill the need for a general text on NRC response to reactor accidents. The manual is intended to be the foundation for a course for all NRC response personnel. Public Protective Actions - Predetermined Criteria and Initial Actions is the fourth in a series of volumes that collectively summarize the US Nuclear Regulatory Commission (NRC) emergency response during severe power reactor accidents and provide necessary background information. This volume reviews public protective action criteria and objectives, their bases and implementation, and the expected public response. Each volume serves, respectively, as the text for a course of instruction in a series of courses for NRC response personnel. These materials do not provide guidance or license requirements for NRC licensees. Each volume is accompanied by an appendix of slides that can be used to present this material. The slides are called out in the text

Lead-cooled flexible conversion ratio fast reactor

International Nuclear Information System (INIS)

Nikiforova, Anna; Hejzlar, Pavel; Todreas, Neil E.

2009-01-01

Lead-cooled reactor systems capable of accepting either zero or unity conversion ratio cores depending on the need to burn actinides or operate in a sustained cycle are presented. This flexible conversion ratio reactor is a pool-type 2400 MWt reactor coupled to four 600 MWt supercritical CO 2 (S-CO 2 ) power conversion system (PCS) trains through intermediate heat exchangers. The cores which achieve a power density of 112 kW/l adopt transuranic metallic fuel and reactivity feedbacks to achieve inherent shutdown in anticipated transients without scram, and lead coolant in a pool vessel arrangement. Decay heat removal is accomplished using a reactor vessel auxiliary cooling system (RVACS) complemented by a passive secondary auxiliary cooling system (PSACS). The transient simulation of station blackout (SBO) using the RELAP5-3D/ATHENA code shows that inherent shutdown without scram can be accommodated within the cladding temperature limit by the enhanced RVACS and a minimum (two) number of PSACS trains. The design of the passive safety systems also prevents coolant freezing in case all four of the PSACS trains are in operation. Both cores are also shown able to accommodate unprotected loss of flow (ULOF) and unprotected transient overpower (UTOP) accidents using the S-CO 2 PCS.

Development of the supporting system of the Monju advanced reactor simulator (MARS)

International Nuclear Information System (INIS)

Koyagoshi, Naoki; Sasaki, Kazuichi; Sawada, Makoto

2002-10-01

The MARS has been operating for operator training and operation procedure's verification of the prototype fast breeder reactor 'Monju' since April 1991. In order to carry out the above results more effectively, the MARS supporting system which consists of several computer system has being developed. This report covers the following three supporting systems developed from 1994 to 2001 and study on evaluation method of Monju operator training data. Expanded Monju visual animation system. The Monju visual animation system was developed to visualize the inner structure of equipments and the parameters without measuring points. This system is used for training form 1993. And then, the training limits of the system has been extended. Development of the Monju min simulator for reactor core analysis. Development of the Monju min simulator which analyzes thermo-hydraulic behavior in the Monju reactor in detail is proceeding with the aims; of upgrading Monju operator training effect. The obtained results will be reflected to remodeling of MARS's reactor core analysis mode. Development of the severe accident CAI (Computer Assisted Instruction) system. The prototype system which supports study on accident management was developed. This system will be converted when the severe accident procedure of Monju is fixed, and it will be used for training. Study on evaluation method of Monju operate training data. In order to reconstruct the operator training system, the evaluation method of training data was considered. The availability has been checked as a result of evaluating crew communication using this method. (author)

E-chem page: A Support System for Remote Diagnosis of Water Quality in Boiling Water Reactors

International Nuclear Information System (INIS)

Naohiro Kusumi; Takayasu Kasahara; Kazuhiko Akamine; Kenji Tada; Naoshi Usui; Nobuyuki Oota

2002-01-01

It is important to control and maintain water quality for nuclear power plants. Chemical engineers sample and monitor reactor water from various subsystems and analyze the chemical quality as routine operations. With regard to controlling water quality, new technologies have been developed and introduced to improve the water quality from both operation and material viewpoints. To maintain the quality, it is important to support chemical engineers in evaluating the water quality and realizing effective retrieval of stored data and documents. We have developed a remote support system using the Internet to diagnose BWR water quality, which we call e-chem page. The e-chem page integrates distributed data and information in a Web server, and makes it easy to evaluate the data on BWR water chemistry. This system is composed of four functions: data transmission, water quality evaluation, inquiry and history retrieval system, and reference to documents on BWR water chemistry. The developed system is now being evaluated in trial operations by Hitachi, Ltd. and an electric power company. In addition diagnosis technology applying independent component analysis (ICA) is being developed to improve predictive capability of the system. This paper describes the structure and function of the e-chem page and presents results of obtained with the proposed system for the prediction of chemistry conditions in reactor water. (authors)

Classification of coronary artery tissues using optical coherence tomography imaging in Kawasaki disease

Science.gov (United States)

Abdolmanafi, Atefeh; Prasad, Arpan Suravi; Duong, Luc; Dahdah, Nagib

2016-03-01

Intravascular imaging modalities, such as Optical Coherence Tomography (OCT) allow nowadays improving diagnosis, treatment, follow-up, and even prevention of coronary artery disease in the adult. OCT has been recently used in children following Kawasaki disease (KD), the most prevalent acquired coronary artery disease during childhood with devastating complications. The assessment of coronary artery layers with OCT and early detection of coronary sequelae secondary to KD is a promising tool for preventing myocardial infarction in this population. More importantly, OCT is promising for tissue quantification of the inner vessel wall, including neo intima luminal myofibroblast proliferation, calcification, and fibrous scar deposits. The goal of this study is to classify the coronary artery layers of OCT imaging obtained from a series of KD patients. Our approach is focused on developing a robust Random Forest classifier built on the idea of randomly selecting a subset of features at each node and based on second- and higher-order statistical texture analysis which estimates the gray-level spatial distribution of images by specifying the local features of each pixel and extracting the statistics from their distribution. The average classification accuracy for intima and media are 76.36% and 73.72% respectively. Random forest classifier with texture analysis promises for classification of coronary artery tissue.

Simulation of the behaviour of small and medium nuclear reactors on PCs

International Nuclear Information System (INIS)

Lyon, R.B.

1999-01-01

The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. One of the simulation programs distributed by the IAEA is the the Advanced Reactor Simulator which simulates the behaviour of BWR, PWR and HWR reactor types. For this package, the modeling approach and assumptions are broadly described, together with a general description of the operation of the computer program. (author)

Training of maintenance personnel

International Nuclear Information System (INIS)

Rabouhams, J.

1986-01-01

This lecture precises the method and means developed by EDF to ensure the training of maintenance personnel according to their initial educational background and their experience. The following points are treated: General organization of the training for maintenance personnel in PWR and GCR nuclear power stations and in Creys Malville fast breeder reactor; Basic nuclear training and pedagogical aids developed for this purpose; Specific training and training provided by contractors; complementary training taking into account the operation experience and feedback; Improvement of velocity, competence and safety during shut-down operations by adapted training. (orig.)

Guide to good practices for training and qualification of instructors. DOE handbook

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

Purpose of this guide is to provide contractor training organizations with information that can be used to verify the adquacy and/or modify existing instructor training programs, or to develop new training programs. It contains good practices for the training and qualification of technical instructors and instructional technologists at DOE reactor and non-reactor nuclear facilities. It addresses the content of initial and continuing instructor training programs, evaluation of instructor training programs, and maintenance of instructor training records.

Report of the reactor Operators Service - Annex F

International Nuclear Information System (INIS)

Zivotic, Z.

1992-01-01

RA reactor operators service is organized in two groups: permanent staff (chief operator, chief shift operators and operators) and changeable group which is formed according to the particular operation needs for working in shifts. For continuous training of the existing operator staff the Service has prepared and published eleven booklets: Nuclear reactor; RA reactor primary coolant loop; System for purification of heavy water; reactor helium system; system for technical water; electric power system; control and operation; ventilation system in the reactor building; special sewage system; construction properties of the reactor core; reactor building and installations. During the reporting period there have been no accidents nor incidents that could affect the reactor personnel [sr

RB research nuclear reactor, Annual report for 1981

International Nuclear Information System (INIS)

Markovic, H.; Sotic, O.; Pesic, M.; Vranic, S.; Zivkovic, B.; Bogdanovic, M.; Petronijevic, M.

1981-01-01

The annual report for 1981 includes the following: utilization of the RB reactor; accident and incidents analysis; description of the reactor equipment status; dosimetry and radiation protection; RB reactor staff; financial data. Seven Annexes to this report are concerned with: maintenance of the reactor components and equipment, including nuclear fuel, heavy water, reactor vessel, heavy water coolant circuit, experimental platforms, absorption rods; maintenance of the electric power supply system, neutron source equipment, crane; control and maintenance of ventilation and heating systems, gas and comprised gas systems, fire protection system; plan for renewal of the reactor components; contents of the RB reactor safety report; reactor staff; review of measured radiation doses; experimental methods; training of the staff; and financial report

Artificial intelligence and training of nuclear reactor personnel

International Nuclear Information System (INIS)

Uhrig, R.E.; Buenaflor, M.T.

1987-01-01

Expert computer systems offer an excellent and effective means to reduce the potential for operator error, and improve plant safety and reliability. For the training field the benefits are twofold. First, the inclusion of advisory expert systems in the control environments (the physical control room and its simulator) offer a continuous source of on-the-job diagnostic training. Second, expert systems specifically designed for training are feasible for specialized license/requalification training in higher order analytical skills. This paper consists of two parts. In the first section, the improvements for on-the-job training are examined. In the second section, the benefits for the overall training program are explored in terms of technical and educational rationales

Innovations and enhancements in neutronic analysis of the Big-10 university research and training reactors based on the AGENT code system

International Nuclear Information System (INIS)

Hursin, M.; Shanjie, X.; Burns, A.; Hopkins, J.; Satvat, N.; Gert, G.; Tsoukalas, L. H.; Jevremovic, T.

2006-01-01

Introduction. This paper summarizes salient aspects of the 'virtual' reactor system developed at Purdue Univ. emphasizing efficient neutronic modeling through AGENT (Arbitrary Geometry Neutron Transport) a deterministic neutron transport code. DOE's Big-10 Innovations in Nuclear Infrastructure and Education (INIE) Consortium was launched in 2002 to enhance scholarship activities pertaining to university research and training reactors (URTRs). Existing and next generation URTRs are powerful campus tools for nuclear engineering as well as a number of disciplines that include, but are not limited to, medicine, biology, material science, and food science. Advancing new computational environments for the analysis and configuration of URTRs is an important Big-10 INIE aim. Specifically, Big-10 INIE has pursued development of a 'virtual' reactor, an advanced computational environment to serve as a platform on which to build operations, utilization (research and education), and systemic analysis of URTRs physics. The 'virtual' reactor computational system will integrate computational tools addressing the URTR core and near core physics (transport, dynamics, fuel management and fuel configuration); thermal-hydraulics; beam line, in-core and near-core experiments; instrumentation and controls; confinement/containment and security issues. Such integrated computational environment does not currently exist. The 'virtual' reactor is designed to allow researchers and educators to configure and analyze their systems to optimize experiments, fuel locations for flux shaping, as well as detector selection and configuration. (authors)

Training of nuclear facility personnel: boon or boondoggle

International Nuclear Information System (INIS)

Remick, F.J.

1975-01-01

The training of nuclear facility personnel has been a requirement of the reactor licensing process for over two decades. However, the training of nuclear facility personnel remains a combination of boon and boondoggle. The opportunity to develop elite, well trained, professionally aggressive reactor operation staffs is not being realized to its full potential. Improvements in the selection of personnel, training programs, operational tools and professional pride can result in improved plant operation and contribute to improved plant capacity factors. Industry, regulatory agencies, professional societies and universities can do much to improve standards and quality of the training of nuclear facility personnel and to improve the professional level of plant operation

Overview of the Dalat Nuclear Research Reactor

International Nuclear Information System (INIS)

Nguyen Nhi Dien; Nguyen Thai Sinh; Luong Ba Vien

2016-01-01

The present reactor called Dalat Nuclear Research Reactor (DNRR) has been reconstructed from the former TRIGA Mark II reactor which was designed by General Atomic (GA, San Diego, California, USA), started building in early 1960s, put into operation in 1963 and operated until 1968 at nominal power of 250 kW. In 1975, all fuel elements of the reactor were unloaded and shipped back to the USA. The DNRR is a 500-kW pool-type research reactor using light water as both moderator and coolant. The reactor is used as a neutron source for the purposes of: (1) radioactive isotope production; (2) neutron activation analysis; and (3) research and training

DOE University Reactor Sharing Program. Final technical report for 1996--1997

International Nuclear Information System (INIS)

Chappas, W.J.; Adams, V.G.

1998-01-01

The Department of Energy University Reactor Sharing Program at University of Maryland, College Park (UMCP) has, once again, stimulated a broad use of the reactor and radiation facilities by undergraduate and graduate students, visitors, and professionals. Participants are exposed to topics such as nuclear engineering, radiation safety, and nuclear reactor operations. This information is presented through various means including tours, slide presentations, experiments, and discussions. Student research using the MUTR is also encouraged. In addition, the Reactor Sharing Program here at the University of Maryland does not limit itself to the confines of the TRIGA reactor facility. Incorporated in the program are the Maryland University Radiation Effects Laboratory, and the UMCP 2 x 4 Thermal Hydraulic Loop. These facilities enhance and give an added dimension to the tours and experiments. The Maryland University Training Reactor (MUTR) and the associated laboratories are made available to any interested institution six days a week on a scheduled basis. Most institutions are scheduled at the time of their first request--a reflection of their commitment to the Reactor Sharing Program. The success of the past years by no means guarantees future success. Therefore, the reactor staff is more aggressively pursuing its outreach program, especially with junior colleges and universities without reactor or radiation facilities; more aggressively developing demonstration and training programs for students interested in careers in nuclear power and radiation technology; and more aggressively up-grading the reactor facilities--not only to provide a better training facility but to prepare for relicensing in the year 2000

Development of research reactor simulator and its application to dynamic test-bed

International Nuclear Information System (INIS)

Kwon, Kee-Choon; Baang, Dane; Park, Jae-Chang; Lee, Seung-Wook; Bae, Sung Won

2014-01-01

We developed a real-time simulator for 'High-flux Advanced Neutron Application ReactOr (HANARO), and the Jordan Research and Training Reactor (JRTR). The main purpose of this simulator is operator training, but we modified this simulator into a dynamic test-bed (DTB) to test the functions and dynamic control performance of reactor regulating system (RRS) in HANARO or JRTR before installation. The simulator hardware consists of a host computer, 6 operator stations, a network switch, and a large display panel. The software includes a mathematical model that implements plant dynamics in real-time, an instructor station module that manages user instructions, and a human machine interface module. The developed research reactor simulators are installed in the Korea Atomic Energy Research Institute nuclear training center for reactor operator training. To use the simulator as a dynamic test-bed, the reactor regulating system modeling software of the simulator was replaced by actual RRS cabinet, and was interfaced using a hard-wired and network-based interface. RRS cabinet generates control signals for reactor power control based on the various feedback signals from DTB, and the DTB runs plant dynamics based on the RRS control signals. Thus the Hardware-In-the-Loop Simulation between RRS and the emulated plant (DTB) has been implemented and tested in this configuration. The test result shows that the developed DTB and actual RRS cabinet works together simultaneously resulting in quite good dynamic control performances. (author)

TAP 1, Training Program Manual

International Nuclear Information System (INIS)

1991-01-01

Training programs at DOE nuclear facilities should provide well-trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor nuclear facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically determined job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two companion manuals provide additional information to assist contractors in their efforts to accredit training programs

Training of operating personnel for nuclear ships

International Nuclear Information System (INIS)

Lakey, J.R.A.; Gibbs, D.C.C.

1983-01-01

Training for Nuclear Power Plant Operators is provided by the Royal Navy in support of the Nuclear Submarine Programme which is based on the Pressurised Water Reactor. The Royal naval college has 21 years of experience in this training field in which the core is the preparation of graduate electro-mechanical engineers to assume the duties of marine engineer in command of a team of supporting Engineer Officers of the Watch and Fleet Chief Petty Officers. The paper describes the training programme and shows how it is monitored by academic, professional and naval authorities and indicates the use of feedback from the user. The lynch pin of the programme is a post-graduate diploma course in Nuclear Reactor Technology attended by graduates after gaining some practical experience at sea. The course which is described in detail makes use of simplified simulators and models to develop the principles, these are applied on the JASON Training Reactor with the emphasis on in-core experiments demonstrating reactivity effects and instrumentation interpretation. The training programme provides for interaction between academic education, practical experience, applied education, full plant simulation training and on-the-job training in which boards or examinations have to be successfully passed at each stage. (author)

Final Stage Development of Reactor Console Simulator

International Nuclear Information System (INIS)

Mohamad Idris Taib; Ridzuan Abdul Mutalib; Zareen Khan Abdul Jalil Khan; Mohd Khairulezwan Abdul Manan; Mohd Sabri Minhat; Nurfarhana Ayuni Joha

2013-01-01

The Reactor Console Simulator PUSPATI TRIGA Reactor was developed since end of 2011 and now in the final stage of development. It is will be an interactive tool for operator training and teaching of PUSPATI TRIGA Reactor. Behavior and characteristic for reactor console and reactor itself can be evaluated and understand. This Simulator will be used as complement for actual present reactor console. Implementation of human system interface (HSI) is using computer screens, keyboard and mouse. Multiple screens are used to match the physical of present reactor console. LabVIEW software are using for user interface and mathematical calculation. Polynomial equation based on control rods calibration data as well as operation parameters record was used to calculate and estimated reactor console parameters. The capabilities in user interface, reactor physics and thermal-hydraulics can be expanded and explored to simulation as well as modeling for New Reactor Console, Research Reactor and Nuclear Power Plant. (author)

Practical course on reactor instrumentation

International Nuclear Information System (INIS)

Boeck, H.; Villa, M.

2004-06-01

This course is based on the description of the instrumentation of the TRIGA-reactor Vienna, which is used for training research and isotope production. It comprises the following chapters: 1. instrumentation, 2. calibration of the nuclear channels, 3. rod drop time of the control rods, 4. neutron flux density measurements using compensated ionization, 5. neutron flux density measurement with fission chambers (FC), 6. neutron flux density measurement with self-powered neutron detectors (SPND), 7. pressurized water reactor simulator, 8. verification of the radiation level during reactor operation. There is one appendix about neutron-sensitive thermocouples. (nevyjel)

Operation and maintenance of the RB reactor, Annual report for 1977

International Nuclear Information System (INIS)

Sotic, O.; Vranic, S.

1977-01-01

The annual report for 1977 includes the following: utilization of the RB reactor; new regulations and instructions for reactor operation; improvement of experimental possibilities of the RB reactor; state of the reactor equipment; dosimetry and radiation protection; reactor staff. Five annexes are concerned with: testing the properties of preamplifiers for linear and logarithmic experimental channels; properties of the neutron converter; maintenance of the reactor equipment; purchase of new equipment; and the program for training reactor operators

76 FR 37852 - Advisory Committee on Reactor Safeguards; Notice of Meeting

Science.gov (United States)

2011-06-28

... Thursday, October 21, 2010 (74 FR 65038-65039). Wednesday, July 13, 2011, Conference Room T2-B1, 11545....: Safety Evaluation Report Associated with NEDC-33173, Supplement 2, Parts 1, 2, and 3, ``Analysis of Gamma... Electric Hitachi (GEH) regarding the safety evaluation report associated with NEDC-33173, Supplement 2...

Simulator for materials testing reactors

International Nuclear Information System (INIS)

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

2013-06-01

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

Multimedia on nuclear reactors physics

International Nuclear Information System (INIS)

Dies, Javier; Puig, Francesc

2010-01-01