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Sample records for bir reactor

  1. Reactor

    International Nuclear Information System (INIS)

    Toyama, Masahiro; Kasai, Shigeo.

    1978-01-01

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

  2. Reactor

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  3. Akselere Fazda Bir Chediak Higashi Sendromu

    OpenAIRE

    Vitrinel, Ayça; Albayrak, Aydoğan; Erer, Buket; Çorbacıoğlu, Doğan

    2014-01-01

    Tekrarlayan ateş atakları nedeniyle kliniğimize yatırılarak incelenen bir hastaya parsiyel okülokutanöz albinizm kemik iliğindeki noneritroid hücrelerdeki tipik devgranüller ve aile hikayesine dayanılarak akselere fazda Chediak Higashi sendromu tanısı kondu Hastalığın başlıca özellikleri ilgili literatür ışığında tartışıldı Anahtar kelimeler: Chediak Higashi Sendromu Akselere Faz Albinizm

  4. Reactor

    International Nuclear Information System (INIS)

    Fujibayashi, Toru.

    1976-01-01

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

  5. Reactor

    International Nuclear Information System (INIS)

    Evans, R.M.

    1976-01-01

    Disclosed is a neutronic reactor having a moderator, coolant tubes traversing the moderator from an inlet end to an outlet end, bodies of material fissionable by neutrons of thermal energy disposed within the coolant tubes, and means for circulating water through said coolant tubes characterized by the improved construction wherein the coolant tubes are constructed of aluminum having an outer diameter of 1.729 inches and a wall thickness of 0.059 inch, and the means for circulating a liquid coolant through the tubes includes a source of water at a pressure of approximately 350 pounds per square inch connected to the inlet end of the tubes, and said construction including a pressure reducing orifice disposed at the inlet ends of the tubes reducing the pressure of the water by approximately 150 pounds per square inch. 1 claim, 16 figures

  6. BIR 2014 - Bibliometric-enhanced Information Retrieval

    DEFF Research Database (Denmark)

    This first “Bibliometric-enhanced Information Retrieval” (BIR 2014) workshop1 aims to engage with the IR community about possible links to bibliometrics and scholarly communication. Bibliometric techniques are not yet widely used to enhance retrieval processes in digital libraries, although...... analysis of co-authorship network, can improve retrieval services for specific communities, as well as for large, cross-domain collections. This workshop aims to raise awareness of the missing link between information retrieval (IR) and bibliometrics / scientometrics and to create a common ground...... for the incorporation of bibliometric-enhanced services into retrieval at the digital library interface. Our interests include information retrieval, information seeking, science modelling, network analysis, and digital libraries. The goal is to apply insights from bibliometrics, scientometrics, and informetrics...

  7. An exegesis of IAPs: salvation and surprises from BIR motifs.

    Science.gov (United States)

    Miller, L K

    1999-08-01

    The BIR (baculovirus IAP repeat) motif is a conserved sequence of approximately 70 amino acids that was identified originally in the 'inhibitor of apoptosis' (IAP) family of proteins. BIR-containing proteins (BIRPs) are found in viruses, yeast and metazoans. Recent genetic analysis of a nematode BIRP demonstrated an essential role in cytokinesis instead of apoptosis. It is likely that BIRs originated in eukaryotes to serve a role in cytokinesis and/or mitotic spindle function during cell division and that, with gene duplication, the more recent adaptation of some BIRPs to the regulation of apoptosis was possible. IAPs interact with a variety of proteins, including members of the caspase protease family. This article discusses current research on the structure and function of the BIR motifs and how it could provide insight into the function of BIRPs in cell division.

  8. Tivoli peab läbirääkimisi Tallinnas

    Index Scriptorium Estoniae

    2004-01-01

    Taani firma Tivoli Internatinal soovib ehitada Tallinna vähemalt 6 ha paiknevat lõbustusparki. Kuna linna poolt pakutav Skoone bastion on vaid 2,5-hektarine, peetakse lisahektarite leidmiseks läbirääkimisi Eesti Energia, Eesti Raudtee ja Tallinna Soojusega

  9. Cornelia De Lange Sendromlu Bir Olguda Ektrodaktili: Olgu Sunumu

    OpenAIRE

    YILDIRIM, M. Selman

    2008-01-01

    Cornelia de Lange sendromu (CDL) karakteristik yüz özellikleri prenatal ve postnatal büyüme geriliği, mental retardasyon ile karakterizedir. Fasiyal özellikleri (synophrys, uzun kirpikler ve kaşlar ) muhtemel doğru tanıyı koymaya yardımcı olur. Kliniğimize getirilen bir aylık dismorfik yüz özellikleri olan CDL sendromlu bir kız çocuğu olgu olarak sunuldu. Klasik CDL sendromuna farklı olarak olguda sağ elde ektrodaktili, sol elde basit sindaktili vardı. Bu çalışmada CDL sendromunun klinik özel...

  10. Fibröz Displazi - Bir vak'a bildirisi -

    OpenAIRE

    Timoçin, Necla; Gümrü, Osman; Alatlı, Metin

    2013-01-01

    ÖZETÜst çenede oluşan, fossa canina ve tuber maxilla'yı içine alan sinus maxillaris'ini ortadan kaldıran bir fibröz displazi vak'ası sunuldu. SUMMARY A case of fibrous dysplasia in the maxilla that ruined maxillary sinus involving fossa canina and tuber maxilla is discussed. 

  11. Turkiye’de Vergi Gelirlerinin Oynakligina Dair Bir Analiz

    OpenAIRE

    Tuba Ozsevinc; Erdal Yilmaz

    2014-01-01

    [TR] Vergi gelirlerinin oynakliginin dusuk olmasi, butce planlarini kolaylastirici bir role sahiptir. Bu calismada, degisim katsayisi ve vergi geliri istikrar katsayisi kullanilarak, Turkiye’de vergi gelirlerinin istikrarli olup olmadigi ortaya koyulmaya calisilmistir. Bu nedenle, 2007-2013 yillarina ait vergi gelirleri ele alinmistir. Calismanin sonuclari, Turkiye’de goreli en istikrarli vergi gelirinin, dolaysiz vergilerin en onemli bileseni olan gelir ve kazanc uzerinden alinan vergiler ol...

  12. Kaybolmuş bir İçecek Kefir

    Directory of Open Access Journals (Sweden)

    Zekâi Varnacı

    2015-02-01

    Full Text Available Kafkasya’da bir parça dana veya koyun şirdeni keçi tulumlarında inek sütüyle maserasyona bırakılarak hazırlanır. Süt çabuk ve spontan olarak koagüle olur. Bundan sonra tulum yeniden doldurularak yeni bir işleme geçilir. Birkaç hafta sonra tulumun iç cidarlarında yavaş yavaş süngerimsi bir kabuk tabakası oluşur. İşte bu kabuk tabakası bölünüp veya kasılıp, sonra kurutularak kefir daneleri meydana getirilir. Danelerin görünüşü sarımsı, küçük, tomurcuğumsudur. Bu daneler kefirin hazırlanmasında maya olarak kullanılmak üzere ticarete arzedilir.

  13. Geochemical regionalism of biržai area topsoil and technogenous ground

    OpenAIRE

    Stankevičius, Tadas

    2008-01-01

    Objectives: to perform Biržai region soil geochemical regionalism in accordance with geological-geophormalogical evidence, to establish geochemical field differences, evaluate resistance to polution technogenous chemical elements. Goals: 1. Summarize experience gained in previously accomplished geochemical regionalism in Lithuania. 2. Familiarize with geochemical mapping of Biržai region . 3. To explore geological (quaternary), geomorphologic and anthropocentric pollution conditions in Biržai...

  14. Ekspress testis euroläbirääkijaid / Sulev Vedler

    Index Scriptorium Estoniae

    Vedler, Sulev, 1970-

    2001-01-01

    Tallinnas pidasid nõu kuue riigi pealäbirääkijad kõnelustel Euroopa Liiduga. Tabel: Ungari, Poola, Sloveenia, Küprose, Eesti ja Tšehhi pealäbirääkijate küsitluseelistuste kohta. Vt. samas intervjuu Alar Streimanniga

  15. SlBIR3 Negatively Regulates PAMP Responses and Cell Death in Tomato

    Directory of Open Access Journals (Sweden)

    Shuhua Huang

    2017-09-01

    Full Text Available Bri1-associated kinase 1 (BAK1-interacting receptor-like kinase (BIR proteins have been shown to play important roles in regulating growth and development, pathogen associated molecular pattern (PAMP-triggered immunity (PTI responses, and cell death in the model plant, Arabidopsis thaliana. We identified four BIR family members in tomato (Solanum lycopersicum, including SlBIR3, an ortholog of AtBIR3 from A. thaliana. SlBIR3 is predicted to encode a membrane localized non-arginine-aspartate (non-RD kinase that, based on protein sequence, does not have autophosphorylation activity but that can be phosphorylated in vivo. We established that SlBIR3 interacts with SlBAK1 and AtBAK1 using yeast two-hybrid assays and co-immunoprecipitation and maltose-binding protein pull down assays. We observed that SlBIR3 overexpression in tomato (cv. micro-tom and A. thaliana has weak effect on growth and development through brassinosteroid (BR signaling. SlBIR3 overexpression in A. thaliana suppressed flg22-induced defense responses, but did not affect infection with the bacterial pathogen Pseudomonas syringae (PstDC3000. This result was confirmed using virus-induced gene silencing (VIGS in tomato in conjunction with PstDC3000 infection. Overexpression of SlBIR3 in tomato (cv. micro-tom and A. thaliana resulted in enhanced susceptibility to the necrotrophic fungus Botrytis cinerea. In addition, co-silencing SlBIR3 with SlSERK3A or SlSERK3B using VIGS and the tobacco rattle virus (TRV-RNA2 vector containing fragments of both the SlSERK3 and SlBIR3 genes induced spontaneous cell death, indicating a cooperation between the two proteins in this process. In conclusion, our study revealed that SlBIR3 is the ortholog of AtBIR3 and that it participates in BR, PTI, and cell death signaling pathways.

  16. Altered Regulation of Escherichia coli Biotin Biosynthesis in BirA Superrepressor Mutant Strains

    Science.gov (United States)

    Chakravartty, Vandana

    2012-01-01

    Transcription of the Escherichia coli biotin (bio) operon is directly regulated by the biotin protein ligase BirA, the enzyme that covalently attaches biotin to its cognate acceptor proteins. Binding of BirA to the bio operator requires dimerization of the protein, which is triggered by BirA-catalyzed synthesis of biotinoyl-adenylate (biotinoyl-5′-AMP), the obligatory intermediate of the ligation reaction. Although several aspects of this regulatory system are well understood, no BirA superrepressor mutant strains had been isolated. Such superrepressor BirA proteins would repress the biotin operon transcription in vivo at biotin concentrations well below those needed for repression by wild-type BirA. We isolated mutant strains having this phenotype by a combined selection-screening approach and resolved multiple mutations to give several birA superrepressor alleles, each having a single mutation, all of which showed repression dominant over that of the wild-type allele. All of these mutant strains repressed bio operon transcription in vivo at biotin concentrations that gave derepression of the wild-type strain and retained sufficient ligation activity for growth when overexpressed. All of the strains except that encoding G154D BirA showed derepression of bio operon transcription upon overproduction of a biotin-accepting protein. In BirA, G154D was a lethal mutation in single copy, and the purified protein was unable to transfer biotin from enzyme-bound biotinoyl-adenylate either to the natural acceptor protein or to a biotin-accepting peptide sequence. Consistent with the transcriptional repression data, each of the purified mutant proteins showed increased affinity for the biotin operator DNA in electrophoretic mobility shift assays. Surprisingly, although most of the mutations were located in the catalytic domain, all of those tested, except G154D BirA, had normal ligase activity. Most of the mutations that gave superrepressor phenotypes altered residues

  17. Gıda Kaynaklı Bir Patojen: Arcobacter

    Directory of Open Access Journals (Sweden)

    Reyhan İrkin

    2015-02-01

    Full Text Available Camplylobacteraceae familyasına ait Gram negatif, zoonotik ve oksijene dirençli bir mikroorganizma olan Arcobacter 15 ºC’de gelişmesi, 42 ºC’de gelişmemesi, aerobik ortamda optimum olarak 30 °C’de gelişme göstermesi, %27-30 mol G+C içeriği ve önemli izoprenoid kinonlardan olan menakinon-6 içermemesi ile Campylobacter’den ayrılmaktadır. Arcobacter’in, A. butzleri, A. cryaerophilus, A. skirrowii, A. cibarus, A. sulfidicus gibi türleri bulunmaktadır. Arcobacter türlerinin son yıllarda İtalya, Kanada, Brezilya gibi bazı ülkelerde gıda zehirlenmelerine yol açtığı gözlenmiştir. Özellikle kirli su, kümes hayvanları, karkas, et ürünleri ve çiğ sütler aracılığıyla enfeksiyonlara neden olduğu bildirilmiştir. İnsana bulaşma yolları ve toksin mekanizmasıyla ilgili bilgiler oldukça sınırlı ve yetersizdir. Belirli bir ölçüde antibiyotiklere de direnç gösterdiği bilinmektedir. Bu çalışmada Arcobacter türlerinin hayvan ve insanlardaki potansiyel patojenitesi, bulaşma koşulları, yol açtığı sorunlar ve alınabilecek tedbirlere değinilmiştir.

  18. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

    This pamphlet describes how reactors work; discusses reactor design; describes research, teaching, and materials testing reactors; production reactors; reactors for electric power generation; reactors for supply heat; reactors for propulsion; reactors for space; reactor safety; and reactors of tomorrow. The appendix discusses characteristics of U.S. civilian power reactor concepts and lists some of the U.S. reactor power projects, with location, type, capacity, owner, and startup date.

  19. Tıpta işbirliği ve hukuksal sorunlar

    OpenAIRE

    Rosenau, Henning

    2010-01-01

    Tıpta işbirliği ve hukuksal sorunlar : tarih: 16-17 nisan 2010, Kurupelit Yerleskesi, Samsun = Delegation und Kooperation im Gesundheitswesen / ed.: Henning Rosenau ... - Samsun : Adalet, 2010. - XII, 331 S.

  20. Prokaryotic BirA ligase biotinylates K4, K9, K18 and K23 in histone H3.

    Science.gov (United States)

    Kobza, Keyna; Sarath, Gautam; Zempleni, Janos

    2008-04-30

    BirA ligase is a prokaryotic ortholog of holocarboxylase synthetase (HCS) that can biotinylate proteins. This study tested the hypothesis that BirA ligase catalyzes the biotinylation of eukaryotic histones. If so, this would mean that recombinant BirA ligase is a useful surrogate for HCS in studies of histone biotinylation. The biological activity of recombinant BirA ligase was confirmed by enzymatic biotinylation of p67. In particular, it was found that BirA ligase biotinylated both calf thymus histone H1 and human bulk histone extracts. Incubation of recombinant BirA ligase with H3-based synthetic peptides showed that lysines 4, 9, 18, and 23 in histone H3 are the targets for the biotinylation by BirA ligase. Modification of the peptides (e.g., serine phosphorylation) affected the subsequent biotinylation by BirA ligase, suggesting crosstalk between modifications. In conclusion, this study suggests that prokaryotic BirA ligase is a promiscuous enzyme and biotinylates eukaryotic histones. Moreover the biotinylation of histones by BirA ligase is consistent with the proposed role of human HCS in chromatin.

  1. Bir Jelleşme Maddesi Olarak Pektin

    Directory of Open Access Journals (Sweden)

    Ö. Utku Çopur

    2015-02-01

    Full Text Available Pektin, jel oluşturma özelliğinden yararlanılan ve en önemli kullanım alanı gıdalar olan bir katkı maddesidir. Bu nedenle pektin reçel marmelat, jele gibi mamullerin üretiminde kullanılır. Yüksek bitkilerin hücreleri arasında yada hücre duvarlarında yer alan pektin, bitki dokularının çoğunda ve tam olgunlaşmamış meyvelerde suda çözünmeyen “protopektin” şeklinde bulunur. Meyve olgunlaştıkça protopektin suda çözünür forma dönüşür. Bu değişim, olgunlaşma ile oluşan dokusal değişmenin, olgunlaşma ile oluşan dokusal değişmenin kaynağıdır. Yüksek molekül ağırlığına sahip doğal pektinlerin (protopektinler suda çözünmezliği muhtemelen, pektik maddeler arasındaki birincil ve ikincil bağlara, hücre çeperlerindeki diğer maddelere, çok değerli katyonların ve karboksil grubu içeren çözünmeyen tuzların oluşmasına ve büyük moleküllerin hücre çeperlerindeki diğer maddelerce sarılmasına bağlıdır.

  2. Oral condition and mouth disease assessment of risk factors of Birštonas students

    OpenAIRE

    Janulionytė, Neringa

    2013-01-01

    Aim of the study: Investigate and evaluate Birštonas gymnasium 8-12 year old pupils oral health and hygiene; researched parents attitude towards children's oral health. Objectives: To evaluate 8-12 year-old children caries prevalence and severity, oral hygiene status and assess parents' views on oral hygiene; to evaluate 8-12 year old children's eating habits. Material and methods: The study was conducted from January 2012 to the end of February in Birštonas city high school. In total i...

  3. Nuclear reactors

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2015-10-01

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

  4. birääkijate viis lemmikviga / Max H. Bazerman, Don A Moore

    Index Scriptorium Estoniae

    Bazerman, Max H.

    2008-01-01

    Harvardi Ärikooli professorid annavad nõu, mida teha siis, kui jäädakse läbirääkimistel liigselt pidama esimese pakkumise külge, ollakse jäärapäine, minnakse liiale enesekindlusega või keskendutakse liiga kitsale eesmärgile

  5. Disease-causing mutations in the XIAP BIR2 domain impair NOD2-dependent immune signalling

    DEFF Research Database (Denmark)

    Damgaard, Rune Busk; Fiil, Berthe Katrine; Speckmann, Carsten

    2013-01-01

    that the RIPK2 binding site in XIAP overlaps with the BIR2 IBM-binding pocket and find that a bivalent Smac mimetic compound (SMC) potently antagonises XIAP function downstream of NOD2 to limit signalling. These findings suggest that impaired immune signalling in response to NOD1/2 stimulation is a general...

  6. Põhja-Korea lahkus tuumaläbirääkimistelt / Jüri Piirisild

    Index Scriptorium Estoniae

    Piirisild, Jüri

    2005-01-01

    Põhja-Korea teatas tuumaprogrammi alaste läbirääkimiste tähtajatust katkestamisest. Analüütikute arvates peaks USA pehmendama oma jäika hoiakut Põhja-Korea suhtes ning püüdma senisest aktiivsemalt leida kriisile lahendust

  7. "İman da Hikmet de Yemendedir "Hadisine Dair Bir İnceleme

    Directory of Open Access Journals (Sweden)

    Kadir Demirci

    2015-11-01

    Full Text Available Pek çok hadis kitabında Hz. Peygamber’in söyle söylediği nakledilmistir: “İman da Hikmet de Yemen’dedir.” Hadisin zahirinde ifade edildiği gibi iman ve hikmet gerçekten belli bir coğrafyaya mı aittir. Eğer öyle ise bu durum hadisin anlamı ve güvenilirliği hakkında bir süphe uyandırmaktadır. Hadis alimlerinin ha- dis hakkındaki farklı görüsleri de bir problem olarak karsımızda durmaktadır. Bu çalısmada hadisin hem rivayet edilisi hem de anlamı ile ilgili konular ele alınmıs, bu çerçevede hadis bir değerlendirmeye tabi tutulmustur .

  8. Kas sugu on läbirääkimistel tähtis

    Index Scriptorium Estoniae

    2006-01-01

    Ülevaade Harvard Business Schooli uudiskirja Working Knowledge 2006. aasta veebruari numbris ilmunud Dina W. Pradel'i, Hannah Riley Bowles'i ja Kathleen L. McGinn'i artiklist inimese soo mõjust läbirääkimistele

  9. Disiplinlerarası Bir İçerik Olarak Mimarlık

    Directory of Open Access Journals (Sweden)

    Gamze ŞENSOY

    2015-03-01

    Full Text Available ÖZETMimarlık, insan eylemlerini karşılamaya ve bu eylemleri sürdürebilmeye yönelik bir ihtiyaç olarak ortaya çıkan bina ve yapıların tasarlanması işidir. Tasarlamak; yeni ürünlerin ortaya konulma süreci olan, yaratıcılık ve bilgi birikiminin büyük rol oynadığı bir ifade yöntemidir. Tasarım ise, ortaya çıkan özgün ürünlerdir. Tasarım ve mimarlık sürekli bir ilişki içinde olan ve dönüşümlü olarak birbirini etkileyen iki olgudur. Tasarım kavramının yanısıra, mimarlığın ilişki içerisinde bulunduğu birçok disiplin de mevcuttur. Bu, mimarlığın disiplinlerarası bir kavram olduğunun göstergesidir. Bu disiplinler, mimarlığı doğrudan ya da dolaylı olarak etkileyerek mimarlık olgusunun sürdürülebilirliğini sağlar.Bu çalışma, mimarlığın ve diğer disiplinlerin birbirleri ile olan ilişkilerini irdelemekte olup, bu disiplinlerin mimarlık kavramına göre olan konumlarını şematik olarak ortaya koymayı amaçlamaktadır.Anahtar Kelimeler: Mimarlık, Tasarım, Disiplin

  10. Epistemolojik Bir Dirilişe Doğru, Kalbin Anlaması

    Directory of Open Access Journals (Sweden)

    Mevlüt Uyanık

    2015-11-01

    Full Text Available Farklı zaman ve mekanlarda değişik sosyo-politik sorunlara çözümler üreterek tutarlılığını ve geçerliliğini, dolayısıyla da kendi müntesipleri bazında da olsa evrenselliklerini sistematize edebilmek için her sistem öncelikle bir bilgi tasavvuru geliştirmeli ve kendi modelini bunun üzerine temellendirmelidir. Makale bilgi edinme sürecinde akıl ve kalp yetileri üzerinde durmaktadır.  Makale , "Bilginin İslamileştirilmesi" adlı çalışmamızın bir tamamlayıcısı niteliğindedir. Burada  çağdaş bir İslami bilgi teorisi/tasavvuru oluşturmada akıl ve teakkulun bir üst boyutu olan "kalp ile tefekkür" ya da "kalbin anlaması"  müstakil bir metin haline getirilmiştir. Böylece klasik usul kitaplarında bilginin vasıtası olarak zikredilen beş duyu ve aklın ötesinde ama onların ürettiği bilgiyi de işleyen kalbin işlevselliği ortaya çıkacaktır.

  11. H Reactor

    Data.gov (United States)

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

  12. Pengaruh Lama Perendaman dan Jenis Minuman Beralkohol Bir dan Tuak terhadap Kekerasan Email Gigi Manusia (In Vitro)

    OpenAIRE

    Magista, Malida; Nuryanti, Archadian; Wahyudi, Ivan Arie

    2014-01-01

    Erosi gigi merupakan hilangnya lapisan email gigi karena asam. Jenis asam, pH rendah, serta kandungan kalsium, fosfat, dan fluoride pada bir dan tuak diduga merupakan faktor kimiawi penyebab erosi gigi. Tujuan penelitian ini untuk mengetahui pengaruh lama perendaman dan jenis minuman beralkohol bir dan tuak terhadap kekerasan email gigi manusia (in vitro). Penelitian ini menggunakan 14 sampel gigi premolar pertama atas. Setiap gigi dibagi menjadi 2 bagian, bukal dan palatal. kemudian dibagi m...

  13. Pengaruh Lama Perendaman Dan Jenis Minuman Beralkohol Bir Dan Tuak Terhadap Kekerasan Email Gigi Manusia (in Vitro)

    OpenAIRE

    Magista, Malida; Nuryanti, Archadian; Wahyudi, Ivan Arie

    2014-01-01

    Erosi gigi merupakan hilangnya lapisan email gigi karena asam. Jenis asam, pH rendah, serta kandungan kalsium, fosfat, dan fluoride pada bir dan tuak diduga merupakan faktor kimiawi penyebab erosi gigi. Tujuan penelitian ini untuk mengetahui pengaruh lama perendaman dan jenis minuman beralkohol bir dan tuak terhadap kekerasan email gigi manusia (in vitro). Penelitian ini menggunakan 14 sampel gigi premolar pertama atas. Setiap gigi dibagi menjadi 2 bagian, bukal dan palatal. kemudian dibagi m...

  14. A Functional Link Between Bir1 and the Saccharomyces cerevisiae Ctf19 Kinetochore Complex Revealed Through Quantitative Fitness Analysis.

    Science.gov (United States)

    Makrantoni, Vasso; Ciesiolka, Adam; Lawless, Conor; Fernius, Josefin; Marston, Adele; Lydall, David; Stark, Michael J R

    2017-09-07

    The chromosomal passenger complex (CPC) is a key regulator of eukaryotic cell division, consisting of the protein kinase Aurora B/Ipl1 in association with its activator (INCENP/Sli15) and two additional proteins (Survivin/Bir1 and Borealin/Nbl1). Here, we report a genome-wide genetic interaction screen in Saccharomyces cerevisiae using the bir1-17 mutant, identifying through quantitative fitness analysis deletion mutations that act as enhancers and suppressors. Gene knockouts affecting the Ctf19 kinetochore complex were identified as the strongest enhancers of bir1-17 , while mutations affecting the large ribosomal subunit or the mRNA nonsense-mediated decay pathway caused strong phenotypic suppression. Thus, cells lacking a functional Ctf19 complex become highly dependent on Bir1 function and vice versa. The negative genetic interaction profiles of bir1-17 and the cohesin mutant mcd1-1 showed considerable overlap, underlining the strong functional connection between sister chromatid cohesion and chromosome biorientation. Loss of some Ctf19 components, such as Iml3 or Chl4, impacted differentially on bir1-17 compared with mutations affecting other CPC components: despite the synthetic lethality shown by either iml3 ∆ or chl4 ∆ in combination with bir1-17 , neither gene knockout showed any genetic interaction with either ipl1-321 or sli15-3 Our data therefore imply a specific functional connection between the Ctf19 complex and Bir1 that is not shared with Ipl1. Copyright © 2017 Makrantoni et al.

  15. Dişi Bir Köpekte Görülen Jinekolojik Patolojiler Kompleksi

    OpenAIRE

    GÜNAY, Zeynep; UÇMAK, Melih; YILDIRIM, Funda; SABUNCU, Ahmet; TEK, Çağatay; ÇALIŞKAN, Esra

    2018-01-01

    ÖZET10 yaşında, kısırlaştırılmamış, hiç doğum yapmamış, 7 kg ağırlığında, melez dişi bir köpek, vaginal kitle, meme loblarında değişen büyüklükte tümöral oluşumlar ve iştahsızlık nedenleriyle kliniğimize getirildi. Yapılan ultrasonografik muayene sonucunda pyometra ve her iki ovaryumda kistik oluşumlar gözlendi. Tek bir genel anestezi altında cerrahi yaklaşım olarak ovariohisterektomi, bilateral mastektomi ve vaginal kitlenin ekstirpasyonu uygulandı. Patolojik inceleme sonucunda her iki ovary...

  16. Duchenne Musküler Distrofili Bir Olguda Anestezi Yönetimi

    OpenAIRE

    KARAHAN, N.; AKSUN, M.; KOROĞLU, L.; GİRGİN, S.; ARAN, G.; AKHAN, G.; GÜRBÜZ, A.

    2014-01-01

    Duchenne Musküler Distrofi (DMD); X’e bağlı resesif olarak geçiş gösteren ilerleyici kas zayıflığı ve kas kontraktürleri ile karakterize kalıtımsal bir hastalıktır. En sık çocukluk yaşlarında ve 3.500 erkek doğumda 1 görülmektedir. Bu hastalarda anestezi yönetimi özellik göstermektedir. Çünkü inhalasyon anestezikleri ve süksinilkolin gibi ajanlar, hipermetabolik bir klinik tablo ile seyreden malign hipertermi gibi ölümcül komplikasyonlara yol açabilir. Biz ventriküler septal defekt (VSD) nede...

  17. Dialoogsüsteem ja läbirääkimiste struktuur

    Directory of Open Access Journals (Sweden)

    Mare Koit

    2017-05-01

    Full Text Available "Dialogue systems and the structure of negotiation" We are studying the negotiations in the Estonian dialogue corpus, with the aim of identifying the typical dialogue acts and communicative strategies used in the dialogues. Three sub-corpora have been analysed: 1 conversations between a travel agent and a customer who is planning a trip; 2 telemarketing calls where a sales clerk for an educational company argues that a customer should take a training course, and 3 everyday conversations where the initiator attempts to persuade the communication partner to perform an action. The structure of the different types of dialogues is represented as a sequence of dialogue acts and communicative strategies. The general structure of human-human negotiation is identified and described. This structure is compared with the structure of the negotiations carried out by an experimental dialogue system. The results can help to develop the dialogue system in order to make conversations with the system more human-like. Artiklis uuritakse eesti dialoogikorpuses leiduvaid inimestevahelisi läbirääkimisi, et välja selgitada sellistes dialoogides tüüpiliselt kasutatavad dialoogiaktid ja suhtlusstrateegiad. Analüüsitakse kolme alamkorpust: 1 dialooge reisibüroo agendi ja kliendi vahel, 2 müügiläbirääkimisi, kus koolitusfirma ametnik pakub võimalikule kliendile firma kursusi, ning 3 argivestlusi, kus kaks omavahel tuttavat osalejat püüavad saavutada kokkulepet teatava tegevuse tegemise suhtes. Erinevat tüüpi dialoogide struktuur esitatakse nii dialoogiaktide kui ka suhtlusstrateegiate järjendina ning nende andmete põhjal leitakse ka läbirääkimiste üldine struktuur. Seda struktuuri võrreldakse olemasoleva eksperimentaalse dialoogsüsteemiga peetavate läbirääkimiste struktuuriga. Tulemused võimaldavad dialoogsüsteemi edasi arendada, et muuta sellega suhtlemist inimlähedasemaks.

  18. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

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

  19. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

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

  20. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

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

  1. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    1962-01-01

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

  2. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

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

  3. Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Martens, Frederick H. [Argonne National Laboratory; Jacobson, Norman H.

    1968-09-01

    This booklet discusses research reactors - reactors designed to provide a source of neutrons and/or gamma radiation for research, or to aid in the investigation of the effects of radiation on any type of material.

  4. Nuclear reactors

    International Nuclear Information System (INIS)

    Middleton, J.E.

    1977-01-01

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

  5. Yerel Dokusunu Yitirmekte Olan Bir Kent: Malatya A City Losing Its Local Texture: Malatya

    Directory of Open Access Journals (Sweden)

    Zaliha İnci KARABACAK

    2013-07-01

    Full Text Available Turkey is a country that was built on Anatolia’s rich heritage in respect to historical, social, cultural and economical. This study approaches the changing face of Malatya which is one of the new big cities of Turkey. Change is one of the realities that can not be ignored. In social life, cities have emerged as spaces which are exposed to changes. Cities are being transformed for various reasons such as population growth, modern urbanization policies, economic interests. In some cases, the change is damaging the essence of the city. Today, the change shows its effect in this aspect on many cities. This situation causes many cities to lose the local texture of its’. Malatya distinguishes itself as an city with some characteristics of economic, geographic, social and cultural. But a significant portion of these distinctive values are being succumbed in the face of change. In this context in the study it’s elaborated on fall of; especially greenbelt which -Malatya’s the worldwide economic value-apricotes are grown on and Malatya’s traditional houses because of construction of boulevard, junction, multiplex housing to create a modern city. The values which are being lost in Malatya are expressed visually by nearby dated photos. In this study similar changes, which are often internalized by most of us in everyday city life, are bringing forward once again with the example of Malatya. So, it’s tried to wake up the consciousness of being more sensitive to these changes as an individual and a citizen. Bu çalışmada; tarihi, sosyal, kültürel ve ekonomik bakımdan zengin bir mirasa ev sahipliği yapan Anadolu topraklarında kurulu Türkiye’nin yeni büyükşehirlerinden biri olan Malatya’nın bir süredir değişen çehresi ele alınmaktadır. Değişim, yaşamın gözardı edilemeyecek gerçeklerinden biridir. Toplumsal yaşamda kentler değişime maruz kalan mekanlar olarak karşımıza çıkmaktadırlar. Kentler; nüfus art

  6. Reactor Neutrinos

    OpenAIRE

    Kim, Soo-Bong; Lasserre, Thierry; Wang, Yifang

    2013-01-01

    We review the status and the results of reactor neutrino experiments. Short-baseline experiments have provided the measurement of the reactor neutrino spectrum, and their interest has been recently revived by the discovery of the reactor antineutrino anomaly, a discrepancy between the reactor neutrino flux state of the art prediction and the measurements at baselines shorter than one kilometer. Middle and long-baseline oscillation experiments at Daya Bay, Double Chooz, and RENO provided very ...

  7. BOILING REACTORS

    Science.gov (United States)

    Untermyer, S.

    1962-04-10

    A boiling reactor having a reactivity which is reduced by an increase in the volume of vaporized coolant therein is described. In this system unvaporized liquid coolant is extracted from the reactor, heat is extracted therefrom, and it is returned to the reactor as sub-cooled liquid coolant. This reduces a portion of the coolant which includes vaporized coolant within the core assembly thereby enhancing the power output of the assembly and rendering the reactor substantially self-regulating. (AEC)

  8. Reactor vessel

    NARCIS (Netherlands)

    Makkee, M.; Kapteijn, F.; Moulijn, J.A.

    1999-01-01

    A reactor vessel (1) comprises a reactor body (2) through which channels (3) are provided whose surface comprises longitudinal inwardly directed parts (4) and is provided with a catalyst (6), as well as buffer bodies (8, 12) connected to the channels (3) on both sides of the reactor body (2) and

  9. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

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

  10. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Ronen, Y.; Elias, E.

    1994-01-01

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

  11. Research reactors

    International Nuclear Information System (INIS)

    Merchie, Francois

    2015-10-01

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

  12. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Nagatomi, Shozo.

    1976-01-01

    Object: To provide a jet and missile protective wall of a configuration being inflated toward the center of a reactor container on the inside of a body of the reactor container disposed within a biological shield wall to thereby increase safety of the reactor container. Structure: A jet and missile protective wall comprised of curved surfaces internally formed with a plurality of arch inflations filled with concrete between inner and outer iron plates and shape steel beam is provided between a reactor container surrounded by a biological shield wall and a thermal shield wall surrounding the reactor pressure vessel, and an adiabatic heat insulating material is filled in space therebetween. (Yoshino, Y.)

  13. Paleohydrology and paleoenvironments at Bir Sahara: Pleistocene lithostratigraphy and sedimentology in the southern Egyptian Sahara

    Science.gov (United States)

    Hill, Christopher L.; Schild, Romuald

    2017-12-01

    The Bir Sahara area contains a remarkable record of Middle and Late Pleistocene hydrologic and environmental conditions for Saharan North Africa, based on lithostratigraphic and sedimentologic evidence from basin-fill deposits. Some of the deposits contain Lower Paleolithic (Acheulean) or Middle Paleolithic artifacts that help to constrain their age, since Acheulian artifacts are assigned to the Middle Pleistocene, while Middle Paleolithic artifacts are limited to either the Middle or Late Pleistocene. Locality BS-14 is in the southern part of Bir Sahara, while localities E-88-15, E-88-2, BS-13, and BS-16 are situated in the south-central part of the deflational basin, closer to the present-day water-hole. Lowered groundwater conditions during arid intervals resulted in erosional topographic basins. These deflational basins were later filled with sediments associated with wetter hydrologic conditions. The oldest studied sedimentary sequence in the Bir Sahara depression (BS-14) contains in situ Acheulian artifacts. Acheulian handaxes are found in sands underlying carbonates that are interpreted as evidence of spring-fed pond and marsh environments during a Middle Pleistocene wet interval. At the E-88-15 locality, the stratigraphic sequence documents deposition in a possible perennial pond or small lake that varied in extent and depth and is associated with Middle Paleolithic artifacts. At E-88-12 and BS-13, lateral and vertical variations in the lithofacies of the basin-fill sediments provide additional records of changing hydrologic conditions during the Late Pleistocene. These hydrologic conditions appear to reflect variations in water-table levels related to groundwater recharge and, at times, local rains.

  14. Research reactors

    International Nuclear Information System (INIS)

    Kowarski, L.

    1955-01-01

    It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

  15. Site-specific, covalent immobilization of BirA by microbial transglutaminase: A reusable biocatalyst for in vitro biotinylation.

    Science.gov (United States)

    Yu, Chang-Mei; Zhou, Hui; Zhang, Wei-Fen; Yang, Hong-Ming; Tang, Jin-Bao

    2016-10-15

    A facile approach for the production of a reusable immobilized recombinant Escherichia coli biotin ligase (BirA) onto amine-modified magnetic microspheres (MMS) via covalent cross-linking catalyzed using microbial transglutaminase (MTG) was proposed in this study. The site-specifically immobilized BirA exhibited approximately 95% of enzymatic activity of the free BirA, and without a significant loss in intrinsic activity after 10 rounds of recycling (P > 0.05). In addition, the immobilized BirA can be easily recovered from the solution via a simple magnetic separation. Thus, the immobilized BirA may be of general use for in vitro biotinylation in an efficient and economical manner. Copyright © 2016 Elsevier Inc. All rights reserved.

  16. Fermente bir Soya Ürünü “Miso”

    Directory of Open Access Journals (Sweden)

    Kamuran Ayhan

    2015-02-01

    Full Text Available Miso, Uzakdoğu’da üretilen ve insanlarca fazla miktarda tüketilen fermente bir soya ürünüdür. Miso üretiminde hammadde olarak soya fasulyesi, pirinç veya arpa, tuz ve mikroorganizma kültürü (Aspergillus oryzae kullanılmaktadır. Miso’nun rengi koyu kahverenginden açık sarıya kadar değişim göstermektedir. Fermentasyon sırasında soya fasulyesinde bulunan protein, karbonhidrat ve yağlar daha basit bileşim unsurlarına parçalanmaktadır. Miso, %12.5-19.0 protein, %1.4-6.9 yağ, %5.5-13 oranında tuz içermekte, lezzet verici bir gıda maddesi özelliği taşımaktadır. Miso özellikle esansiyel amino asitlerce zengindir. Protein kalitesini belirleyen NPU (Net protein kullanımı değeri misoda %72’dir. Protein kalitesi açısından bilinen protein kaynaklı gıdalar içinde ilk sırayı almaktadır.

  17. Geliştirilmiş Bir Yerli Dokuma Desen Tasarım Programı

    OpenAIRE

    ALA, Deniz Mutlu; ÇELİK, Nihat

    2015-01-01

    Bu çalışmada dokuma desenleri ve üretim planlamasına yönelik çalışmalar için kullanılabilecek birCAD-CAM programı, Dokuma Desen Tasarım Programı, DELPHI XE5 sürümü kullanılarak geliştirilmiştir.Program sayesinde desen tasarımıyla birlikte tahar ve armür planları manuel veya otomatik olaraküretilmektedir. Program menüsünde desen tasarımı ve geliştirmesine imkan veren araçlar kullanılmıştır.Geliştirilmiş olan yerli dokuma desen tasarım programı, yerli bir numune dokuma makinasının ağızlık açmam...

  18. İran Halk Kütüphaneleri: Niceliksel Bir Değerlendirme

    Directory of Open Access Journals (Sweden)

    Jahangir Gholipour

    2013-06-01

    Full Text Available Halk kütüphaneleri dijital uçurumun azaltılmasında önemli roller üstlenen toplumsal kuruluşlardır. On­ların, bu rollerini gerçekleştirebilmeleri için niceliksel açıdan yeterli durumda olmaları gerekmektedir. Ayrıca, halk kütüphanelerine ilişkin niceliksel göstergeler niteliklerini ve nitelikli hizmet vermelerini doğrudan belirler. İran, 30 ilde yaşayan 71 milyon nüfusa sahip bir Ortadoğu ülkesidir. Bu çalışmada, İran’daki halk kütüphanelerine ilişkin niceliksel durum kütüphane sayısı, kullanıcı, derme ve personel unsurları açısından ortaya konulmaya çalışılmıştır. Elde edilen sonuçlara göre, İran’da ele alınan söz konusu unsurlar açısından genelde bir yetersizlik olduğu anlaşılmıştır. Çalışma sonunda bazı önerilerde bulunulmuştur.

  19. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

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

  20. Heterogeneous reactors

    International Nuclear Information System (INIS)

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

    1979-08-01

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

  1. Bussijuhtide ja Go Busi läbirääkimised jätkuvad / Jano Purga

    Index Scriptorium Estoniae

    Purga, Jano

    2007-01-01

    Maakonnaliinide turuvalitseja Go Bus katkestab lepingud Hiiumaal, Valgamaal ja Saaremaal, kuid jätkab läbirääkimisi bussijuhtide ametiühinguga palgatõusu üle, samas teeb ametiühing ettevalmistusi streigiks, mis algab 11. detsembril

  2. Successful Conversion of the Bacillus subtilis BirA Group II Biotin Protein Ligase into a Group I Ligase

    Science.gov (United States)

    Henke, Sarah K.; Cronan, John E.

    2014-01-01

    Group II biotin protein ligases (BPLs) are characterized by the presence of an N-terminal DNA binding domain that allows transcriptional regulation of biotin biosynthetic and transport genes whereas Group I BPLs lack this N-terminal domain. The Bacillus subtilis BPL, BirA, is classified as a Group II BPL based on sequence predictions of an N-terminal helix-turn-helix motif and mutational alteration of its regulatory properties. We report evidence that B. subtilis BirA is a Group II BPL that regulates transcription at three genomic sites: bioWAFDBI, yuiG and yhfUTS. Moreover, unlike the paradigm Group II BPL, E. coli BirA, the N-terminal DNA binding domain can be deleted from Bacillus subtilis BirA without adverse effects on its ligase function. This is the first example of successful conversion of a Group II BPL to a Group I BPL with retention of full ligase activity. PMID:24816803

  3. Nuclear reactor

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  4. Nuclear reactor

    International Nuclear Information System (INIS)

    Tilliette, Z.

    1975-01-01

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

  5. Dünya Denizcilik Eğitim Faaliyetleriyle İlgili Genel Bir Kıyaslama

    Directory of Open Access Journals (Sweden)

    Feramuz AŞKIN

    2015-12-01

    Full Text Available Deniz taşımacılığındaki artan profesyonelleşme gereksinimleri bu alanda hizmet veren personel ve mürettebatın aynı düzeyde eğitim alması ile cevap bulacaktır. Bu da eğitim veren kurum ve üniversitelerin belirli bir standartta eğitim vermesi ile mümkün olacaktır. Burada üzerinde durulması gereken konu eğitim veren kurumların eğitim düzeylerinin alt ve üst noktası arasındaki farkın mümkün mertebede birbirine yakın olması ile belirli bir kalite düzeyinde tutulabilecek olmasıdır. Bunun için eğitim veren kurumların uyması gereken başta STCW Manila kararları gibi uluslararası standartlar olmak üzere, iç mevzuatlar, çeşitli idarelerin önerileri ve kararları, EMSA gibi denetleyici birimlerin üzerinde durmuş olduğu çeşitli standartlar bir dayanak noktası oluşturacaktır. Bu çalışmada yazarlar, farklı düzeylerde eğitim veren örnek eğitim sistemlerinin karşılaştırılması yolu ile bu standartların uygulanması hususunu göz önüne sermeyi hedeflemektedir. Böylece bu bildirinin yazım amacı olan ve standartlarla genel kaideleri belirlenmiş daha kaliteli ve profesyonel eğitim sistemine geçişe katkıda bulunulabilecektir.

  6. Hepatit A Enfeksiyonu Sonrası Gelişen Bir Guillian-Barre Sendromu Olgusu+

    OpenAIRE

    Özışık, Handan Işın; Kızkın, Sibel; Çalışkan, Özden; Özcan, Cemal

    2015-01-01

    Guillian-Barre Sendromu ile enfeksiyon hastalıkları arasındaki ilişki iyi bilinmektedir. Hepatit A enfeksiyonu sırasında GBS gelişimi ender görülen bir tablodur. Hepatit A enfeksiyonuna bağlı olarak gelişen GBS'lu olgular gözden geçirildiğinde bazı ortak klinik özellikleri saptanmıştır. Bunlar: 1- Erkeklerde daha sık olması 2- Hepatit A enfeksiyonundan ortalama 14 gün sonra gelişmesi 3- Fasiyal sinir ve bulbar tutulumun sık olması 4- Yüzeyel duyu bozukluklarına ek olarak p...

  7. Akut poststreptokoksik glomerülonefritli bir çocuk hastada idiyopatik trombositopenik purpura

    OpenAIRE

    Bal, Alkan; Yurtseven, Ali; Şahbudak, Zümrüt; Anıl, Murat; Aksu, Nejat

    2014-01-01

    Akut poststreptokoksik glomerülonefrit APSGN çocukluk çağının en sık hematüri nedenlerinden biridir Akut poststreptokoksik glomerülonefritde hematolojik değişiklikler hemodilüsyon ve hafif düzeyde hemoliz nedeniyle gelişebilen anemi dışında tipik değildir İdiyopatik trombositopenik purpura İTP ve APSGN birlikteliği ise nadiren bildirilmektedir Bu makalede eş zamanlı APSGN ve İTP saptanan 13 yaşında bir hasta nadir görülmesi nedeniyle sunulmuştur Türk Ped Arş 2011; 46: 171 3...

  8. Atipik Özellikler Gösteren Akut Enflamatuvar Polinöropatili Bir Olgu

    Directory of Open Access Journals (Sweden)

    Sule Aydin Turkoglu

    2016-01-01

    Full Text Available Bilateral fasiyal paralizi, ilerleyici kas güçsüzlüğü ve elektrofizyolojik değerlendirmede akut motor aksonal polinöropati bulguları gösteren bir olgu sunulmaktadır. Öncesinde karın ağrısı, ishal ve grip benzeri şikayetlere sonrasında otonom anormallikler, görsel halüsinasyon epizotları, konuşma bozukluğu eklendi. Campylobacter jejuni enfeksiyonu, Lyme hastalığı ve porfiri ayırıcı tanısı yapıldı. Western-blot testi Lyme hastalığı birlikteliğini doğruladı. Ek olarak porfirine spesifik testler pozitif bulundu.

  9. Difteri Aşısı: Koruyucu Hekimlik Tarihinden Bir Örnek

    OpenAIRE

    KESMEZACAR, Özgü; DOĞAN, Hanzade; HOT, İnci

    2005-01-01

    Özet Koruyucu hekimlik, her zaman tedavi seçeneklerinden daha de¤erli olmufltur. Kiflileri, tedavinin zahmet ve yan etkilerinden korur. Afl›lamalar, koruyucu hekimli¤in önemli bir arac›d›r. Bu konulardaki araflt›rmalar t›p tarihinin de¤iflik dönemlerinde varolmufltur. Bu çal›flmada, tarih içerisinde difteri ile mücadelenin detaylar› anlat›lmaktad›r. Ana kayna¤›m›z, 1925 y›l›nda yay›nlanm›fl olan "S›hhiye Mecmuas›"d›r. Bulgular, karfl›laflt›rmal› olarak tart›fl›lm›flt›r. .Anahtar Kelimeler: Difteri afl›s›,...

  10. SLOWPOKE reactor

    International Nuclear Information System (INIS)

    Evans, D.J.R.; Downs, W.E.

    1974-01-01

    The SLOWPOKE reactor is described, which is a small pool type with thermal neutron fluxes ranging from 10 11 -10 12 n cm -2 sec -1 . It differs in many ways from conventional pool type, namely small critical mass, beryllium reflector and a closed reactor container. The reactor is designed as small and simply as possible, and consistently with safety and good operating practice. Access to the present model is via pneumatic irradiation tubes only, which limits the use of the facility to activation analysis, tracer production and training. (Mori, K.)

  11. Nuclear reactor

    International Nuclear Information System (INIS)

    Rau, P.

    1980-01-01

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

  12. Pengaruh Lama Perendaman dan Jenis Minuman Beralkohol Bir dan Tuak terhadap Kekerasan Email Gigi Manusia (In Vitro

    Directory of Open Access Journals (Sweden)

    Malida Magista

    2014-06-01

    Full Text Available Erosi gigi merupakan hilangnya lapisan email gigi karena asam. Jenis asam, pH rendah, serta kandungan kalsium, fosfat, dan fluoride pada bir dan tuak diduga merupakan faktor kimiawi penyebab erosi gigi. Tujuan penelitian ini untuk mengetahui pengaruh lama perendaman dan jenis minuman beralkohol bir dan tuak terhadap kekerasan email gigi manusia (in vitro. Penelitian ini menggunakan 14 sampel gigi premolar pertama atas. Setiap gigi dibagi menjadi 2 bagian, bukal dan palatal. kemudian dibagi menjadi 7 kelompok perlakuan, yaitu kelompok (A1 perendaman dalam bir (ringan; (A2 kelompok perendaman dalam bir sedang; kelompok (A3 perendaman dalam bir berat, kelompok (B1: perendaman dalam tuak ringan, (B2: perendaman dalam tuak sedang, (B3: perendaman dalam tuak berat dan kelompok kontrol (C. Uji kekerasan email gigi dilakukan menggunakan Micro Vickers Hardness Tester. Pengujian kekerasan awal email gigi dilakukan sebelum perendaman gigi. Perendaman gigi premolar pertama atas pada bir dan tuak dilakukan selama 10 detik, 50 detik, dan 250 detik perhari dengan penyimpanan subjek penelitian pada saliva buatan. Uji kekerasan akhir email gigi dilakukan setelah perlakuan selama 30 hari. Nilai perubahan kekerasan email gigi merupakan selisih nilai kekerasan akhir dan nilai kekerasan awal email gigi. Sebagai tambahan data, pada bir dan tuak juga diukur kandungan pH, kalsium, dan fosfor. Data dianalisis menggunakan uji ANAVA dua jalur dilanjutkan dengan uji LSD. Hasil analisis ANAVA dua jalur menujukkan bahwa jenis minuman dan lama perendaman berpengaruh bermakna terhadap kekerasan email gigi (p<0,05. Hasil uji LSD menunjukkan adanya perbedaan rerata yang signifikan (p<0,05 antar kelompok uji bir dan tuak. Kesimpulan dari penelitian ini adalah terdapat pengaruh jenis minuman beralkohol bir dan tuak dan lama perendaman terhadap kekerasan email gigi manusia (in vitro. The Effect Of Contact Time And Alcohol Beverages Beer And Tuak On Human Dental Enamel Hardness (In

  13. NUCLEAR REACTOR

    Science.gov (United States)

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

    1958-01-21

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

  14. Reactor Neutrinos

    Directory of Open Access Journals (Sweden)

    Soo-Bong Kim

    2013-01-01

    Full Text Available We review the status and the results of reactor neutrino experiments. Short-baseline experiments have provided the measurement of the reactor neutrino spectrum, and their interest has been recently revived by the discovery of the reactor antineutrino anomaly, a discrepancy between the reactor neutrino flux state of the art prediction and the measurements at baselines shorter than one kilometer. Middle and long-baseline oscillation experiments at Daya Bay, Double Chooz, and RENO provided very recently the most precise determination of the neutrino mixing angle θ13. This paper provides an overview of the upcoming experiments and of the projects under development, including the determination of the neutrino mass hierarchy and the possible use of neutrinos for society, for nonproliferation of nuclear materials, and geophysics.

  15. REACTOR SHIELD

    Science.gov (United States)

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

    1959-02-17

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

  16. NEUTRONIC REACTOR

    Science.gov (United States)

    Anderson, H.L.

    1960-09-20

    A nuclear reactor is described comprising fissionable material dispersed in graphite blocks, helium filling the voids of the blocks and the spaces therebetween, and means other than the helium in thermal conductive contact with the graphite for removing heat.

  17. Chemical Reactors.

    Science.gov (United States)

    Kenney, C. N.

    1980-01-01

    Describes a course, including content, reading list, and presentation on chemical reactors at Cambridge University, England. A brief comparison of chemical engineering education between the United States and England is also given. (JN)

  18. Reactor technology

    International Nuclear Information System (INIS)

    Erdoes, P.

    1977-01-01

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

  19. Propulsion reactors

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    A nuclear reactor equips the recently constructed French aircraft- carrier Charles-De-Gaulle, in a few months the second nuclear submarine (SNLE) of new generation will be operational. In last october the government launched the program Barracuda which consists of 6 submarines (SNA) whose series head will be operational in 2010. The main asset of nuclear propulsion is to allow an almost unlimited autonomy: soft water, air are produced inside the submarine and the maximum time spent underwater is only limited by human capacity to cope with confinement. CEA has 3 missions concerning country defence. First the designing, the fabrication and the maintenance of weapons, secondly the supplying of fissile materials and thirdly the nuclear propulsion. A new generation of propulsion reactors is being studied and a ground installation involving a test reactor equivalent to that on board is being built. This test reactor (RES) will simulate any type of on-board reactors by adjusting temperature, pressure, flowrate and even equipment such as steam generator. This reactor will validate the technological choices for the Barracuda program. (A.C.)

  20. Angela Carter’ın The Bloody Chamber Adlı Anlatısı: Feminist Deyişbilimsel Bir Yaklaşım

    OpenAIRE

    ARIKAN, Seda

    2016-01-01

    Bir yazarın yazın üslubunu inceleyen deyişbilim özellikle son yirmi otuz yıldırçeşitli yaklaşımları bir araya getirmiştir. Bu nedenle, feminist eleştiriüzerine temellenen feminist deyişbilim, kadını ve kadının konumunu sadecetoplumda değil dilde de tanımlayan önemli bir yaklaşım olarak ortaya çıkar.Feminist deyişbilim, toplumdaki ve edebi eserlerdeki erkek egemenliğiniinceleyerek, hem dil hem de toplum yapılanmasında kadın için bir karşı-imgesunmaya çalışır. Mevcut feminist deyişbilim yaklaşı...

  1. Research reactors - an overview

    International Nuclear Information System (INIS)

    West, C.D.

    1997-01-01

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

  2. Türkiye İçin Gümrük Birliği’ne Alternatif Bir Pazar: İslam İşbirliği Teşkilatı / An Alternative Market to European Union for Turkey: The Organization of Islamic Cooperation

    Directory of Open Access Journals (Sweden)

    Hayrettin Kesgingöz

    2018-03-01

    Full Text Available Abstract Increasing competition in the world by the help of globalization has directed countries to cooperation with other countries and interregional organizations. Nowadays competition in foreign trade is becoming more and more challenging due to globalization process and countries use the most important alternatives, economic integrations to export and import. The new idea of creating new regional alternatives to increase foreign trade for Turkey is becoming more important day by day. Organization of Islamic Cooperation (OIC which is being created under the leadership of Turkey has an important share on Turkish foreign trade after G20, OECD and Customs Union. Though OIC has occupied an important place in Turkish foreign trade it is least known and this study searches whether OIC can become an alternative in future. In order to answer this question, the performance analysis of foreign trade was conducted with the help of macroeconomic indicators while the analysis of foreign trade compliance was held with the help of international foreign trade indices. As a result of foreign trade compliance analysis it is concluded that importance of Organization of Islamic Cooperation is increasing every day. Though foreign trade between Turkey and Customs Union reduced, foreign trade between Turkey and OIC increased and that result shows that Turkey turns his face to markets of OIC. However foreign trade between Turkey and OIC can just be alternative to Custom union in further years.   Öz Küreselleşmeyle birlikte dünyada artan rekabet ortamı 2008 küresel ekonomik krizinden sonra dünya ülkelerini ülkeler ve bölgeler arası işbirliğine doğru yöneltmiştir. Küreselleşme sürecinde dış ticarette rekabetin her geçen gün zorlaştığı bir dönemde bugün ülkeler, dış ticareti gerçekleştirmek için en önemli seçenekleri olan ülkeler ve bölgesel arası ekonomik bütünleşmeleri kullanmaktadırlar. Yeni yeni bölgesel ekonomik b

  3. Kosovo albaanlaste imelootus hääbub läbirääkimiste kiuste / Triin Oppi

    Index Scriptorium Estoniae

    Oppi, Triin

    2007-01-01

    Serbia ja Kosovo provintsi esindajate läbirääkimistest Viinis ning ÜRO esindaja Martti Ahtisaari ettepanekust Kosovo suhtes, kus välditakse sõna "iseseisvus". Euroopa Liit üritab Kosovot juhtida iseseisvuse teele, pakkudes Serbiale võimalust mitte anda välja Haagi sõjatribunalile Ratko Mladicit. Vt. samas: Kosovo äärmuslased õhkisid kolm ÜRO sõidukit. Kaart

  4. Lithospheric mantle evolution in the Afro-Arabian domain: Insights from Bir Ali mantle xenoliths (Yemen)

    Science.gov (United States)

    Sgualdo, P.; Aviado, K.; Beccaluva, L.; Bianchini, G.; Blichert-Toft, J.; Bryce, J. G.; Graham, D. W.; Natali, C.; Siena, F.

    2015-05-01

    Detailed petrological and geochemical investigations of an extensive sampling of mantle xenoliths from the Neogene-Quaternary Bir Ali diatreme (southern Yemen) indicate that the underlying lithospheric mantle consists predominantly of medium- to fine-grained (often foliated) spinel-peridotites (85-90%) and spinel-pyroxenites (10-15%) showing thermobarometric estimates in the P-T range of 0.9-2.0 GPa and 900-1150 °C. Peridotites, including lherzolites, harzburgites and dunites delineate continuous chemical, modal and mineralogical variations compatible with large extractions of basic melts occurring since the late Proterozoic (~ 2 Ga, according to Lu-Hf model ages). Pyroxenites may represent intrusions of subalkaline basic melts interacting and equilibrated with the host peridotite. Subsequent metasomatism has led to modal changes, with evidence of reaction patches and clinopyroxene and spinel destabilization, as well as formation of new phases (glass, amphibole and feldspar). These changes are accompanied by enrichment of the most incompatible elements and isotopic compositions. 143Nd/144Nd ranges from 0.51419 to 0.51209 (εNd from + 30.3 to - 10.5), 176Hf/177Hf from 0.28459 to 0.28239 (εHf from + 64.4 to - 13.6), and 208Pb/204Pb from 36.85 to 41.56, thus extending from the depleted mantle (DM) towards the enriched OIB mantle (EM and HIMU) components. 3He/4He (R/RA) ratios vary from 7.2 to 7.9 with He concentrations co-varying with the most incompatible element enrichment, in parallel with metasomatic effects. These metasomatic events, particularly effective in harzburgites and dunites, are attributable to the variable interaction with alkaline basic melts related to the general extensional and rifting regime affecting the East Africa-Arabian domain during the Cenozoic. In this respect, Bir Ali mantle xenoliths resemble those occurring along the Arabian margins and the East Africa Rift system, similarly affected by alkaline metasomatism, whereas they are

  5. Hz. Peygamber Dönemi Eğitimine Genel Bir Bakış

    Directory of Open Access Journals (Sweden)

    Yasin Yılmaz

    2015-11-01

    Full Text Available Allah'a inanan güzel ahlakla teçhiz edilen erdemli bir toplum oluşturmayı amaçlayan Hz. Peygamber için bunu gerçekleştirmede, ilim, eğitim ve öğretim bir hayat felsefesi olmuştur. Buna paralel olarak onun çalışmalarında ve sözlerinde bilgi, öğrenme, öğretme, öğrenci ve öğretmene büyük önem verildiği görülmektedir. İnsanIarın karanlıktan aydınlığa çıkması için bütün imkanları kullanmıştır. Ancak Hz. Peygamber'in yaptığı eğitim ve öğretimi kendi döneminin sosyal ve fiziki şartları, ihtiyaçları ve metotları çerçevesinde gerçekleştirdiğini unutmamak gerekir. Dönemin şartlarının, imkanlarının ve olumsuzluklarının çok fazla olmasına rağmen, Hz.Peygamber'in eğitim ve öğretim konusunda bugün dahi geçerliliğini koruyan evrensel nitelikteki uygulamaları bizim için çok önemlidir. Modem çağların insanlarının olan günümüz insanlarının onun eğitim ve öğretim sisteminden istifade edeceği çok yönlerin olduğu kanaatindeyim

  6. Nuclear reactors

    International Nuclear Information System (INIS)

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

    1978-01-01

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

  7. Reactor utilization

    International Nuclear Information System (INIS)

    Zecevic, V.

    1963-01-01

    In 1962, the RA reactor was operated almost three times more than in 1961, producing total of 25 555 MWh. Diagram containing comparative data about reactor operation for 1960, 1961, and 1962, percent of fuel used and U-235 burnup shows increase in reactor operation. Number of samples irradiated was 659, number of experiments done was 16. mean powered level was 5.93 MW. Fuel was added into the core twice during the reporting year. In fact the core was increased from 56 to 68 fuel channels and later to 84 fuel channels. Fuel was added to the core when the reactivity worth decreased to the minimum operation level due to burnup. In addition to this 5 central fuel channels were exchanged with fresh fuel in february for the purpose of irradiation in the VISA-2 channel

  8. Bioconversion reactor

    Science.gov (United States)

    McCarty, Perry L.; Bachmann, Andre

    1992-01-01

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

  9. Thermonuclear reactor

    International Nuclear Information System (INIS)

    Araki, Takao; Saito, Yasushi.

    1987-01-01

    Purpose: To reduce the seismic wave responsivity of an exhaust duct shields thereby preventing the release of tritium in an evacuating device due to failures upon earthquakes. Constitution: The ends on the cutting side of upper outer exhaust duct shields of a thermonuclear reactor are connected with a plurality of support beams. In a case where seismic vibrations are exerted to such a thermonuclear reactor, since the ends on the cutting side are coupled with the support beams, vibrations of the upper outer exhaust duct shields are greatly restricted. Thus, since there is no more such a possibility, for example, that an exhaust duct connected to the upper portion of a reactor main body is greatly distorted due to the seismic response of the upper outside exhaust duct shields to result in the failure of the connection portion with a vacuum pump, the release of tritium due to failure of the evacuating device can be prevented. (Yoshino, Y.)

  10. An Evaluation on Library Cooperation in Turkey Türkiye'de Kütüphanelerarası İşbirliği Üzerine Bir Değerlendirme

    Directory of Open Access Journals (Sweden)

    Mehmet Emin Küçük

    2004-06-01

    Full Text Available No library in the world has the sufficient budget, space, and professionals to acquire all existing information sources, and to organise and serve the acquired materials. For this reason, libraries cooperate in collection development, cata loguing, providing access to the others' collections and document delivery. Aiming at evaluating the co-operation efforts during the Republican era from the perspective of the historical, organisational and practicable fields of implementation, this paper examines the library co-operation in Turkey. To determine the present situation, the Turkish National Library, General Directorate of Libraries and Publications, National Academic Network and Information Centr, and some special and school libraries in Ankara, Ministry of National Education, university libraries, consortia, and professional associations are examined, and the data gathered from literature and interviews are evaluated. In conclusion, it has been observed that in recent years, co-operation effort has gained momentum, two consortia have emerged to provide access to the electronic information sources, document delivery projects between university libraries have been started, but efforts in some practicable fields of co-operation, such as preparing union catalogues, sharing bibliographic data, and developing authority files have been unsuccessful. It has also been observed that there is lack of co-operation except among university libraries, and that institutions have failed in establishing a "common wisdom" and consequently in developing the skills of planning and organisation. Inadequacy of resources, legislation, and infrastructure, and most importantly the lack of dedication resulted in discontinuity of the ongoing projects and the production of the new ones. Dünyadaki hiç bir kütüphane varolan tüm bilgi kaynaklarını sağlama, düzenleme ve hizmete sunmada yeterli bütçe, bina ve profesyonele sahip değildir. Bu nedenle k

  11. Bir Felaketin Anatomisi Bazar de La Charite Yangını

    Directory of Open Access Journals (Sweden)

    Anıl Özgüç

    2011-12-01

    Full Text Available Bazar de la Charite, 1885 yılında Katolik Fransız Aristokratlan tarafından yardım ve hayır amacıyla Paris'de kurulmuştur. 1897 yılında yangına kadar yıllık bir organizasyon olarak varlığını sürdürmüştür. Yangında çoğu aristokrat 126 kişi hayatmı kaybetmiştir. Yangının ardından 30 ceset yakınlan tarafından teşhis edilememiş, kimliklendirme amacıyla diş hekimlerine başvurulmuştur. Dr. Oscar Amoedo'nun yürüttüğü çalışmalann sonucunda teşhis edilemeyen cesetler kimliklendirilmiştir. Dr. Oscar Amoedo, yangın sonrası kimliklendirmede diş hekimlerinin rolünü anlatan makalesi ve ardından yayınladığı “L'Art dentaire en Medecine Legale” adlı kitabıyla adli odontolojinin temellerini kurmuştur. Anahtar kelimeler: Bazar de la Charite, adli odontoloji, yangın, Paris

  12. Ölüm Nedeninin Tespitinde Yardımcı Bir Bulgu Diagonal Kulak Lobu Çizgisi

    Directory of Open Access Journals (Sweden)

    Birol Demirel

    2005-08-01

    Full Text Available Koroner arter hastalıkları, doğal sebeplerle meydana gelen ölüm nedenlerinin başında gelmektedir. Bu hastalıkların yüksek insidans ve mortalité oranları, bilinen risk faktörlerinden çok, olası risk faktörlerinin araştırılmasını gerekli kılmıştır. Bir fizik muayene bulgusu olan diagonal kulak lobu çizgisi (DKLÇ, 1973 yılında tanımlanmıştır. Çalışmamızda, DKLÇ’nin, ölü muayenesi yapan hekim için ölüm nedeninin tespitinde yardımcı bir bulgu olup olamayacağının saptanması amaçlanmıştır. Çalışmamızın bulguları, vakalara uygulanan anjiografiler sonucunda; a. coronaria sinistranın dalları olan ramus interventricularis anterior (RIA ve ramus circumflexus (RC ile a. coronaria dextra’da (ACD saptanan daralma yüzdeleri arttıkça DKLÇ görülme sıklığının da arttığını göstermektedir. Bu durum DKLÇ ve koroner arter hastalıkları arasmda anlamlı ilişkiler bildiren daha önceki çalışmaların bulguları ile uyumludur. Özellikle öyküye ulaşma olanağı bulunmayan ve herhangi bir travmatik bulgu saptanmayan vakalarda DKLÇ’nin, ölümün koroner arter hastalığından meydana geldiği yönünde destekleyici bir bulgu olarak muayeneyi yapan hekimin dikkatini çekmesi gereken bir işaret olduğunu düşünmekteyiz. Anahtar kelimeler: Diagonal kulak lobu çizgisi, koroner arter hastalığı, ölü muayenesi.

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    Gilroy, J.E.

    1980-01-01

    An improved cover structure for liquid metal cooled fast breeder type reactors is described which it is claimed reduces the temperature differential across the intermediate grid plate of the core cover structure and thereby reduces its subjection to thermal stresses. (UK)

  14. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    The method of operating a water-cooled neutronic reactor having a graphite moderator is described which comprises flowing a gaseous mixture of carbon dioxide and helium, in which the helium comprises 40--60 volume percent of the mixture, in contact with the graphite moderator. 2 claims, 4 figures

  15. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield

  16. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

    This presentation discusses reactor licensing and includes the legislative basis for licensing, other relevant legislation , the purpose of the Nuclear Safety and Control Act, important regulations, regulatory document, policies, and standards. It also discusses the role of the CNSC, its mandate and safety philosophy

  17. Neutronic reactor

    International Nuclear Information System (INIS)

    Carleton, J.T.

    1977-01-01

    A graphite-moderated nuclear reactor includes channels between blocks of graphite and also includes spacer blocks between adjacent channeled blocks with an axis of extension normal to that of the axis of elongation of the channeled blocks to minimize changes in the physical properties of the graphite as a result of prolonged neutron bombardment. 3 claims, 6 figures

  18. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

    1994-01-01

    In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

  19. Nuclear reactor

    International Nuclear Information System (INIS)

    Gibbons, J.F.; McLaughlin, D.J.

    1978-01-01

    In the pressure vessel of the water-cooled nuclear reactor there is provided an internal flange on which the one- or two-part core barrel is hanging by means of an external flange. A cylinder is extending from the reactor vessel closure downwards to a seat on the core cupport structure and serves as compression element for the transmission of the clamping load from the closure head to the core barrel (upper guide structure). With the core barrel, subject to tensile stress, between the vessel internal flange and its seat on one hand and the compression of the cylinder resp. hold-down element between the closure head and the seat on the other a very strong, elastic sprung structure is obtained. (DG) [de

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    Aleite, W.; Bock, H.W.; Struensee, S.

    1976-01-01

    The invention concerns the use of burnable poisons in a nuclear reactor, especially in PWRs, in order to improve the controllability of the reactor. An unsymmetrical arrangement in the lattice is provided, if necessary also by insertion of special rods for these additions. It is proposed to arrange the burnable poisons in fuel elements taken over from a previous burn-up cycle and to distribute them, going out from the side facing the control rods, over not more than 20% of the lenth of the fuel elements. It seems sufficient, for the burnable poisons to bind an initial reactivity of only 0.1% and to become ineffective after normal operation of 3 to 4 months. (ORU) [de

  1. Reactor container

    International Nuclear Information System (INIS)

    Otsuka, Hiroaki; Yoshida, Takashi.

    1979-01-01

    Purpose: To prevent rain water falling along the outer wall of the container during the construction work of an atomic power plant from making ingress into the inner part of a reactor container through a large size material carry-in port. Constitution: A weir for preventing the ingress of rain water is provided on the border between the foot floor of a large material carry-in port provided on the side surface at the bottom part of the reactor container and the floor surface of the building. This weir is of a semi-circular plate shape, and formed so that the lower semi-circular part of the carry-in port is tightly closed. (Kamimura, M.)

  2. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Saba, Kazuhisa.

    1979-01-01

    Purpose: To improve the earthquake resistance as well as reduce the size of a container for a nuclear reactor with no adverse effects on the decrease of impact shock to the container and shortening of construction step. Constitution: Reinforcing profile steel materials are welded longitudinally and transversely to the inner surface of a container, and inner steel plates are secured to the above profile steel materials while keeping a gap between the materials and the container. Reactor shielding wall planted to the base concrete of the container is mounted to the pressure vessel, and main steam pipeways secured by the transverse beams and led to the outside of container is connected. This can improve the rigidity earthquake strength and the safetiness against the increase in the inside pressure upon failures of the container. (Yoshino, Y.)

  3. Reactor container

    International Nuclear Information System (INIS)

    Oyamada, Osamu; Furukawa, Hideyasu; Uozumi, Hiroto.

    1979-01-01

    Purpose: To lower the position of an intermediate slab within a reactor container and fitting a heat insulating material to the inner wall of said intermediate slab, whereby a space for a control rod exchanging device and thermal stresses of the inner peripheral wall are lowered. Constitution: In the pedestal at the lower part of a reactor pressure vessel there is formed an intermediate slab at a position lower than diaphragm floor slab of the outer periphery of the pedestal thereby to secure a space for providing automatic exchanging device of a control rod driving device. Futhermore, a heat insulating material is fitted to the inner peripheral wall at the upper side of the intermediate slab part, and the temperature gradient in the wall thickness direction at the time of a piping rupture trouble is made gentle, and thermal stresses at the inner peripheral wall are lowered. (Sekiya, K.)

  4. Neutronic reactor

    International Nuclear Information System (INIS)

    Lewis, W.R.

    1978-01-01

    Disclosed is a graphite-moderated, water-cooled nuclear reactor including a plurality of rectangular graphite blocks stacked in abutting relationship in layers, alternate layers having axes which are normal to one another, alternate rows of blocks in alternate layers being provided with a channel extending through the blocks, said channeled blocks being provided with concave sides and having smaller vertical dimensions than adjacent blocks in the same layer, there being nuclear fuel in the channels

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    Shirakawa, Toshihisa.

    1979-01-01

    Purpose: To prevent cladding tube injuries due to thermal expansion of each of the pellets by successively extracting each of the control rods loaded in the reactor core from those having less number of notches, as well as facilitate the handling work for the control rods. Constitution: A recycle flow control device is provided to a circulation pump for forcibly circulating coolants in the reactor container and an operational device is provided for receiving each of the signals concerning number of notches for each of the control rods and flow control depending on the xenon poisoning effect obtained from the signals derived from the in-core instrument system connected to the reactor core. The operational device is connected with a control rod drive for moving each of the control rods up and down and a recycle flow control device. The operational device is set with a pattern for the aimed control rod power and the sequence of extraction. Upon extraction of the control rods, they are extracted successively from those having less notch numbers. (Moriyama, K.)

  6. Reactor building

    International Nuclear Information System (INIS)

    Ebata, Sakae.

    1990-01-01

    At least one valve rack is disposed in a reactor building, on which pipeways to a main closure valve, valves and bypasses of turbines are placed and contained. The valve rack is fixed to the main body of the building or to a base mat. Since the reactor building is designed as class A earthquake-proofness and for maintaining the S 1 function, the valve rack can be fixed to the building main body or to the base mat. With such a constitution, the portions for maintaining the S 1 function are concentrated to the reactor building. As a result, the dispersion of structures of earthquake-proof portion corresponding to the reference earthquake vibration S 1 can be prevented. Accordingly, the conditions for the earthquake-proof design of the turbine building and the turbine/electric generator supporting rack are defined as only the class B earthquake-proof design conditions. In view of the above, the amount of building materials can be saved and the time for construction can be shortened. (I.S.)

  7. Kamu Yönetiminde Bir Yönetişim Hedefi Olarak Kaynak Optimizasyonu: Kalkınma Ajanslarında COBIT-5 Çerçevesinde Bir Analiz

    Directory of Open Access Journals (Sweden)

    Ahmet Efe

    2016-01-01

    Full Text Available Kurumsal kaynak planlaması (ERP ve insan kaynakları yönetimi (HRM sistemleri sayesinde fiziki, beşeri, fikri ve mali kaynakların yönetimi gibi kavramlar, standartlar ve gerektirdikleri uygulamalar işletmecilik ve kamu yönetimi alanına girmiştir. Ancak kaynak optimizasyonu yaklaşımı ise ilk defa bir yönetişim hedefi ve süreci olarak yapılandırılması olarak COBİT-5 ile ortaya atılmıştır. Bu çalışmada kaynak optimizasyonu ile ilgili olarak Türkiye’de kalkınma ajansları (KA ve bölgesel gelişme dinamiklerinde yapılandırılmış bir yaklaşımın mevcut olmadığından dolayı Devlet Denetleme Kurulu (DDK tarafından belirlenmiş olan kurumsal sorunların çekirdek nedenleri araştırma problemi olarak ele alınmaktadır. COBIT-5 kaynak optimizasyonu ile ilgili modellemesinin KA dinamiklerine uyabilecek ve ilişkili kurumsal sorunları çözebilecek bir modellemenin olanaklı olduğu araştırmamızda iddia edilmektedir. Bu çerçevede yapılan analizler sonucunda kaynak optimizasyonu sürecinin KA dinamiklerinde nasıl işletilebileceği, kilit performans göstergeleri, kriter faaliyetler ile süreçlerde sorumlu, mesul, danışılan ve bilgilendirilen rollerin neler olduğu tespit edilmeye çalışılmaktadır.

  8. The structure of the BIR3 domain of cIAP1 in complex with the N-terminal peptides of SMAC and caspase-9

    Energy Technology Data Exchange (ETDEWEB)

    Kulathila, Raviraj; Vash, Brian; Sage, David; Cornell-Kennon, Susan; Wright, Kirk; Koehn, James; Stams, Travis; Clark, Kirk; Price, Allen ((Novartis)); ((Emmanuel))

    2009-06-24

    The inhibitor of apoptosis protein (IAP) family of molecules inhibit apoptosis through the suppression of caspase activity. It is known that the XIAP protein regulates both caspase-3 and caspase-9 through direct protein-protein interactions. Specifically, the BIR3 domain of XIAP binds to caspase-9 via a 'hotspot' interaction in which the N-terminal residues of caspase-9 bind in a shallow groove on the surface of XIAP. This interaction is regulated via SMAC, the N-terminus of which binds in the same groove, thus displacing caspase-9. The mechanism of suppression of apoptosis by cIAP1 is less clear. The structure of the BIR3 domain of cIAP1 (cIAP1-BIR3) in complex with N-terminal peptides from both SMAC and caspase-9 has been determined. The binding constants of these peptides to cIAP1-BIR3 have also been determined using the surface plasmon resonance technique. The structures show that the peptides interact with cIAP1 in the same way that they interact with XIAP: both peptides bind in a similar shallow groove in the BIR3 surface, anchored at the N-terminus by a charge-stabilized hydrogen bond. The binding data show that the SMAC and caspase-9 peptides bind with comparable affinities (85 and 48 nM, respectively).

  9. Christopher Nolan’ın ‘Batman Üçlemesi’ Üzerine İdeolojik Bir İnceleme

    OpenAIRE

    BÖLÜKBAŞI, Mustafa

    2013-01-01

    Bu makalede bir süperkahraman anlatısı olarak Batman’in nasıl bir ideolojik anlamı olduğu sorgulanmaktadır. Bu amaçlaChristopher Nolan’ın çekmiş olduğu Batman Başlıyor (2005), Kara Şövalye (2008) ve Kara Şövalye Yükseliyor (2012) filmleri,altında yatan ideolojiyi ortaya serecek bir içerik analizine tabi tutulmaktadır. Bu incelemede, “kötülük” ile mücadeleetmek için neden bir Batman yaratıldığı, bunun nasıl bir amacının olabileceği, Batman’e kimin ihtiyaç duyduğu, kısacasıNolan’ın Batman üçlem...

  10. 8051 Mikrodenetleyicili Bir Sumo Robot Tasarımı ve Uygulaması

    Directory of Open Access Journals (Sweden)

    Mehmet ALBAYRAK

    2009-04-01

    Full Text Available Bu çalısmada, 8051 mikrodenetleyici kontrollü bir sumo robotun mekanik tasarımı, kontrol kartı ve yazılımı gerçeklestirilmistir. Robot, yarısma ve egitim amaçlı tasarlandıgı için hücum amaçlı strateji içeren yazılım gelistirilerek yüklenmistir. 8051 mikrodenetleyici içindeki kontrol yazılımı PC 'nin seri portuna baglı mikrodenetleyici programlama kartına takılıp, kolaylıkla güncellenebildigi için yazılım stratejisi her yarısma için degistirilebilir niteliktedir. Microdenetleyici yazılımı μVision Keil derleyicisinde C kodu kullanılarak hazırlanmıstır. Mekanik tasarım asamasında robot dıs yüzeyinin darbelere dayanıklı malzemeden seçilmesine ve tekerleklerin sürtünmesinin fazla (kaymaz olmasına özen gösterilmistir. Robotun gücünü belirlenen agırlık sınırları içinde en fazla hale getirebilmek için 4 ayrı disli DC motor ve 4 amperlik akü kullanılmıstır. Rakip algılama mesafe sensörü ve kontrast sensörü (beyaz algılama seçiminde cevap verme süresi çok az olan sensörler tercih edilmistir.

  11. Nuclear research reactors

    International Nuclear Information System (INIS)

    1985-01-01

    It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.) [pt

  12. 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

  13. Çelik Bir Bacanın Dinamik Davranışının Analizi

    OpenAIRE

    GÜRSOY, Gökhan; YERLİ, Hüseyin R.; KAÇIN, Selçuk

    2015-01-01

    Giderek artan endüstriyel tesislerin (termik ve nükleer santraller, demir çelik fabrikaları, değişik imalata yönelik fabrikalar) ihtiyacı olan endüstriyel bacalar için ülkemizde henüz bir standart bulunmamaktadır. Yine bu yapıların modellenmesi için paket programlar kullanılmakta ancak gerçek davranışı hakkında saha çalışmalarına gerek duyulmaktadır

  14. Monitoring Voltage-Dependent Charge Displacement of Shaker B-IR K+ Ion Channels Using Radio Frequency Interrogation

    OpenAIRE

    Dharia, Sameera; Rabbitt, Richard D.

    2011-01-01

    Here we introduce a new technique that probes voltage-dependent charge displacements of excitable membrane-bound proteins using extracellularly applied radio frequency (RF, 500 kHz) electric fields. Xenopus oocytes were used as a model cell for these experiments, and were injected with cRNA encoding Shaker B-IR (ShB-IR) K(+) ion channels to express large densities of this protein in the oocyte membranes. Two-electrode voltage clamp (TEVC) was applied to command whole-cell membrane potential a...

  15. Mevdûdî’nin Enfal 67 ve 68. Ayetler Hakkındaki Yorumuna Eleştirel Bir Yaklaşım

    OpenAIRE

    Büyük, Enes

    2015-01-01

    Enfal sûresinin 67. ayetinde Hz. Peygamber ve müminler Bedir savaşında esir almalarındandolayı uyarılmıştır. 68. ayette de, Allah’ın önceden geçen bir Kitab/hükmü olmasaydı,esirlere karşı fidye almaları sebebiyle onların elim bir azaba uğrayacakları bildirilmiştir.Bu ayette yer alan "Kitab" kelimesinin mahiyeti tartışmalı olup erken dönemden beri farklıyorumlar yapılmıştır. Son dönemde bu açıklamalara bir yenisi Mevdûdî tarafından eklenmiştir.O, bu ayetteki "Kitab/hüküm" i...

  16. Photocatalytic reactor

    Science.gov (United States)

    Bischoff, Brian L.; Fain, Douglas E.; Stockdale, John A. D.

    1999-01-01

    A photocatalytic reactor for processing selected reactants from a fluid medium comprising at least one permeable photocatalytic membrane having a photocatalytic material. The material forms an area of chemically active sites when illuminated by light at selected wavelengths. When the fluid medium is passed through the illuminated membrane, the reactants are processed at these sites separating the processed fluid from the unprocessed fluid. A light source is provided and a light transmitting means, including an optical fiber, for transmitting light from the light source to the membrane.

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    Anthony, A.J.; Gruber, E.A.

    1979-01-01

    A nuclear reactor with control rods in channels between fuel assemblies wherein the fuel assemblies incorporate guide rods which protrude outwardly into the control rod channels to prevent the control rods from engaging the fuel elements. The guide rods also extend back into the fuel assembly such that they are relatively rigid members. The guide rods are tied to the fuel assembly end or support plates and serve as structural members which are supported independently of the fuel element. Fuel element spacing and support means may be attached to the guide rods. 9 claims

  18. D and DR Reactors

    Data.gov (United States)

    Federal Laboratory Consortium — The world's second full-scale nuclear reactor was the D Reactor at Hanford which was built in the early 1940's and went operational in December of 1944.D Reactor ran...

  19. Reactor core fuel management

    International Nuclear Information System (INIS)

    Silvennoinen, P.

    1976-01-01

    The subject is covered in chapters, entitled: concepts of reactor physics; neutron diffusion; core heat transfer; reactivity; reactor operation; variables of core management; computer code modules; alternative reactor concepts; methods of optimization; general system aspects. (U.K.)

  20. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T [Huntington Beach, CA; Sahimi, Muhammad [Altadena, CA; Fayyaz-Najafi, Babak [Richmond, CA; Harale, Aadesh [Los Angeles, CA; Park, Byoung-Gi [Yeosu, KR; Liu, Paul K. T. [Lafayette Hill, PA

    2011-03-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  1. Reactor container

    International Nuclear Information System (INIS)

    Oikawa, Hirohide; Otonari, Jun-ichiro; Tozaki, Yuka.

    1993-01-01

    Partition walls are disposed between a reactor pressure vessel and a suppression chamber to separate a dry well to an upper portion and a lower portion. A communication pipe is disposed to the partition walls. One end of the communication pipe is opened in an upper portion of the dry well at a position higher than a hole disposed to a bent tube of the suppression chamber. When coolants overflow from a depressurization valve by an erroneous operation of an emergency reactor core cooling device, the coolants accumulate in the upper portion of the dry well. When the pipeline is ruptured at the upper portion of the pressure vessel, only the inside of the pressure vessel and the upper portion of the dry well are submerged in water. In this case, the water level of the coolants does not elevate to the opening of the commuication pipe but they flow into the suppression chamber from the hole disposed to the bent tube. Since the coolants do not flow out to the lower portion of the dry well, important equipments such as control rod drives disposed at the lower portion of the dry wall can be prevented from submerging in water. (I.N.)

  2. Reactor container

    Energy Technology Data Exchange (ETDEWEB)

    Oikawa, Hirohide; Otonari, Jun-ichiro; Tozaki, Yuka.

    1993-09-07

    Partition walls are disposed between a reactor pressure vessel and a suppression chamber to separate a dry well to an upper portion and a lower portion. A communication pipe is disposed to the partition walls. One end of the communication pipe is opened in an upper portion of the dry well at a position higher than a hole disposed to a bent tube of the suppression chamber. When coolants overflow from a depressurization valve by an erroneous operation of an emergency reactor core cooling device, the coolants accumulate in the upper portion of the dry well. When the pipeline is ruptured at the upper portion of the pressure vessel, only the inside of the pressure vessel and the upper portion of the dry well are submerged in water. In this case, the water level of the coolants does not elevate to the opening of the commuication pipe but they flow into the suppression chamber from the hole disposed to the bent tube. Since the coolants do not flow out to the lower portion of the dry well, important equipments such as control rod drives disposed at the lower portion of the dry wall can be prevented from submerging in water. (I.N.).

  3. Reactor monitor

    International Nuclear Information System (INIS)

    Takada, Tamotsu.

    1992-01-01

    The device of the present invention monitors a reactor so that each of the operations for the relocation of fuel assemblies and the withdrawal and the insertion of control rods upon exchange of fuel assemblies and control rods in the reactor. That is, when an operator conducts relocating operation by way of a fuel assembly operation section, the device of the present invention judges whether the operation indication is adequate or not, based on the information of control rod arrangement in a control rod memory section. When the operation indication is wrong, a stop signal is sent to a fuel assembly relocating device. Further, when the operator conducts control rod operation by way of a control rod operation section, the device of the present invention judges in the control rod withdrawal judging section, as to whether the operation indication given by the operator is adequate or not by comparing it with fuel assembly arrangement information. When the operation indication is wrong, a stop signal is sent to control rod drives. With such procedures, increase of nuclear heating upon occurrence of erroneous operation can be prevented. (I.S.)

  4. FOTOVOLTAiK SiSTEMLERiN DENETLENMESi iÇiN YENi BiR KONTROL KARTI VE BiLGiSAYAR YAZILIMI

    Directory of Open Access Journals (Sweden)

    Mustafa Berkant SELEK

    2008-02-01

    Full Text Available Bu çalısmada, İzmir ili Bornova ilçesindeki Ege Üniversitesi Günes Enerjisi Enstitüsü bünyesinde kurulan bir yenilenebilir enerji sisteminin elektrik akısını kontrol eden bir mikroislemci kartı tasarlanmıs ve bilgisayar yazılımı gelistirilmistir. Bu amaçla, anahtarlama görevi yapan güç elektronigi devre elemanlarının bulundugu ayrı bir elektronik kartın kontrol islemini üstlenen PIC18F452 mikrodenetleyicisi kullanan bir elektronik devre gerçeklestirilmistir. Piyasadaki standart kontrol kartları tek seviyeli eviricilerin anahtarlanmasına olanak saglamaktadır. Gelistirilen kontrol kartı ise çok seviyeli eviricilerle çalısmak üzere tasarlanmıstır. Bunun yanı sıra, günes enerjisi panellerinin verimleri oldukça düsük oldugundan, günes panellerinin maksimum güç noktasında (MPP çalıstırmak çok önemlidir. Bu yüzden, tasarlanan kontrol kartı üzerinde MPP algoritması da bulunmaktadır. Ayrıca, tasarlanan kontrol kartının üzerinde RS232 seri haberlesme arabirimi mevcuttur. Böylece, kontrol kartı üzerinde gerçeklestirilen tüm fonksiyonların kullanıcının istegine göre bir bilgisayar yazılımı aracılıgı ile seçilebilmesine ve istenirse kullanıcıya rapor olarak verilebilmesine olanak tanınmıstır. Son olarak, gelistirilen kontrol kartının, gelistirdigimiz yazılım ile haberlesebilmesi için bir komut seti olusturulmustur. Böylece, kendi kontrol kartını gelistirmek isteyen veya daha görsel bir yazılım gelistirmek isteyen diger arastırmacılar için ortak bir taban olusturulması hedeflenmistir.

  5. Godot Üzerine Bir Karşılaştırma A Comparison On Godot Summary

    Directory of Open Access Journals (Sweden)

    Halil ADIYAMAN

    2013-09-01

    Full Text Available The top works in world literature are composed by the way of imitation or endorsement (zeyl Samuel Beckett’s absurd theatre “waiting for Godot” is called as incongruous theatres in Turkish Literature. ”Waiting for Godot” which was written by Cahit Atay resembles in many ways when compared about fiction, place, time and characters. In Turkish Literature Ferhan Şensoy also writes about this topic, but Cahit Atay doesn’t change the things about basic fiction. But when looking at the basic difference, Beckett’s work is based on the waiting for Godot, while Atay doesn’t care about the fact of waiting forGodot. For Atay it doesn’t matter you can wait or not, but for BeckettGodot is an important thing to be waited. Godot who is waited to comein any time frightens people. It isn’t clear that who is Godot, what kindof things Godot bring or take away and what kind of character is Godot.For Atay, Godot is figured as a character which carries humanisticfeatures. Even if you can draw the portrait of Godot, Atay’s Godot isalso an abstract character.In the Works which include different facts about places, thecommon place is based on the property of a foreign person. For specialmeaning in two Works which include different cultures and civilizationsplace differs. Atay talks about different thing like concrete?Environment and the matters of our time. About characters, he changesthe names of them but he doesn’t change the mood and the attitudes ofthem. Dünya edebiyatındaki zirve eserler, taklit veya zeyl yoluyla yeniden oluşturulmaktadır. Samuel Beckett’in Godot’yu Beklerken isimli absürt oyunu Türk edebiyatında uyumsuz tiyatro oyunları olarak kaleme alınır. Cahit Atay’ın kaleme aldığı Godot’yu Beklerken kurgu, mekân, zaman ve şahıs kadrosu açısından değerlendirildiğinde birçok unsur bakımından benzerlikler gösterir. Türk edebiyatında Ferhan Şensoy’un da eser verdiği bu alanda, Cahit Atay temel

  6. Nef’î Hakkında Bir Bibliyografya Denemesi An Essay Of Bibliography About Nef’i

    Directory of Open Access Journals (Sweden)

    Halil Sercan KOŞİK

    2013-03-01

    Full Text Available Nef’î who lived in the first half of 17th century was born in Hasankale one of districts of Erzurum. The poet whose real name was Ömer had a life full of struggles but he managed to produce some important works through his life. Nef’î, one of the leading poets of divan poetry was celebrated much at his age and after his death. Such a reputation is originated from the sharpness of his pen, his talent as well as his wit. Nef’î whose usage of praise and satire is extreme is known forhis mastership in using rhythm and rhyme in his poems. While attaching importance to meaning and utterance he tried to use a new language and accomplished that to a great degree. His knowledge of Persian Language and Literature played a considerable role.A lot has been written so far about Nef’î and a great many research exists about his works too. However it is obvious that there will be many works about Nef’î, a productive poet. In this study a classification of Nef’î’s works and scientific studies about him and his works will be presented. Our research focuses to illustrate which part of his works is the center of modern researches and which parts are not. In addition, it is expected that our research will provided useful information to researchers studying Nef’î as a guide for sources regarding him. On yedinci yüzyılın ilk yarısında yaşamış olan Nef’î, Erzurum’un Hasankale ilçesinde doğmuştur. Asıl adı Ömer olan şair, oldukça mücadele dolu bir hayat geçirmiş ve bu hayata aynı zamanda önemli denilebilecek eserler de sığdırabilmeyi başarmıştır. Divan şiirinin önde gelen şairlerden biri olan Nef’î, adından hem yaşadığı dönemde hem de sonrasında çokça söz ettirmiştir. Nef’î’nin böyle bir şöhrete kavuşması onun edebi yeteneği ve kıvrak zekası yanında kaleminin keskin olmasından kaynaklanmaktadır. Övdüğünü çok iyi öven, yerdiğini de çok kötü bir şekilde yeren Nef

  7. Elma Suyunun Sıcak Teknikle Durultulması İçin Yeni bir Yöntem

    Directory of Open Access Journals (Sweden)

    Aziz Ekşi

    2015-02-01

    Full Text Available Elma suyunun konsantreye işlenmesinde üretim tekniği ve ekonomik açıdan önemli üstünlükleri olan yeni bir sıcak durultma tekniği tanımlanmıştır. Yeni bir amilaz ile pektin ve nişastanın 45-50 oC de parçalanması pektinazla ortaklaşa sağlanmaktadır. Bunu izleyen durultma işleminde de sıcaklık 45-50 oC de kalmaktadır. Bentonit, jelatin ve kieselsol katılması ile durulma sağlanmaktadır. Daha hızlı ve yeterli topaklaşma ve çökme işleme süresini kısaltmaktadır. Mikrobiyolojik bulaşma sakıncası da, durultma sıcaklığının 45-50 oC olması ile azalmış olmaktadır.

  8. Nuclear reactor

    International Nuclear Information System (INIS)

    Schabert, H.P.; Weber, R.; Bauer, A.

    1975-01-01

    The refuelling of a PWR power reactor of about 1,200 MWe is performed by a transport pipe in the containment leading from an external to an internal fuel pit. A wagon to transport the fuel elements can go from a vertical loading position to an also vertical deloading position in the inner fuel pit via guide rollers. The necessary horizontal movement is effected by means of a cable line through the transport pipe which is inclined at least 10 0 . Gravity thus helps in the movement to the deloading position. The cable line with winch is fastened outside the containment. Swivelling devices tip the wagon from the horizontal to the vertical position or vice versa. Loading and deloading are done laterally. (TK/LH) [de

  9. NEUTRONIC REACTOR

    Science.gov (United States)

    McGarry, R.J.

    1958-04-22

    Fluid-cooled nuclear reactors of the type that utilize finned uranium fuel elements disposed in coolant channels in a moderater are described. The coolant channels are provided with removable bushings composed of a non- fissionable material. The interior walls of the bushings have a plurality of spaced, longtudinal ribs separated by grooves which receive the fins on the fuel elements. The lands between the grooves are spaced from the fuel elements to form flow passages, and the size of the now passages progressively decreases as the dlstance from the center of the core increases for the purpose of producing a greater cooling effect at the center to maintain a uniform temperature throughout the core.

  10. Nuclear reactor

    International Nuclear Information System (INIS)

    Schweiger, F.; Glahe, E.

    1976-01-01

    In a nuclear reactor of the kind which is charged with spherical reaction elements and in which control rods are arranged to be thrust directly into the charge, each control rod has at least one screw thread on its external surface so that as the rod is thrust into the charge it is caused to rotate and thus make penetration easier. The length of each control rod may have two distinct portions, a latter portion which carries a screw thread and a lead-in portion which is shorter than the latter portion and which may carry a thread of greater pitch than that on the latter portion or may have a number of axially extending ribs instead of a thread

  11. Nuclear reactor neutron shielding

    Science.gov (United States)

    Speaker, Daniel P; Neeley, Gary W; Inman, James B

    2017-09-12

    A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

  12. Department of reactor technology

    International Nuclear Information System (INIS)

    1980-01-01

    The activities of the Department of Reactor Technology at Risoe during 1979 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

  13. Survey of research reactors

    International Nuclear Information System (INIS)

    Boek, H.; Villa, M.

    2004-06-01

    A survey of reasearch reactors based on the IAEA Nuclear Research Reactor Data Base (RRDB) was done. This database includes information on 273 operating research reactors ranging in power from zero to several hundred MW. From these 273 operating research reactors 205 reactors have a power level below 5 MW, the remaining 68 reactors range from 5 MW up to several 100 MW thermal power. The major reactor types with common design are: Siemens Unterrichtsreaktors, 1.2 Argonaut reactors, Slowpoke reactors, the miniature neutron source reactors, TRIGA reactors, material testing reactors and high flux reactors. Technical data such as: power, fuel material, fuel type, enrichment, maximum neutron flux density and experimental facilities for each reactor type as well as a description of their utilization in physics and chemistry, medicine and biology, academic research and teaching, training purposes (students and physicists, operating personnel), industrial application (neutron radiography, silicon neutron transmutation doping facilities) are provided. The geographically distribution of these reactors is also shown. As conclusions the author discussed the advantages (low capital cost, low operating cost, low burn up, simple to operate, safe, less restrictive containment and sitting requirements, versatility) and disadvantages (lower sensitivity for NAA, limited radioisotope production, limited use of neutron beams, limited access to the core, licensing) of low power research reactors. 24 figs., refs. 15, Tab. 1 (nevyjel)

  14. FBR type reactor

    International Nuclear Information System (INIS)

    Kimura, Kimitaka; Fukuie, Ken; Iijima, Tooru; Shimpo, Masakazu.

    1994-01-01

    In an FBR type reactor for exchanging fuels by pulling up reactor core upper mechanisms, a connection mechanism is disposed for connecting the top of the reactor core and the lower end of the reactor core upper mechanisms. In addition, a cylindrical body is disposed surrounding the reactor core upper mechanisms, and a support member is disposed to the cylindrical body for supporting an intermediate portion of the reactor core upper mechanisms. Then, the lower end of the reactor core upper mechanisms is connected to the top of the reactor core. Same displacements are caused to both of them upon occurrence of earthquakes and, as a result, it is possible to eliminate mutual horizontal displacement between a control rod guide hole of the reactor core upper mechanisms and a control rod insertion hole of the reactor core. In addition, since the intermediate portion of the reactor core upper mechanisms is supported by the support member disposed to the cylindrical body surrounding the reactor core upper mechanisms, deformation caused to the lower end of the reactor core upper mechanisms is reduced, so that the mutual horizontal displacement with respect to the control rod insertion hole of the reactor core can be reduced. As a result, performance of control rod insertion upon occurrence of the earthquakes is improved, so that reactor shutdown is conducted more reliably to improve reactor safety. (N.H.)

  15. Partiklid jah, jaa ning jajaa naaberpaari järelliikmena müügiläbirääkimistes / Riina Kasterpalu

    Index Scriptorium Estoniae

    Kasterpalu, Riina

    2005-01-01

    Vastavate partiklite funktsionaalsetest ülesannetest, kasutamisest ja tähendustest müügivestlustes telefoni teel peetud müügiläbirääkimisi analüüsides. Järgneb: Keel ja Kirjandus, 2005, nr. 12

  16. Zamanın Bir Başlangıcı Olmalı mıdır?

    Directory of Open Access Journals (Sweden)

    Zikri Yavuz

    2015-12-01

    Full Text Available Bu makalede, zamanın bir başlangıcı olup olmadığını tartışacağım. Büyük patlama modeline göre, evrenimiz sonsuz bir şekilde geçmişe sahip değildir. Bu, muhtemelen modern kozmolojinin en görkemli keşiflerinden birisidir. Buna rağmen bazı filozoflar zamanın zorunlu olarak bir başlangıcının olmadığını iddia etmektedirler. Büyük patlamanın âlemin zamansal bir başlangıcı olduğu görüşünü desteklediğini ileri süreceğim. Aynı zamanda zamanın başlangıcı olmadığına dair a priori argümanların da başarılı olmadığını göstermeyi deneyeceğim.

  17. Ankara Üniversitesi Kriz Merkezine başvuran yas olguları üzerine bir çalışma

    OpenAIRE

    ŞENELMİŞ, Halil

    2006-01-01

    Ankara Üniversitesi Kriz Merkezi'ne BaşvuranYas Olguları Üzerine Bir ÇalışmaSosyal bir varlık olan insan yaşam süreci içerisinde zorlayıcı, yıpratıcı, tehdit edicibirçok olay ve sorunla karşılaşır. Her zaman sorunlar karşısında kullandığı çözüm yollarınınişe yaramadığını gören kişi, kendisini çaresiz hisseder. Bu yaşanan bir kriz durumudur. Krizçeşitli duygusal zorlanmalar sonunda meydana gelen akut ve süresi sınırlı bir dengebozukluğudur.Kişinin yaşamı boyunca karşılaştı...

  18. Sr and Pb isotopic composition of five USGS glasses (BHVO-2G, BIR-1G, BCR-2G, TB-1G, NKT-1G)

    NARCIS (Netherlands)

    Elburg, M.A.; Vroon, P.Z.; van der Wagt, R.A.C.A.; Tchalikian, A.

    2005-01-01

    Sr isotopic compositions and Rb/Sr ratios of three USGS glasses (BHVO-2G, BIR-1G, BCR-2G) are identical to those of the original USGS reference materials. NKT-1G and TB-1G give values of 0.70351 and 0.70558, respectively. Pb isotopic ratios were measured by the standard-sample bracketing technique

  19. Fast breeder reactors

    International Nuclear Information System (INIS)

    Heinzel, V.

    1975-01-01

    The author gives a survey of 'fast breeder reactors'. In detail the process of breeding, the reasons for the development of fast breeders, the possible breeder reactors, the design criteria, fuels, cladding, coolant, and safety aspects are reported on. Design data of some experimental reactors already in operation are summarized in stabular form. 300 MWe Prototype-Reactors SNR-300 and PFR are explained in detail and data of KWU helium-cooled fast breeder reactors are given. (HR) [de

  20. Determining Reactor Neutrino Flux

    OpenAIRE

    Cao, Jun

    2011-01-01

    Flux is an important source of uncertainties for a reactor neutrino experiment. It is determined from thermal power measurements, reactor core simulation, and knowledge of neutrino spectra of fuel isotopes. Past reactor neutrino experiments have determined the flux to (2-3)% precision. Precision measurements of mixing angle $\\theta_{13}$ by reactor neutrino experiments in the coming years will use near-far detector configurations. Most uncertainties from reactor will be canceled out. Understa...

  1. Nuclear reactor coolant channels

    International Nuclear Information System (INIS)

    Macbeth, R.V.

    1978-01-01

    A nuclear reactor coolant channel is described that is suitable for sub-cooled reactors as in pressurised water reactors as well as for bulk boiling, as in boiling water reactors and steam generating nuclear reactors. The arrangement aims to improve heat transfer between the fuel elements and the coolant. Full constructional details are given. See also other similar patents by the author. (U.K.)

  2. Nuclear reactor

    International Nuclear Information System (INIS)

    Irion, L.; Tautz, J.; Ulrych, G.

    1976-01-01

    This additional patent complements the arrangement of non-return valves to prevent loss of cooling water on fracture of external tubes in the main coolant circuit (according to PS 24 24 427.7) by ensuring that the easily movable valves only operate in case of a fault, but do not flutter in operation, because the direction of flow is not the same at each location where they are installed. The remedy for this undesirable effect consists of allocating 1 non-return valve unit with 5 to 10 valves to each (of several) ducts for the cooling water intake. These units are installed in the annular space between the reactor vessel and the pressure vessel below the inlet of the ducts. Due to flow guidance surfaces in the same space, the incoming cooling water is deflected downwards and as the guiding surfaces are closed at the sides, must pass parallel to the valves of the non-return valve unit. On fracture of the external cooling water inlet pipe concerned, all valves of this unit close due to reversal of flow on the outlet side. (TK) [de

  3. Reactor container

    International Nuclear Information System (INIS)

    Kagawa, Tatsuo; Yanai, Ryoichi.

    1976-01-01

    Object: To provide a reactor container which is free from water shock action or condensing vibrations and cannot be readily broken by a missile from a pump impeller, pipe whipping, steam jet reaction, etc., and which also quickly condenses issuing steam and possesses a large vibration-proof strength. Structure: A high pressure containment vessel accommodating a pressure container includes a plurality of pressurized water tanks arranged along its inner periphery, and a pneumatic valve is provided in a lower portion of each of these pressurized water tanks. If an accident occurs, vapor is caused to issue from the pressure container into the vessel. When a certain value is reached, the pneumatic valves are opened, whereby the gas within the pressurized water tanks causes pressurized water to flow through the pipe and be ejected from spray nozzles to cause condensation of water within the vessel. Further, water of a pool within the container is circulated to allow heat release to the outside. (Horiuchi, T.)

  4. Sakyamuni Buda'nın Tarihsel Kişiliği Ve Öğretisinin Yeni Bir Din Haline Geliş Süreci

    Directory of Open Access Journals (Sweden)

    Hüsamettin Karataş

    2013-06-01

    Full Text Available Sakyamuni Buda, Hindu kast sistemindeki yönetici sınıfa mensup bir prenstir. O, yaşadığı bir takım hayat tecrübelerinden hareketle, var olan anlayışların yetersiz olduğunu düşünerek kendi gerçeğinin peşine düşmüş tarihsel bir şahsiyettir. Sakyamuni Buda, çeşitli yollar deneyerek sonunda mutlak kurtuluşa erdiğini, yani aydınlandığını iddia eden bir din kurucusudur. Onun kurduğu dinî ve felsefi sistemin adı Budizm'dir. Budizm, ortaya çıktığı dönemdeki politeist yapıya, aşırı çileci veya hazcı ahlak ilkelerine, kurtuluş yolunun formalitelerine ve kast sistemine tepki göstermiştir. Bunun yanı sıra var olmaya çalıştığı bölgedeki dinlerin en belirgin özelliklerini de bünyesinde barındırmış, bazı öğreti ve uygulamaları aynen sürdürmüş, kültürel ve toplumsal hayata dair konularda ise devamlı surette esnek bir yol takip etmiştir. Budizm uzun tarihsel süreç içerisinde dünyanın çok farklı bölgelerine yayılmış ve günümüzün en çok taraftara sahip dinlerden biri haline gelmiştir

  5. Reactor Physics Training

    International Nuclear Information System (INIS)

    Baeten, P.

    2007-01-01

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

  6. Bir Yeşil İguana'da {İguana iguana) Saptanan Peritonitle Beraber Seyreden Oxyurid Enfestasyonu

    OpenAIRE

    KOENHEMSİ, Lora; ULUTAŞ ESATGİL, Meltem; BAYRAKAL, Alper; ERDOĞAN, Özge; GÖNÜL, Remzi

    2013-01-01

    ÖZETBu olgunun materyalini halsizlik ve iştahsızlık şikayeti ile kliniğimize getirilen 18 aylık bir iguana oluşturdu. Yapılan klinik muayene ve radyolojik incelemeler sonucunda toraks ve sölomda sıvı toplanması saptandı. Hastada yapılan aspirasyon biyopsisi sonucunda yapılan sitolojik incelemede peritonit olduğu tespit edildi. Diğer taraftan dışkısında mukus görülmesi şikayeti nedeniyle yapılan parazitolojik incelemede Pharyngodonidae ailesinden: Alaeuris sp. veya Ozolamius sp. cinslerinden h...

  7. Duchenne Müsküler Distrofi ve Gilbert"s Sendromu Birlikteliği: Bir Olgu Sunumu

    OpenAIRE

    İncecik, Faruk; Hergüner, Özlem M.; Mert, Gülen; Horoz, Özden; Altunbaşak, Şakir

    2014-01-01

    Gilbert"s sendromu konjuge olmayan hiperbilirubinemi ile karekterize bir hastalıktır. 5 yaşında erkek çocuğu hafif sarılık ile hastanemize getirildi. Hastanın karaciğer enzimleri ve kreatin fosfokinaz yüksekliği ile beraber ısrarcı unkonjuge hiperbilirubinemisi vardı. Normal hemoglobin ve retikülosit değerleri ile hemoliz dışlandı ve Gilbert"s sendromu tanısı konuldu. Kreatin kinaz değeri 15600 U/l idi ve distrofin geninde delesyon mevcuttu. Sonuç olarak hastaya Gilbert"s sendr...

  8. Orta Ölçekli Bir İşletmenin Enerji İzleme Sisteminin Tasarlanması

    Directory of Open Access Journals (Sweden)

    Erdal Irmak

    2012-02-01

    Full Text Available Bu uygulamada, orta ölçekli bir işletmenin gerçek zamanlı ve geçmişe yönelik enerji takibinin bilgisayar ara yüzünden izlenmesi gerçekleştirilmiştir. Enerjinin ölçülmesi için akım ve gerilim bilgilerini Programlanabilir Lojik Kontrolörün ( PLC algılayacağı seviyeye getiren bir kart tasarlanmıştır. Bu karttan alınan akım ve gerilim bilgileri, PLC'nin analog kanalları ile okunmaktadır. Sistemin güç katsayısının algılanması için, bir sıfır geçiş detektörü tasarlanmıştır. Sıfır geçiş detektöründen elde edilen sinyaller arasındaki zaman farkı FM 350-1 sayıcı modül kullanılarak ölçülmüştür. Alınan bilgiler, PLC tarafından RS485/RS232 dönüştürme protokolü kullanarak, bilgisayarın seri iletişim kanalı aracılığı ile veritabanına aktarılmaktadır. Elde edilen veriler, C# programlama dili kullanılarak tasarlanan bir arayüz ile anlık takip edilebilmektedir. Elde edilen veriler sürekli olarak kaydedilerek geçmişe yönelik enerji analizleri yapma olanağı sağlanmıştır. Böylece, istenildiğinde belirlenen zaman aralığında kullanılan aktif, reaktif ve görünür güçler gözlemlenebilmektedir. Geçmişe yönelik enerji izleme sistemi kullanılarak işletmelerin fazla enerji harcadığı zamanlar tespit edilebilmektedir. Böylece, yoğun çalışma saatleri enerjinin ucuz olduğu zamanlara kaydırılarak kullanılan enerjinin işletmeye olan maliyetinin azaltılması gibi olanaklar sağlanmaktadır.

  9. Pratique de l’extranéité dans l’écriture d’Abdelkébir Khatibi

    Directory of Open Access Journals (Sweden)

    Hassan Moustir

    2013-11-01

    Full Text Available Promoted to the rank of operational concept in writing, the notion of "foreign professional" means in both fictional and critical work of Abdelkébir Khatibi (1938-2009 this cosmopolitan otherness that reduces identity disparities and cultural differences. Late Khatibi’s fictions, including Un été à Stockholm (1990 and Féerie d’un mutant (2005 represent an ontological extraneous out with all cultural and identity anchors and discourse representations. Op-erating in a global space, and private of a fixed identity and separated cultural roots, the characters of these two fictions embody the thought of foreignness and border crossing practice, at the linguistic and the cultural levels. This fact grows to reflect on what would be writing and deterritorialized identity.

  10. The fast breeder reactor

    International Nuclear Information System (INIS)

    Collier, J.

    1990-01-01

    The arguments for and against the fast breeder reactor are debated. The case for the fast reactor is that the world energy demand will increase due to increasing population over the next forty years and that the damage to the global environment from burning fossil fuels which contribute to the greenhouse effect. Nuclear fission is the only large scale energy source which can achieve a cut in the use of carbon based fuels although energy conservation and renewable sources will also be important. Fast reactors produce more energy from uranium than other types of (thermal) reactors such as AGRs and PWRs. Fast reactors would be important from about 2020 onwards especially as by then many thermal reactors will need to be replaced. Fast reactors are also safer than normal reactors. The arguments against fast reactors are largely economic. The cost, especially the capital cost is very high. The viability of the technology is also questioned. (UK)

  11. Sezai Karakoç'un Bir Sorusu Üzerine On A Question Of Sezai Karakoç

    Directory of Open Access Journals (Sweden)

    Fırat CANER

    2013-07-01

    Full Text Available The voice in Sezai Karakoç’s Hızırla Kırk Saat says that he learned how to break the idols made of rocks from Abraham, but he doesn’t know how to destroy the idols made of words. This voice constitutes a typical 20th century philosopher concerned with pornography. Those philosophers who live in the age of images, and whose minds areblurred by the excessive bombardment of images, generally act as ifthey were iconaclasts in the age of Byzantium. Philosophers and literarywriters of our age are hopeless because of the pornographic patternswhich determine our lives. This hopelessness is driven by volontarismwhen they speak about the future, and/but by determinism when theyspeak about the past. But we should take the historical necessities intoaccount when what’s at stake is a consideration of the future. Thencewe can foresee that pornography will lose its effect on our lives becauseof the historical necessities. As a result of the coexistence of thousandsof images, no image can sufficiently satisfy or provoke the eye. That’swhy iconaclasts are not different from romantic revolutionists whohopefully dream that they can change the world in a moment.Consequently we can say that satisfying the eye is a stage within theprocess of images’ losing their effect on out minds. Sezai Karakoç’un Hızırla Kırk Saat adlı eserindeki ses, mermer putları nasıl devireceğini Hz. İbrahim’den öğrendiğini, buna karşılık, nesnesi olmayan putları, örneğin sözlerle, yani zihinlerde inşa edilen putları nasıl devireceğini bilmediğini, bunu kimsenin öğretmediğini söyler. Sözlerle inşa edilen putların nasıl kırılacağını bilmediğini söyleyen ses, pornografi hakkında yazan tipik bir 20. yüzyıl düşünürü sesidir. İmaj çağının imaj bombardımanı altında zihni bulanan bu düşünürler, genel olarak, Bizans tarihindeki put kırıcıların tavrını benimsemişlerdir. Günümüz felsefe ve edebiyatının günlük ya

  12. Safeguarding research reactors

    International Nuclear Information System (INIS)

    Powers, J.A.

    1983-03-01

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  13. Nuclear reactor instrumentation at research reactor renewal

    International Nuclear Information System (INIS)

    Baers, B.; Pellionisz, P.

    1981-10-01

    The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

  14. Reactor Physics Programme

    International Nuclear Information System (INIS)

    De Raedt, C.

    2000-01-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

  15. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

  16. Endüstriyel İşletmelerde Franchising Model Önerisi: Hazır Beton Sektöründe Bir Uygulama

    Directory of Open Access Journals (Sweden)

    İpek Kazançoğlu

    2016-12-01

    Full Text Available Endüstriyel pazarda faaliyet gösteren firmaların daha hızlı büyüyerek, yeni pazarlara açılmasında franchising sistemi bir yeni bir satış, dağıtım kanalı olarak değerlendirilmektedir. Bu araştırmada amaç,  hazır beton sektöründe faaliyet gösteren bir firmanın franchising sistemini bir iş modeli olarak benimseme kararında dikkat etmesi gereken unsurları ve karşılaşılan zorlukları incelemektedir. Örnek olay çalışması olarak ele alınan çalışmada,  BATIBETON A.Ş. firmasının yedi yöneticiyle BATIBETON markasının franchising uygulamalarına ilişkin görüşlerini öğrenmek amacıyla derinlemesine görüşmeler yapılmıştır. Bu görüşmeler sonucunda, franchising sisteminin hazır beton sektöründe bir model önerisi olarak uygulanıp/uygulanmayacağı değerlendirilmiştir. Yapılan görüşmelerden elde edilen bulguların diğer endüstriyel işletmeler içinde geliştirilebilecek bir franchising iş modeli kararında etkili olabilecek faktörlerin anlaşılması yönünden uygulamaya katkı sağlayacağı düşünülmektedir.

  17. Research reactor instrumentation

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2001-02-01

    This is a textbook on research reactor instrumentation for training purposes, it gives a survey on research reactor instrumentation requirements and eight exercises covering the major aspects of this topic are presented. (author)

  18. Nuclear reactors; graphical symbols

    International Nuclear Information System (INIS)

    1987-11-01

    This standard contains graphical symbols that reveal the type of nuclear reactor and is used to design graphical and technical presentations. Distinguishing features for nuclear reactors are laid down in graphical symbols. (orig.) [de

  19. Hybrid plasmachemical reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lelevkin, V. M., E-mail: lelevkin44@mail.ru; Smirnova, Yu. G.; Tokarev, A. V. [Kyrgyz-Russian Slavic University (Kyrgyzstan)

    2015-04-15

    A hybrid plasmachemical reactor on the basis of a dielectric barrier discharge in a transformer is developed. The characteristics of the reactor as functions of the dielectric barrier discharge parameters are determined.

  20. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    Fribourg, Ch.

    2002-01-01

    This paper takes the state of the art on ship propulsion reactors technology. The french research programs with the corresponding technological stakes, the reactors specifications and advantages are detailed. (A.L.B.)

  1. Fusion reactor design studies

    International Nuclear Information System (INIS)

    Emmert, G.A.; Kulcinski, G.L.; Santarius, J.F.

    1990-01-01

    This report discusses the following topics on the ARIES tokamak: systems; plasma power balance; impurity control and fusion ash removal; fusion product ripple loss; energy conversion; reactor fueling; first wall design; shield design; reactor safety; and fuel cost and resources

  2. Reactor shutdown method

    International Nuclear Information System (INIS)

    Nishino, Yoshitaka; Sawa, Toshio; Matsumoto, Takayuki; Osumi, Katsumi; Usui, Naoshi.

    1991-01-01

    A device for injecting a hydrogen gas, a chelating agent or a reducing agent is disposed in a reactor water recycling system. Upon reactor shutdown, the hydrogen gas, the chelating agent or the reducing agent is injected to primary coolants. With such a procedure, radioactive ions formed by the dissolution of oxide layers at the surface of pipelines and equipments in a reactor water recycling system and a reactor water cleanup system are removed from the primary coolants by a reactor water cleanup device. Accordingly, since the dose rate at the surface of the pipelines can be reduced, the operator's radiation dose can be reduced upon periodical inspection for a power plant. Further, the inner pressure of the reactor is kept higher than the saturated steam pressure at the reactor water temperature to suppress boiling of the reactor water. This can suppress the peeling of cruds deposited to the surface of the fuel cladding tube. (I.N.)

  3. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    Edwards, R.M.; Power, M.A.; Bryan, M.

    1992-01-01

    A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

  4. Reactor System Design

    International Nuclear Information System (INIS)

    Chi, S. K.; Kim, G. K.; Yeo, J. W.

    2006-08-01

    SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

  5. İbn Haldun'un mukaddimequot123sinde toplumun yasalarını keşfeden bir düşünce etkinliği olarak tarih

    OpenAIRE

    KARACA, Çağlar

    2011-01-01

    ÖZET Bu çalıĢmada, Ġbn Haldun‟un tarih anlayıĢı ve toplumun yasalarını keĢfeden bir tarih bilimine katkısı incelenmiĢtir. Ġbn Haldun, kendinden sonraki birçok tarih görüĢüne esin kaynağı olmuĢtur. Ancak onun ününün yanında, Mukaddime‟deki fikirlerin ve tarihsel etkinliğin kuramsal bir değerlendirmesi sönük kalmıĢtır. Ġbn Haldun, kurucusu olduğu umran biliminde tarihsel zorunlulukları, toplumun hal ve tavırlarını keĢfetmeyi amaçlamaktadır. Bir Ġslam bilgini olarak, Aristoteles‟ten et...

  6. Orta Asya ve Kafkasya’da Nükleer Enerji Açısından Türkiye’nin Mali Beklenti ve Riskleri: Praksiyolojik Bir İnceleme

    OpenAIRE

    Bahçe, Abdullah; Gümüş, Öner

    2016-01-01

     ÖzNükleer enerji birçok ülkenin birbirine karşı üstünlük sağlamada kullanabildikleri bir araçtır. Bunun temel sebebi de nükleer enerjinin ekonomik ve mali getiri sağlayarak ülkelerin kalkınmalarını etkileyebilecek bir potansiyele sahip olmasıdır. Bu yönüyle nükleer enerji, verginin doğmasına neden olacak bir etkiye de sahiptir. Türkiye’de ise nükleer enerji üretilememektedir. Bununla birlikte diğer enerji çeşitlerinin üretimi söz konusudur ve bu enerji çeşitlerinden üretilen mal ve hizmetler...

  7. Nuclear reactor shutdown system

    International Nuclear Information System (INIS)

    Mangus, J.D.; Cooper, M.H.

    1982-01-01

    An improved nuclear reactor shutdown system is described comprising a temperature sensitive device connected to control the electric power supply to a magnetic latch holding a body of a neutron absorbing material. The temperature sensitive device is exposed to the reactor coolant so that when the reactor coolant temperature rises above a specific level, the temperature sensitive device will cause deenergization of the magnetic latch to allow the body of neutron absorbing material to enter the reactor core. (author)

  8. 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)

  9. On Yedinci Yüzyıldan Bir Kırkambar: Baldırzâde Ailesine Ait Bir Mecmua A Kırkambar from the Seventieth Century: A Mecmua of the Baldırzâde Family

    Directory of Open Access Journals (Sweden)

    Fatma BÜYÜKKARCI YILMAZ

    2013-03-01

    gives details concerning the content of the mecmua andpresents Tâcîzâde Cafer Çelebi’s work, provides information on Selisî ŞeyhMehmed Efendi and his family, including their personal notes such as thedates of birth and death of the family members. The article also focuses onthe subjects that were of interest to the members of the Baldırzâde family, bystudying the content of the mecmua. Tokatlı bir ailenin oğlu olan Baldırzâde Selisî Şeyh Mehmed Efendi’nin dedesi Ali, gençliğinde Bursa’ya yerleşmiş, oğlu Mevlânâ Mustafa farklı ilim merkezlerinde eğitimini başarıyla tamamlamış, Bursa’ya dönmüş, hatip ve imamlık yapmıştır. Mevlânâ Mustafa’nın oğlu, Baldırzâde Selisî Şeyh Mehmed Efendi de Bursa’da, İstanbul’da, Mekke’de müderrislik, kadılık gibi çeşitli görevlerde bulunmuş, çok sayıda telif eser bırakarak 1060/1650’de Bursa’da vefat etmiştir. Oğlu Derviş Mehmed Efendi, babası gibi bir süre Bursa’da müderrislik yapmış, kadı olarak Konya, Trablusşam ve Kayseri’de görev almış, felç geçirdiği için emekli olmuş, 1079/1668’te Bursa’da vefat etmiştir. Derviş Mehmed Efendi’nin terekesine göre pek çok kitabı vardır. Ölümünün ardından kitapların bir kısmı Ulucami’de satılmıştır. Baldırzâde ailesine ait olan mecmuanın, bu satış sonucu ailenin elinden çıkmış olabileceği düşünülmektedir.Mecmualar, bir bakıma çeşitli notlar ve suretlerin yer aldığı kişisel defterlerdir. Baldırzâdelere ait bu mecmuada da kişisel ve mesleki kullanım amacıyla kaydedilen fetvalar, vakıf suretleri gibi bazı belgelerle birlikte şiirler, dualar, dini, tasavvufi metinler ve alıntılar ile bazı risaleler/eserler mevcuttur. Bu mecmua örneğinden, mecmuanın içeriğinden yola çıkarak Osmanlı kültür dünyasını kavramak, tarihsel ve kültürel odaklı incelemeler için faydalanmak, hazırlayıcısının okuma pratiğini ortaya koymak imkânı vardır. Bazen

  10. Reactor power measuring device

    International Nuclear Information System (INIS)

    Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

    1993-01-01

    The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

  11. 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)

  12. Towards nuclear fusion reactors

    International Nuclear Information System (INIS)

    1993-11-01

    The results of nuclear fusion researches in JAERI are summarized. In this report, following themes are collected: the concept of fusion reactor (including ITER), fusion reactor safety, plasma confinement, fusion reactor equipment, and so on. Includes glossary. (J.P.N.)

  13. Refuelling nuclear reactors

    International Nuclear Information System (INIS)

    Stacey, J.; Webb, J.; White, W.P.; McLaren, N.H.

    1981-01-01

    An improved nuclear reactor refuelling machine is described which can be left in the reactor vault to reduce the off-load refuelling time for the reactor. The system comprises a gripper device rangeable within a tubular chute, the gripper device being movable by a pantograph. (U.K.)

  14. The Jules Horowitz reactor

    International Nuclear Information System (INIS)

    2003-01-01

    The Jules Horowitz reactor is the future european reactor for irradiation. It will be used for materials and new fuels irradiation. Experiments for the safety and the validation of neutronics calculation will be also realized. This paper presents the design and the performance of the reactor and the schedule of the remaining design studies. (A.L.B.)

  15. Sanat Yapıtı Sergileme ve Sunum Çeşitlerine Örnekler Eşliğinde Bir Bakış

    OpenAIRE

    AYAN ERGEN, Burcu

    2014-01-01

    Sergi, sahip olunanları gerek göstermek gerekse ticaret amacıyla başkalarına sunmak için oluşturulan bir düzendir. Sergilemek eski kullanımıyla teşhir etmek anlamına gelir. Sergileme ve sunum yöntemleri, gereksinimlerin ve teknolojinin zaman içinde geçirdiği evrime bağlı olarak sürekli değişen ve yenilenen bir biçim alır. Günümüzde müze ve galerilerde sergileme çeşitleri üzerinde durulacak ve sergilerin oluşturulma düşüncesi ile nasıl oluşturulduğunun inceleneceği bu bildiride, örnekler üzeri...

  16. Depremde Zemin Davranısının Kestiriminde Yeni Bir Yöntem: Ankara Kenti Batı Kesimindeki Jeolojik Birimlere Uygulanması

    OpenAIRE

    BAŞOKUR, Ahmet Tuğrul

    2009-01-01

    Proje alanı, Ankara il merkezinde Etimesgut, Çuğlu, Macunköy ve Çukurambar sınırlarınıkapsar. Proje alanının hemen hemen tümünde, Ankara çayı yatağında depolanmış olanKuvaterner yaşlı alüvyonlar ile gölsel Üst Pliyosen çökelleri bulunmaktadır. Gerek bu birimlerinjeoteknik özelliklerini incelemek gerekse bölgenin depremselliğini tanımlamak ve zeminlerindinamik davranışlarını ortaya koymak amacıyla farklı disiplinlerin bir arada yer aldığı çok yönlübir araştırma gerçekleştirilmiştir.Bölgede dep...

  17. Geleneksel ve Elektronik Ağızdan Ağıza İletişim Yöntemlerine Genel Bir Bakış

    OpenAIRE

    Demirbaş, Esra

    2018-01-01

    Ağızdan ağıza iletişim (WOM-word of mouth); tüketicilerin, bir ürün, hizmet veya kurumlailgili çoğunlukla memnun kalmadıkları veya beğendikleri hususları diğer kişilere iletmek üzerekullandıkları resmi olmayan bir iletişim yoludur.Bazı özel ürün kategorilerinde ve özellikle de hizmet sektöründe, müşterilerin satın alım öncesiWOM’dan etkilenip karar verdikleri düşünülmektedir. Globalleşen ve gelişen iletişim teknolojilerineticesinde WOM’un gittikçe artan önemi ve kurumların performansını etkil...

  18. Dünden Bugüne Avrupa Güvenlik ve İşbirliği Teşkilatı

    OpenAIRE

    DEMİR, Sertif

    2015-01-01

    Soğuk Savaş döneminin diyalog ve işbirliği süreci olarak ortaya çıkan Avrupa Güvenlik ve İşbirliği Konferansı (AGİK), Helsinki Nihai Belgesi, Paris Şartı ve Avrupa Konvansiyonel Kuvvetler Anlaşması (AKKA) gibi önemli uluslararası belgelerin imzalanmasını sağlayarak Soğuk Savaş'ın bitirilmesine yardımcı olmuştur. 1990'larda Doğu Avrupa'da demokrasinin yerleştirilmesi ve kriz yönetimi konularında ağırlıklı olarak faaliyet gösteren AGİT, ABD'nin NATO'yu, Batı Avrupa ülke...

  19. Thorium fueled reactor

    Science.gov (United States)

    Sipaun, S.

    2017-01-01

    Current development in thorium fueled reactors shows that they can be designed to operate in the fast or thermal spectrum. The thorium/uranium fuel cycle converts fertile thorium-232 into fissile uranium-233, which fissions and releases energy. This paper analyses the characteristics of thorium fueled reactors and discusses the thermal reactor option. It is found that thorium fuel can be utilized in molten salt reactors through many configurations and designs. A balanced assessment on the feasibility of adopting one reactor technology versus another could lead to optimized benefits of having thorium resource.

  20. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

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

  1. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

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

  2. Fundamentals of reactor chemistry

    International Nuclear Information System (INIS)

    Akatsu, Eiko

    1981-12-01

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around the nuclear reactors. The curricula of the courses contain also the subject material of chemistry. With reference to the foreign curricula, a plan of educational subject material of chemistry in the Nuclear Engineering School of JAERI was considered, and the fundamental part of reactor chemistry was reviewed in this report. Since the students of the Nuclear Engineering School are not chemists, the knowledge necessary in and around the nuclear reactors was emphasized in order to familiarize the students with the reactor chemistry. The teaching experience of the fundamentals of reactor chemistry is also given. (author)

  3. Solid phase synthesis of Smac/DIABLO-derived peptides using a 'Safety-Catch' resin: identification of potent XIAP BIR3 antagonists.

    Science.gov (United States)

    Elsawy, Mohamed A; Martin, Lorraine; Tikhonova, Irina G; Walker, Brian

    2013-09-01

    The N-terminal sequence of the Smac/DIABLO protein is known to be involved in binding to the BIR3 domain of the anti-apoptotic proteins IAPs, antagonizing their action. Short peptides and peptide mimetics based on the first 4-residues of Smac/DIABLO have been demonstrated to re-sensitize resistant cancer cells, over-expressing IAPs, to apoptosis. Based on the well-defined structural basis for this interaction, a small focused library of C-terminal capped Smac/DIABLO-derived peptides was designed in silico using docking to the XIAP BIR3 domain. The top-ranked computational hits were conveniently synthesized employing Solid Phase Synthesis (SPS) on an alkane sulfonamide 'Safety-Catch' resin. This novel approach afforded the rapid synthesis of the target peptide library with high flexibility for the introduction of various C-terminal amide-capping groups. The library members were obtained in high yield (>65%) and purity (>85%), upon nucleophilic release from the activated resin by treatment with various amine nucleophiles. In vitro caspase-9 activity reconstitution assays of the peptides in the presence of the recombinant BIR3-domain of human XIAP (500nM) revealed N-methylalanyl-tertiarybutylglycinyl-4-(R)-phenoxyprolyl-N-biphenylmethyl carboxamide (11a) to be the most potent XIAP BIR3 antagonist of the series synthesized inducing 93% recovery of caspase-9 activity, when used at 1μM concentration. Compound (11a) also demonstrated moderate cytotoxicity against the breast cancer cell lines MDA-MB-231 and MCF-7, compared to the Smac/DIABLO-derived wild-type peptide sequences that were totally inactive in the same cell lines. Copyright © 2013 Elsevier Ltd. All rights reserved.

  4. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    2010-03-01

    While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO 2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPR TM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1 TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENA TM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENA TM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

  5. Spinning fluids reactor

    Science.gov (United States)

    Miller, Jan D; Hupka, Jan; Aranowski, Robert

    2012-11-20

    A spinning fluids reactor, includes a reactor body (24) having a circular cross-section and a fluid contactor screen (26) within the reactor body (24). The fluid contactor screen (26) having a plurality of apertures and a circular cross-section concentric with the reactor body (24) for a length thus forming an inner volume (28) bound by the fluid contactor screen (26) and an outer volume (30) bound by the reactor body (24) and the fluid contactor screen (26). A primary inlet (20) can be operatively connected to the reactor body (24) and can be configured to produce flow-through first spinning flow of a first fluid within the inner volume (28). A secondary inlet (22) can similarly be operatively connected to the reactor body (24) and can be configured to produce a second flow of a second fluid within the outer volume (30) which is optionally spinning.

  6. Reactor power monitoring device

    International Nuclear Information System (INIS)

    Dogen, Ayumi; Ozawa, Michihiro.

    1983-01-01

    Purpose: To significantly improve the working efficiency of a nuclear reactor by reflecting the control rod history effect on thermal variants required for the monitoring of the reactor operation. Constitution: An incore power distribution calculation section reads the incore neutron fluxes detected by neutron detectors disposed in the reactor to calculate the incore power distribution. A burnup degree distribution calculation section calculates the burnup degree distribution in the reactor based on the thus calculated incore power distribution. A control rod history date store device supplied with the burnup degree distribution renews the stored control rod history data based on the present control rod pattern and the burnup degree distribution. Then, thermal variants of the nuclear reactor are calculated based on the thus renewed control rod history data. Since the control rod history effect is reflected on the thermal variants required for the monitoring of the reactor operation, the working efficiency of the nuclear reactor can be improved significantly. (Seki, T.)

  7. Reactor power control device

    International Nuclear Information System (INIS)

    Ishii, Yoshihiko; Arita, Setsuo; Miyamoto, Yoshiyuki; Fukazawa, Yukihisa; Ishii, Kazuhiko

    1998-01-01

    The present invention provides a reactor power control device capable of enhancing an operation efficiency while keeping high reliability and safety in a BWR type nuclear power plant. Namely, the device of the present invention comprises (1) a means for inputting a set value of a generator power and a set value of a reactor power, (2) a means for controlling the reactor power to either smaller one of the reactor power corresponding to the set value of the generator power and the set value of the reactor power. With such procedures, even if the nuclear power plant is set so as to operate it to make the reactor power 100%, when the generator power reaches the upper limit, the reactor power is controlled with a preference given to the upper limit value of the generator power. Accordingly, safety and reliability are not deteriorated. The operation efficiency of the plant can be improved. (I.S.)

  8. One piece reactor removal

    International Nuclear Information System (INIS)

    Chia, Wei-Min; Wang, Song-Feng

    1993-01-01

    The strategy of Taiwan Research Reactor Renewal plan is to remove the old reactor block with One Piece Reactor Removal (OPRR) method for installing a new research reactor in original building. In this paper, the engineering design of each transportation works including the work method, the major equipments, the design policy and design criteria is described and discussed. In addition, to ensure the reactor block is safety transported for storage and to guarantee the integrity of reactor base mat is maintained for new reactor, operation safety is drawn special attention, particularly under seismic condition, to warrant safe operation of OPRR. ALARA principle and Below Regulatory Concern (BRC) practice were also incorporated in the planning to minimize the collective dose and the total amount of radioactive wastes. All these activities are introduced in this paper. (J.P.N.)

  9. Hayvan Islahında Güncel Bir Yaklaşım: CRISPR/Cas9 Genom Modifikasyon Sistemi

    Directory of Open Access Journals (Sweden)

    Fatih Bilgi

    2016-12-01

    Full Text Available Genom modifikasyonları, verimin arttırılmasında ve hastalıklara karşı direncin kazandırılması konusunda önemli avantajlar sağlama potansiyeli içermektedir. Bireyin zaten sahip olduğu bir genin susturulmasını ya da ifade edilmesini sağlayan gen düzenlenmesi yöntemleri (gene editing çevreyi en az etkileyerek genetik yapının geliştirilmesi konusunda önemli olanaklar sağlamaktadır. Son zamanlarda yeni genetik düzenleme yöntemleri geliştirilmiştir. Bunlar ZFN (Zinc Finger Nuclease’ler, TALEN (Transcription Activator-like Effector Nuclease’ler ve CRISPR/Cas nükleaz sistemleridir. CRISPR/Cas sistemi yabancı genetik materyalleri yok etmek için RNA güdümlü nükleazları kullanan bir mikrobiyal immün sistem olup, bu sistemin günümüzde hayvanlarda basit ve etkili bir gen düzenleme mekanizması olarak kullanılabilme potansiyeli değerlendirilmektedir. Bu derlemede CRISPR/Cas9 sistemi ve hayvan ıslahında kullanılabilirliği özetlenmiştir.

  10. Reactor coolant pump for a nuclear reactor

    International Nuclear Information System (INIS)

    Burkhardt, W.; Richter, G.

    1976-01-01

    The invention deals with disengaging the coupling of a reactor coolant pump of a nuclear reactor feeding pressurized coolant. The disengaging coupling has two parts joined by bolts, at least one of them containing a driving agent within a bore. This is provided with a speed-depending ignition device in such manner that, if the critical speed is reached, the driving charge is ignited and the coupling is disengaged by destroying the bolts. (UWI) [de

  11. Neutron fluxes in test reactors

    Energy Technology Data Exchange (ETDEWEB)

    Youinou, Gilles Jean-Michel [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-01-01

    Communicate the fact that high-power water-cooled test reactors such as the Advanced Test Reactor (ATR), the High Flux Isotope Reactor (HFIR) or the Jules Horowitz Reactor (JHR) cannot provide fast flux levels as high as sodium-cooled fast test reactors. The memo first presents some basics physics considerations about neutron fluxes in test reactors and then uses ATR, HFIR and JHR as an illustration of the performance of modern high-power water-cooled test reactors.

  12. Pleistocene Deposits in the Southern Egyptian Sahara: Lithostratigraphic Relationships of Sediments and Landscape Dynamics at Bir Tarfawi

    Directory of Open Access Journals (Sweden)

    Hill Christopher L.

    2017-06-01

    Full Text Available The sedimentological and lithostratigraphic record from north-central Bir Tarfawi documents the presence of Pleistocene basin-fill deposits. Three topographic basins were created as a result of deflation during climate episodes associated with lowering of the local groundwater table. In each case, the three deflational basins or topographic depressions were subsequently filled with sediments; these basin aggradations coincided with changes from arid climate conditions to wetter conditions and a rise in the groundwater table. The oldest and highest sedimentary remnant is associated with Acheulian artifacts and may reflect spring-fed pond and marsh conditions during a Middle Pleistocene wet climate episode. Lithofacies for a lower stratigraphic sequence (the “White Lake” documents deposition in a perennial lake that varied in extent and depth and is associated with Middle Paleolithic artifacts. A third episode of deflation created a topographic low that has been filled with Late Pleistocene sediments that are associated with Middle Paleolithic artifacts and fossil remains. Lateral and vertical variations in the lithofacies of this basin-fill sequence and the sediments of the “grey-green” lake phases provide a record of changing hydrologic conditions. These hydrologic conditions appear to reflect variations in water-table levels related to groundwater recharge and, at times, local rains.

  13. Bir Üniversitenin Ebelik Bölümü Öğrencilerinde Premenstrual Sendrom

    OpenAIRE

    DOĞAN YÜKSEKOL, Özlem

    2018-01-01

    Premenstruel sendrom en sık ergenlik döneminde görülen, genç kızların yaşamını, derslere devam etme durumunu, okul başarısını ve sosyal yaşamını olumsuz etkileyen bir sağlık sorunudur. Bu çalışma Elazığ Sağlık Yüksekokulu Ebelik bölümünde öğrenim gören öğrencilerin premenstruel semptomlarını belirlemek amacıyla yapılmıştır. Tanımlayıcı ve ilişki arayıcı nitelikteki çalışmanın evrenini 2010-2011 eğitim öğretim yılında Fırat Üniversitesi Elazığ Sağlık Yüksekokulu Ebelik bölümü 1., 2. ve 3.sınıf...

  14. Correlation of fine needle aspiration cytology with histopathology findings in cases of thyroid lesions in Bir Hospital

    Directory of Open Access Journals (Sweden)

    PB Thapa

    2014-01-01

    Full Text Available Aims: To correlate the findings of fine needle aspiration cytology (FNAC with the histopathology( HPE of the excised nodule or specimen and to assess the accuracy and efficacy of FNAC in the diagnosis of the thyroid nodules. Materials and methods: This is a prospective study conducted at the Department of Ear Nose Throat (ENT & Head & NecK Surgery( HNS, National Academy of Medical Sciences, Bir Hospital, Kathmandu from 2nd January 2009 to 29th December 2011. One hundred patients with thyroid nodule were included in the study. Results: Out of 100 patients 77 were females and 23 males. The age ranged from 11-60 years. Statistical analysis of results for Benign Thyroid lesion showed 98.6% sensitivity, 75 % specificity. Likewise, results for Malignant thyroid lesions showed 75 % sensitivity, 98.6 % specificity . Conclusion: FNAC has high accuracy in the diagnostic evaluation of thyroid lesions. Journal of College of Medical Sciences-Nepal, 2013, Vol-9, No-1, 23-29 DOI: http://dx.doi.org/10.3126/jcmsn.v9i1.9670

  15. Yeni Bir Armür Tahrik Mekanizmasının Tasarımı

    OpenAIRE

    CAN, Özgün; ABDULLA, Gabil

    2014-01-01

    Dokuma kumaşların üretilmesinde ağızlık açma işlemi oldukça önemlidir. Günümüzde, ağızlık açma işlemi için yüksek hızlı dokuma makinelerinde rotatif armürlü mekanizmalar kullanılmaktadır. Rotatif armürlerin temel özelliklerinden birisi makinenin ana miline tek yönlü beklemeli dönme hareketinin iletilmesidir. Böyle bir hareketin elde edilmesi için ileri teknoloji ve maliyet gerektirmektedir. Bu çalışmanın amacı, rotatif armürlerde armür miline 1800 açı altında çalışacak eşit zamanlı, beklem...

  16. Bir “Doğrudan Eylem Hareketi” Olarak Greenpeace (Yeşil Barış)

    OpenAIRE

    ARSLAN, Hüseyin

    2011-01-01

    Greenpeace çevresel bir sivil toplum örgütüdür ve ekolojik hareketlerden “Green Politics” içinde kabul edilmektedir. Greenpeace küresel ısınma, ormansızlaşma, aşırı avlanma, ticari balına avcılığı ve anti-nükleer sorunlar gibi konular üzerinde çalışmalarını yoğunlaştırmaktadır. Greenpeace amacına ulaşmak için “doğrudan eylem” yöntemini kullanmaktadır. Günümüzde Greenpeace örgütünün uluslararası idare merkezi Hollanda’nın Amsterdam şehrindedir. Uluslararası Greenpeace’in başkanlığını Kumi Naid...

  17. Bilinmeyen Bir Eser: Yümnî Divanı An Unknown Work: Yümnî’s Divan

    Directory of Open Access Journals (Sweden)

    Hakan SEVİNDİK

    2012-09-01

    gazelden oluşan bu küçük hacimli Divan’ın sahibi olması muhtemel Yümnî’ler hakkında eserin kendisi ve kaynaklardan yola çıkarak birtakım yorumlarda bulunuldu. İncelemelerimiz neticesinde Divan’ın sahibi Yümnî’nin 1604-1644 yılları arasında kaside ve gazeller kaleme alan IV. Murad devri şairi olduğu tespit edildi. Ayrıca söz konusu şairin Şeyhülislâm Yahyâ’ya övgü niteliğinde kaleme aldığı kaside ve gazellerden Şeyhülislâm’ın hayranı olduğu anlaşıldı. İkinci kısımda ise esere ait tek yazma nüshanın tavsifi yapılarak, Divan’ın şekil ve muhteva özelliklerine dair genel bir inceleme hazırlandı. Bu incelemeye göre eserde geçen manzumelerde Şeyhülislâm Yahyâ’nın Yümnî üzerinde geniş bir tesirinin olduğu ortaya çıktı. Özellikle gazellerinde bir aşk şairi olduğunu hissettiren Yümnî’nin bu yönüyle de Şeyhülislam Yahyâ’yı örnek aldığı görüldü. Makale boyunca, eserin sahibi Yümnî ile Şeyhülislâm Yahyâ arasındaki hem kişisel hem de sanatsal bağa değinildi. Yümnî Divanı’nın klasik Türk şiiri açısından üzerinde durulması gereken vasfı, Türk edebiyatında Şeyhülislâm Yahyâ’ya duyulan bağlılığı dile getiren örneklerden biri olmasıdır. Ayrıca eser, Şeyhülislâm Yahyâ takipçiliğinin edebiyatımızda ayrı bir şiir/üslup çizgisi olarak incelenmesi gerektiğini de yeniden hatırlatmıştır.

  18. Dolar/Euro Paritesinin Türkiye’nin İhracatına Etkisi: Ekonometrik Bir Analiz.

    OpenAIRE

    KARACA, Cem SAATCİOĞLU Orhan

    2010-01-01

    Türkiye ihracatını ağırlıklı olarak euro, ithalatını ağırlıklı olarak dolar ile yapmaktadır. Ayrıca ithalatının büyük bölümü hammaddelerden oluşurken ihracatında tüketim mallarının payı göreceli olarak daha fazladır. Böylece Türkiye dolar ile ithal ettiği hammaddeleri kullanarak ürettiği tüketim mallarını euro ile ihraç eden bir ülke konumundadır. Dış ticaretteki bu yapı dolar/euro paritesindeki değişmelerin Türkiye’nin ihracatını reel olarak etkilemesini gündeme getirmektedir. Euronun dolar ...

  19. Macaristan Türkolojisi Üzerine Bir Biyo-Biyografi Denemesi An Attempt At A Bioagrapy of Hungarian Turkology

    Directory of Open Access Journals (Sweden)

    Mehmet GÜMÜŞKILIÇ

    2012-12-01

    Full Text Available Hungary is the place where Turcology studies started in modern terms. For many years Hungarian scientists have been engaged in Turkish studies- as a part of their research of their own roots -. Theyhad great contribution to Turkish language, history, literature,geography, ethnography and music. It may also be supposed thatTurkish Hungarian relations were better than now. However, todayTurkish Hungarian relations have been enjoying a revival again.Considering the closeness of Hungarians and Turks, it is obvious thatthe two nations share some responsibilities in improving their relations.In this article, after organizing the names of all the HungarianTurcologs who have conducted studies on Turks after the foundation ofmodern Turcology in alphabetical order, their articles on Turcologyfromoldest to newest will be presented as well as their career lives.Also the lists of some of the studies on some of the Turcologs will begiven. The Hungarian scientists and their studies mentioned in thisarticle do not encompass all of them. If we include other articles, books,presentations, credits, reviews and the studies of other scientists thatwe haven’t been able to mention here, the number will swell and gobeyond the limits of this article. In the future, we hope that furtherdetailed studies will be conducted on Hungarian Turcology. Through anattempt at biyo biography, we have tried to touch briefly on theimportance Hungarians give to Turks.Undoubtedly in the future, Turkish Hungarian relations andfriendship will further improve with the help of further detailed studies.This article will serve its purpose if we have a tiny contribution. Modern anlamda Türkoloji çalışmalarının başladığı yer Macaristan’dır. Macar bilim adamları yıllar boyu -bir bakıma kendi köklerini de arama çabaları sebebiyle- Türklük bilimiyle uğraştılar. Türk diline, tarihine, kültürüne, edebiyatına, coğrafyasına, etnoğrafyasına, musikîsine b

  20. Huzursuzlukla Yuvaya Dönüş: Fatih-Harbiye Ve Bir Tereddüdün Romanı’nda Aşılamayan Kriz

    Directory of Open Access Journals (Sweden)

    Jale Özata Dirlikyapan

    2017-12-01

    Full Text Available Döneminin en önemli romancı ve düşünce adamlarından biri olan Peyami Safa (1899-1961, hemen her devride romanları üzerine düşünülen ve söz söylenen bir yazar olmuştur. Özellikle ilk dönem romanlarının şematik yapısından sıkça söz edilmiş ve bu romanlar çoğunlukla “ulusal alegori” düşüncesi etrafında değerlendirilmişlerdir. Fatih-Harbiye ve Bir Tereddüdün Romanı kitaplarındaki kadın-erkek ilişkileri çoğunlukla bir medeniyet krizinin görünümleri olarak ele alınmış, romanlardaki bazı önemli detaylar görmezden gelinebilmiştir. Her iki romanın sonunda da Batıyı temsil eden değerler savuşturulmuş gibi görünse de, aslında romanlar bir tür bezginlik, boşvermişlik ve huzursuzlukla son bulur. Peyami Safa genelde söylendiği gibi dişil, irrasyonel, kozmopolit unsurları bünyesinden kovmayı arzular görünse de, tam da dişil, irrasyonel veya “vahşi ölçüde samimi” olanın alanındayken kısmen daha özgür bir bilinçle nitelikli edebiyat yapıyordur. Birbirine sıkı sıkıya bağlı olan bu unsurlar, yazarın “milli ideal” etrafında ördüğü kürsü konuşmaları tarafından gizlenmeye, baskılanmaya çalışılsa da, bunları ele alışı sayesinde Peyami Safa’daki “büyük romancı” kendini gösterebilmiştir

  1. Thai research reactor

    International Nuclear Information System (INIS)

    Aramrattana, M.

    1987-01-01

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

  2. İletişim Çalışmalarında Yeni Bir Mecra: Finansal İletişim

    Directory of Open Access Journals (Sweden)

    Gökhan Gökgöz

    2013-09-01

    Full Text Available 1970’li yıllar toplumsal ve politik tarih açısından önemli bir uğrağı temsil eder. Bu yılların başında yaşanan kriz, ekonominin işleyiş süreçlerini, devletin yapısını ve toplumsal alanın tasavvur edilme biçimini büyük ölçüde değiştirmiştir. Bu dönemde, finansal sermaye, kapitalizm içerisinde bir hegemonik lider olarak ön plana çıkmış; devlet, bir yandan üretimin çekirdeğinden uzak bir yerde konumlandırılırken diğer yandan paranın dolaşım kanallarının rehabilitasyonu işine odaklanmış; insana ilişkin değerler, kültürel mefhumlar ve toplumsal pratikler ise birer değişken olarak ekonomi-politikanın merkezine taşınmıştır. Kültür ile ekonomi arasındaki geleneksel ilişki bozulmuş; bir ekonomi-politikanın başarısı, toplumsal aktörlere temas etme kabiliyeti ile paralel hale gelmiştir. Finansallaşma sürecinde bu temas, iletişim politikaları vasıtasıyla sağlanır; ekonomi-politika ve bundan sorumlu merkezi kurumlarla toplumsal alan arasındaki bağ, iletişim stratejileri üzerinden kurulur; ekonomik alan ile kültürel alan arasındaki boşluk, iletişim kanalları içerisinden taşınan enformasyon marifetiyle doldurulur; insana ilişkin öngörülemezlikler, iletişim süreçleri vasıtasıyla öngörülebilir kılınır. Bu çalışmada, iletişim çalışmaları içerisinde yeni bir mecra olarak çağrılan “finansal iletişim”in farklı temas noktalarına işaret edilecek ve her bir uğrağın finansal iletişim alanına bağlandığı nokta, modeller üzerinden gösterilecektir. 

  3. Hybrid reactors. [Fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Moir, R.W.

    1980-09-09

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

  4. Fast Spectrum Reactors

    CERN Document Server

    Todd, Donald; Tsvetkov, Pavel

    2012-01-01

    Fast Spectrum Reactors presents a detailed overview of world-wide technology contributing to the development of fast spectrum reactors. With a unique focus on the capabilities of fast spectrum reactors to address nuclear waste transmutation issues, in addition to the well-known capabilities of breeding new fuel, this volume describes how fast spectrum reactors contribute to the wide application of nuclear power systems to serve the global nuclear renaissance while minimizing nuclear proliferation concerns. Readers will find an introduction to the sustainable development of nuclear energy and the role of fast reactors, in addition to an economic analysis of nuclear reactors. A section devoted to neutronics offers the current trends in nuclear design, such as performance parameters and the optimization of advanced power systems. The latest findings on fuel management, partitioning and transmutation include the physics, efficiency and strategies of transmutation, homogeneous and heterogeneous recycling, in addit...

  5. 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

  6. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Matsuura, Shojiro; Nakahara, Yasuaki; Takano, Hideki

    1982-09-01

    Research and development activities in the Division of Reactor Engineering in fiscal 1981 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

  7. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1985-08-01

    Research and development activities in the Department of Reactor Engineering in fiscal 1984 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, safeguards technology, and activities of the Committee on Reactor Physics. (author)

  8. Spectral shift reactor control method

    International Nuclear Information System (INIS)

    Impink, A.J. Jr.

    1981-01-01

    A method of operating a nuclear reactor having a core and coolant displacer elements arranged in the core wherein is established a reator coolant temperature set point at which it is desired to operate said reactor and first reactor coolant temperature band limits are provided within which said set point is located and it is desired to operate said reactor charactrized in that said reactor coolant displacer elements are moved relative to the reactor core for adjusting the volume of reactor coolant in said core as said reactor coolant temperature approaches said first band limits thereby to maintain said reactor coolant temperature near said set point and within said first band limits

  9. Seals in nuclear reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The aim of this invention is the provision of improved seals for reactor vessels in which fuel assemblies are located together with inlets and outlets for the circulation of a coolant. The object is to provide a seal arrangement for the rotatable plugs of nuclear reactor closure heads which has good sealing capacities over a wide gap during operation of the reactor but which also permits uninhibited rotation of the plugs for maintenance. (U.K.)

  10. Power reactors operational diagnosis

    International Nuclear Information System (INIS)

    Dach, K.; Pecinka, L.

    1976-01-01

    The definition of reactor operational diagnostics is presented and the fundamental trends of research are determined. The possible sources of power reactor malfunctions, the methods of defect detection, the data evaluation and the analysis of the results are discussed in detail. In view of scarcity of a theoretical basis and of insufficient in-core instrumentation, operational diagnostics cannot be as yet incorporated in a computer-aided reactor control system. (author)

  11. Pressurised water reactor operation

    International Nuclear Information System (INIS)

    Birnie, S.; Lamonby, J.K.

    1987-01-01

    The operation of a pressurized water reactor (PWR) is described with respect to the procedure for a unit start-up. The systems details and numerical data are for a four loop PWR station of the design proposed for Sizewell-'B', United Kingdom. A description is given of: the initial conditions, filling the reactor coolant system (RCS), heat-up and pressurisation of the RCS, secondary system preparations, reactor start-up, and reactivity control at power. (UK)

  12. Reactor BR2

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported

  13. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported.

  14. 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)

  15. The replacement research reactor

    International Nuclear Information System (INIS)

    Cameron, R.

    1999-01-01

    As a consequences of the government decision in September 1997. ANSTO established a replacement research reactor project to manage the procurement of the replacement reactor through the necessary approval, tendering and contract management stages This paper provides an update of the status of the project including the completion of the Environmental Impact Statement. Prequalification and Public Works Committee processes. The aims of the project, management organisation, reactor type and expected capabilities are also described

  16. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1988-01-01

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics. 3 refs., 4 figs., 1 tab

  17. New reactor concepts

    International Nuclear Information System (INIS)

    Meskens, G.; Govaerts, P.; Baugnet, J.-M.; Delbrassine, A.

    1998-11-01

    The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost

  18. Remote Reactor Monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Bernstein, Adam [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dazeley, Steve [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dobie, Doug [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Marleau, Peter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brennan, Jim [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gerling, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sumner, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sweany, Melinda [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-10-21

    The overall goal of the WATCHMAN project is to experimentally demonstrate the potential of water Cerenkov antineutrino detectors as a tool for remote monitoring of nuclear reactors. In particular, the project seeks to field a large prototype gadolinium-doped, water-based antineutrino detector to demonstrate sensitivity to a power reactor at ~10 kilometer standoff using a kiloton scale detector. The technology under development, when fully realized at large scale, could provide remote near-real-time information about reactor existence and operational status for small operating nuclear reactors out to distances of many hundreds of kilometers.

  19. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    Conceptual design studies were made of fusion reactors based on the three current mirror-confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fuel for fission reactors. We have designed a large commercial hybrid and a small pilot-plant hybrid based on standard mirror confinement. Tandem mirror designs include a commercial 1000-MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single-cell pilot plant

  20. Multi purpose research reactor

    International Nuclear Information System (INIS)

    Raina, V.K.; Sasidharan, K.; Sengupta, Samiran; Singh, Tej

    2006-01-01

    At present Dhruva and Cirus reactors provide the majority of research reactor based facilities to cater to the various needs of a vast pool of researchers in the field of material sciences, physics, chemistry, bio sciences, research and development work for nuclear power plants and production of radio isotopes. With a view to further consolidate and expand the scope of research and development in nuclear and allied sciences, a new 20 MWt multi purpose research reactor is being designed. This paper describes some of the design features and safety aspects of this reactor

  1. Trench reactor: an overview

    International Nuclear Information System (INIS)

    Spinrad, B.I.; Rohach, A.F.; Razzaque, M.M.; Sankoorikal, J.T.; Schmidt, R.S.; Lofshult, J.; Ramin, T.; Sokmen, N.; Lin, L.C.

    1988-01-01

    Recent fast, sodium-cooled reactor designs reflect new conditions. In nuclear energy these conditions are (a) emphasis on maintainability and operability, (b) design for more transparent safety, and (c) a surplus of uranium and enrichment availability that eases concerns about light water reactor fueling costs. In utility practice the demand is for less capital exposure, short construction time, smaller new unit sizes, and low capital cost. The PRISM, SAFR, and integral fast reactor (IFR) concepts are responses to these conditions. Fast reactors will not soon be deployed commercially, so more radical designs can be considered. The trench reactor is the product of such thinking. Its concepts are intended as contributions to the literature, which may be picked up by one of the existing programs or used in a new experimental project. The trench reactor is a thin-slab, pool-type reactor operated at very low power density and- for sodium-modest temperature. The thin slab is repeated in the sodium tank and the reactor core. The low power density permits a longer than conventional core height and a large-diameter fuel pin. Control is by borated steel slabs that can be lowered between the core and lateral sodium reflector. Shutdown is by semaphore slabs that can be swung into place just outside the control slabs. The paper presents major characteristics of the trench reactor that have been changed since the last report

  2. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2002-01-01

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed

  3. Nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1980-01-01

    A safety system for shutting down a nuclear reactor under overload conditions is described. The system includes a series of parallel-connected computer memory type look-up tables each of which receives data on a particular reactor parameter and in each of which a precalculated functional value for that parameter is stored indicative of the percentage of maximum reactor load that the parameter contributes. The various functional values corresponding to the actual measured parameters are added together to provide a control signal used to shut down the reactor under overload conditions. (U.K.)

  4. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Carlson, G.A.; Moir, R.W.

    1978-01-01

    We have carried out conceptual design studies of fusion reactors based on the three current mirror confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fission fuel for fission reactors. We have designed a large commercial hybrid based on standard mirror confinement, and also a small pilot plant hybrid. Tandem mirror designs include a commercial 1000 MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single cell pilot plant

  5. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    Frisch, E.; Andrews, H.N.

    1976-01-01

    A nuclear reactor internals arrangement is disclosed which facilitates reactor refueling. A reactor vessel and a nuclear core is utilized in conjunction with an upper core support arrangement having means for storing withdrawn control rods therein. The upper core support is mounted to the underside of the reactor vessel closure head so that upon withdrawal of the control rods into the upper core support, the closure head, the upper core support and the control rods are removed as a single unit thereby directly exposing the core for purposes of refueling

  6. Reactor core monitor for nuclear reactor

    International Nuclear Information System (INIS)

    Azekura, Kazuo; Kurihara, Kunitoshi.

    1992-01-01

    The device of the present invention provides a various information of a wide adaptability, such as a power distribution, to an operator by determining a reactor core performance of the reactor by a performance calculation with improved accuracy. That is, a calculation means determines a neutron flux distribution of the reactor and coolant temperature based on the neutron flux distribution. A measuring means measures a cooled temperature of a reactor core inlet and a temperature at the exit of a fuel assembly. The result of coolant temperature by the measuring means and the result of the calculation by the calculation means are compared. The result of the calculation for the neutron flux distribution obtained by the calculation means is corrected based on the result of the comparison. The calculation means introduces calculation at higher accuracy by adopting two-dimensional balance in the fuel assembly. Further, a more accurate three-dimensional neutron diffusion calculation model is introduced in an on-line computer. Then, the accuracy of the calculation for the neutron flux distribution, power distribution, temperature distribution, etc. is improved. In view of the above, adaptability of a reactor core monitor is widened. (I.S.)

  7. RB Research nuclear reactor RB reactor, Annual report for 2000

    International Nuclear Information System (INIS)

    Milosevic, M.

    2000-12-01

    Report on RB reactor operation during 2000 contains 3 parts. Part one contains a brief description of reactor operation and reactor components, relevant dosimetry data and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level-meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization with a comprehensive list of publications resulting from experiments done at the RB reactor. It contains data about reactor operation during previous 14 years, i.e. from 1986 - 2000

  8. Sesli Okuma ve Konuşma Prozodisi: İlişkisel Bir Çalışma

    Directory of Open Access Journals (Sweden)

    Hasan Keskin

    2013-02-01

    Full Text Available Bu araştırma,  ilköğretim dördüncü sınıf öğrencilerinin sesli okuma ve konuşma prozodileri arasındaki ilişkiyi incelemek amacıyla ilişkisel tarama modelinde yapılmıştır. Araştırmaya,  Konya ve Afyonkarahisar’da ilköğretim dördüncü sınıfa devam eden 50 öğrenci katılmıştır.  Öğrencilerin sesli okumaları ve konuşmaları video ile kayıt altına alınmış, daha sonra bu kayıtlar üzerinde ölçekler aracılığıyla puanlamalar yapılmıştır. Sesli okuma ve konuşma prozodisi arasındaki ilişkiyi belirlemeye yönelik, Pearson Momentler Çarpım Korelasyon Tekniği kullanılmıştır. Analiz sonuçlarına göre, öğrencilerin sesli okuma ve konuşma prozodileri arasında, pozitif yönlü orta düzeyde bir ilişki çıkmıştır. Öğrencilerin sesli okumaları ve konuşma prozodi puanları cinsiyet açısından ayrı ayrı incelenmiş; kız ve erkek öğrencilerin ortalamaları arasında anlamlı bir farklılık çıkmamıştır. Ayrıca, öğrencilerin sesli okuma ve konuşmalarındaki prozodik düzeyi belirlemeye yönelik ölçümler yapılmıştır. Bu ölçüm sonuçlarına göre, araştırmaya katılan öğrencilerin %52’sinin sesli okuma prozodilerinin,  %48’inin ise konuşma prozodilerinin düşük düzeyde olduğu görülmüştür.

  9. Kırgızistan’da Televizyon İzleme Davranışı Örüntüleri: Bir Kullanımlar ve Doyumlar Perspektif

    OpenAIRE

    Balcı, Şükrü; Ayhan, Bünyamin

    2015-01-01

    Televizyon toplumsal yaşam içerisinde oldukça güçlü ve zamanla önemi daha da artan bir kitle iletişim aracı olarak dikkat çekmektedir. Televizyon, diğer kitle iletişim araçlarıyla kıyaslandığında, insanlara mesajları etkili ve inandırıcı bir şekilde sunan ve kullanımı için herhangi bir eğitim gerektirmeyen bir araç olma özelliğini korumaktadır. Gerek görsel ve işitsel unsurları birlikte kullanması; gerekse de sahte bir katılım duygusu yaratması onu diğer kitle iletişim araçları arasında ön pl...

  10. GIS based Cadastral level Forest Information System using World View-II data in Bir Hisar (Haryana)

    Science.gov (United States)

    Mothi Kumar, K. E.; Singh, S.; Attri, P.; Kumar, R.; Kumar, A.; Sarika; Hooda, R. S.; Sapra, R. K.; Garg, V.; Kumar, V.; Nivedita

    2014-11-01

    Identification and demarcation of Forest lands on the ground remains a major challenge in Forest administration and management. Cadastral forest mapping deals with forestlands boundary delineation and their associated characterization (forest/non forest). The present study is an application of high resolution World View-II data for digitization of Protected Forest boundary at cadastral level with integration of Records of Right (ROR) data. Cadastral vector data was generated by digitization of spatial data using scanned mussavies in ArcGIS environment. Ortho-images were created from World View-II digital stereo data with Universal Transverse Mercator coordinate system with WGS 84 datum. Cadastral vector data of Bir Hisar (Hisar district, Haryana) and adjacent villages was spatially adjusted over ortho-image using ArcGIS software. Edge matching of village boundaries was done with respect to khasra boundaries of individual village. The notified forest grids were identified on ortho-image and grid vector data was extracted from georeferenced cadastral data. Cadastral forest boundary vectors were digitized from ortho-images. Accuracy of cadastral data was checked by comparison of randomly selected geo-coordinates points, tie lines and boundary measurements of randomly selected parcels generated from image data set with that of actual field measurements. Area comparison was done between cadastral map area, the image map area and RoR area. The area covered under Protected Forest was compared with ROR data and within an accuracy of less than 1 % from ROR area was accepted. The methodology presented in this paper is useful to update the cadastral forest maps. The produced GIS databases and large-scale Forest Maps may serve as a data foundation towards a land register of forests. The study introduces the use of very high resolution satellite data to develop a method for cadastral surveying through on - screen digitization in a less time as compared to the old fashioned

  11. Monitoring voltage-dependent charge displacement of Shaker B-IR K+ ion channels using radio frequency interrogation.

    Directory of Open Access Journals (Sweden)

    Sameera Dharia

    2011-02-01

    Full Text Available Here we introduce a new technique that probes voltage-dependent charge displacements of excitable membrane-bound proteins using extracellularly applied radio frequency (RF, 500 kHz electric fields. Xenopus oocytes were used as a model cell for these experiments, and were injected with cRNA encoding Shaker B-IR (ShB-IR K(+ ion channels to express large densities of this protein in the oocyte membranes. Two-electrode voltage clamp (TEVC was applied to command whole-cell membrane potential and to measure channel-dependent membrane currents. Simultaneously, RF electric fields were applied to perturb the membrane potential about the TEVC level and to measure voltage-dependent RF displacement currents. ShB-IR expressing oocytes showed significantly larger changes in RF displacement currents upon membrane depolarization than control oocytes. Voltage-dependent changes in RF displacement currents further increased in ShB-IR expressing oocytes after ∼120 µM Cu(2+ addition to the external bath. Cu(2+ is known to bind to the ShB-IR ion channel and inhibit Shaker K(+ conductance, indicating that changes in the RF displacement current reported here were associated with RF vibration of the Cu(2+-linked mobile domain of the ShB-IR protein. Results demonstrate the use of extracellular RF electrodes to interrogate voltage-dependent movement of charged mobile protein domains--capabilities that might enable detection of small changes in charge distribution associated with integral membrane protein conformation and/or drug-protein interactions.

  12. Monitoring voltage-dependent charge displacement of Shaker B-IR K+ ion channels using radio frequency interrogation.

    Science.gov (United States)

    Dharia, Sameera; Rabbitt, Richard D

    2011-02-28

    Here we introduce a new technique that probes voltage-dependent charge displacements of excitable membrane-bound proteins using extracellularly applied radio frequency (RF, 500 kHz) electric fields. Xenopus oocytes were used as a model cell for these experiments, and were injected with cRNA encoding Shaker B-IR (ShB-IR) K(+) ion channels to express large densities of this protein in the oocyte membranes. Two-electrode voltage clamp (TEVC) was applied to command whole-cell membrane potential and to measure channel-dependent membrane currents. Simultaneously, RF electric fields were applied to perturb the membrane potential about the TEVC level and to measure voltage-dependent RF displacement currents. ShB-IR expressing oocytes showed significantly larger changes in RF displacement currents upon membrane depolarization than control oocytes. Voltage-dependent changes in RF displacement currents further increased in ShB-IR expressing oocytes after ∼120 µM Cu(2+) addition to the external bath. Cu(2+) is known to bind to the ShB-IR ion channel and inhibit Shaker K(+) conductance, indicating that changes in the RF displacement current reported here were associated with RF vibration of the Cu(2+)-linked mobile domain of the ShB-IR protein. Results demonstrate the use of extracellular RF electrodes to interrogate voltage-dependent movement of charged mobile protein domains--capabilities that might enable detection of small changes in charge distribution associated with integral membrane protein conformation and/or drug-protein interactions.

  13. Technical specifications, Hanford production reactors

    Energy Technology Data Exchange (ETDEWEB)

    Gilbert, W.D. [comp.

    1962-06-25

    These technical specifications are applicable to the eight operating production reactor facilities, B, C, D, DR, F, H, KE, and KW. Covered are operating and performance restrictions and administrative procedures. Areas covered by the operating and performance restrictions are reactivity, reactor control and safety elements, power level, temperature and heat flux, reactor fuel loadings, reactor coolant systems, reactor confinement, test facilities, code compliance, and reactor scram set points. Administrative procedures include process control procedures, training programs, audits and inspections, and reports and records.

  14. A nuclear power reactor

    International Nuclear Information System (INIS)

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

    1979-12-01

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

  15. Reactor cost driving items

    International Nuclear Information System (INIS)

    Spears, W.R.

    1987-01-01

    Assuming that the design solutions presently perceived for NET can be extrapolated for use in a power reactor, and using costing experience with present day fusion experiments and with fission power plants, the major components of the cost of a tokamak fusion power reactor are described. The analysis shows the emphasis worth placing on various areas of plant design to reduce costs

  16. Reactor Materials Research

    International Nuclear Information System (INIS)

    Van Walle, E.

    2001-01-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  17. CAREM 25 nuclear reactor

    International Nuclear Information System (INIS)

    Rossini, A.A.; Ordonez, J.P.; Rajoy, J.E.; Durione, C.

    1990-01-01

    This work describes the CAREM project reactor, its design philosophy, its main characteristics and its advantages with respect to similar reactors. The main objective is to use the nuclear energy at lower costs than those applied up to now. (Author) [es

  18. Molten salt reactor concept

    International Nuclear Information System (INIS)

    Sood, D.D.

    1980-01-01

    Molten salt reactor is an advanced breeder concept which is suited for the utilization of thorium for nuclear power production. This reactor is based on the use of solutions of uranium or plutonium fluorides in LiF-BeF 2 -ThF 4 as fuel. Unlike the conventional reactors, no external coolant is used in the reactor core and the fuel salt itself is circulated through heat exchangers to transfer the fission produced heat to a secondary salt (NaF-NaBF 4 ) for steam generation. A part of the fuel stream is continuously processed to isolate 233 Pa, so that it can decay to fissile 233 U without getting converted to 234 Pa, and for the removal of neutron absorbing fission products. This on-line processing scheme makes this reactor concept to achieve a breeding ratio of 1.07 which is the highest for any thermal breeder reactor. Experimental studies at the Bhabha Atomic Research Centre, Bombay, have established the use of plutonium as fuel for this reactor. This molten salt reactor concept is described and the work conducted at the Bhabha Atomic Research Centre is summarised. (auth.)

  19. International thermal reactor development

    International Nuclear Information System (INIS)

    Zebroski, E.L.

    1977-01-01

    The worldwide development of nuclear power plants is reviewed. Charts are presented which show the commitment to light-water reactor capacity construction with breakdown by region and country. Additional charts show the major nuclear research centers which have substantial scope in light water reactor development and extensive international activities

  20. The fusion reactor

    International Nuclear Information System (INIS)

    Brennan, M.H.

    1974-01-01

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

  1. Advanced converter reactors

    International Nuclear Information System (INIS)

    Kasten, P.R.

    1979-01-01

    Advanced converter reactors (ACRs) of primary US interest are those which can be commercialized within about 20 years, and are: Advanced Light-Water Reactors, Spectral-Shift-Control Reactors, Heavy-Water Reactors (CANDU type), and High-Temperature Gas-Cooled Reactors. These reactors can operate on uranium, thorium, or uranium-thorium fuel cycles, but have the greatest fuel utilization on thorium type cycles. The water reactors tend to operate more economically on uranium cycles, while the HTGR is more economical on thorium cycles. Thus, the HTGR had the greatest practical potential for improving fuel utilization. If the US has 3.4 to 4 million tons U 3 O 8 at reasonable costs, ACRs can make important contributions to maintaining a high nuclear power level for many decades; further, they work well with fast breeder reactors in the long term under symbiotic fueling conditions. Primary nuclear data needs of ACRs are integral measurements of reactivity coefficients and resonance absorption integrals

  2. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2001-04-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  3. Space Nuclear Reactor Engineering

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-03-06

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

  4. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.; Lineberry, M.J.

    1990-01-01

    Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 5 refs., 3 figs

  5. Nuclear reactor instrumentation method

    International Nuclear Information System (INIS)

    Handa, Hiroyuki; Hayashi, Katsumi; Nemesawa, Shigeki; Nemoto, Yuji; Ohashi, Masahisa.

    1993-01-01

    The present invention can appropriately monitor the state of a reactor core in an FBR type reactor which has a system of storing spent fuel assemblies in a reactor container while reducing the weight and making the structure compact in the reactor. That is, a fuel assembly having a shield lacking portion in upper axial shields is disposed. The shield lacking portion defines neutrons' leaking path from the reactor core. The leakage of neutrons from the path is detected by a neutron monitor disposed just above the fuel assembly. With such a constitution, influence of neutrons from stored spent fuel assemblies disposed to the out side of the radial shields can be reduced by a shielding effect of the existent radial shields around the reactor core. Further, if a shield lacking portion is locally disposed in the region of the upper axial shields just below the neutron monitor, neutrons from the reactor core can be monitored while suppressing excessive neutron leakage. As a result, it is unnecessary to dispose shields on the outer side of the spent fuel assembly disposed in the reactor core. (I.S.)

  6. Reactor building for a nuclear reactor

    International Nuclear Information System (INIS)

    Haidlen, F.

    1976-01-01

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

  7. Reactor coolant pump for a nuclear reactor

    International Nuclear Information System (INIS)

    Burkhardt, W.; Richter, G.

    1976-01-01

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

  8. Tezkire Niteliğinde Bir Şiir Mecmuası A Macmua Of Poem Feature Of Periodical (Tazkirah

    Directory of Open Access Journals (Sweden)

    Uğur ÖZTÜRK

    2013-03-01

    Full Text Available Connotating compiled, collected, gathered, "majmuas" among betwixt "poem majmuas" are of major sources as for being enjoyed to compose history of Ottoman literature. In general terms, it is appropriate to classify the majmuas in recordinds of selected poems inreference to a certain alphabetical order or poem majmuas. Biographicdetails of a majmua which is retained in Atatürk Kitaplığı, MuallimCevdet Section No: K.479 and distinctive for the era written in has beenworken on. From the scripts in the introduction, partially in the middleand at the end of the majmua, as understood, disconnexion exists.Identity of writer and inking time are precarious. It has been inferedfrom the scripts in the majmua that it has been written in the last 15years of era of Suleyman The Great.Author of the majmua placed famous writers before his day andboth fameless and famous during his day. In general, he presentedshort biographic information before poems, even sometimes madeassessments about poets in this informations. What makes a majmuahere is of biographic information in and poets never mentioned intezkires. Poems chosen for majmua show parallelism with ones in 16.centuriy and have generally characteristics of "berceste" Poets likeHayali Bey, Baki, Ahmed Paşa, Necati Bey, Atayi, Muhibbi, Nazmi arepredominant in these majmuas. The others like Savmi, Hazani Bey,Halisi Bey have no records in majmuas. Bir araya getirilmiş, toplamış manasını taşıyan mecmualar içerisinde şiir mecmuları Osmanlı edebiyatı tarihine kaynaklık etmesi açısından birincil kaynaklar arasında yer almaktadır. Şiir mecmualarına genel olarak bakıldığında bu mecmuaları belli bir harf düzenine göre yazılmış seçme şiirlerden oluşan şiir defterleri veya nazire mecmuası diye adlandırmak yerindedir. Atatürk Kitaplığı Muallim Cevdet Bölümü K.479 numarada yer alan ve yazıldığı dönemin açısından önemli olan bir şiir mecmuasının biyografik bilgileri

  9. Malezya’da Din-Devlet İlişkisine Kısa Bir Bakış

    Directory of Open Access Journals (Sweden)

    Mehmet Özay

    2013-03-01

    Full Text Available AbstractStarting from the second half of the 1960s onwards, socio-religious youth movements, which are regarded as the initial element of civil expressions on university campuses, were constructively influential on the perception of the political elites’ understanding of Islam and political evolution of the Islamisation policies in the process in Malaysia. There are opinions that this effect encompassed the efforts of Islamisation particularly in the 1980s. In this process, the task of the state apparatus, as a political power, which managed the religious domain mostly considered belonging to the civil sector, deserves to be scrutinized in relation with at least some influential factors in the near and distant past of the Muslim Malay community. And, it cannot be overseen that the functions of the traditional Malay rulers, say, Sultans, were transferred, to some or larger extent, to the Federal government after the independence. With regard to this, in this article, the present writer will focus on some aspects of the policies of Dr. Mahathir Mohamad, who has molded majorily the history of modern Malaysia, regarding his Islamisation policy aligned with the state-religion relationship.ÖzetMalezya’da 1960’lı yılların ikinci yarısından itibaren üniversite kampüslerinde başlayan ve sivilleşmenin bir unsuru olarak telâkki edilen dini-toplumsal hareketlerin İslam’ın ülke siyasi elitince algılanmasında ve pratikte İslamlaştırma adıyla anılabilecek politikalara evrilmesinde önemli etkisi olmuştur. Bu etkinin, özellikle 1980’li yıllarda devlet eliyle İslamlaştırma çabalarına yol açtığı konusunda görüşler bulunmaktadır. Bu süreçte, yani devletin siyasi bir güç olarak sivil alana dahil olan dini çekip çevirme işini üstlenmesinde, özellikle Müslüman Malay toplumunun yakın ve uzak geçmişindeki kimi faktörler dikkate alınmayı hak etmektedir. Bu bağlamda, geleneksel Malay devletlerinde Sultanlar

  10. Mirror reactor surface study

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, A. L.; Damm, C. C.; Futch, A. H.; Hiskes, J. R.; Meisenheimer, R. G.; Moir, R. W.; Simonen, T. C.; Stallard, B. W.; Taylor, C. E.

    1976-09-01

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included.

  11. Iris reactor conceptual design

    Energy Technology Data Exchange (ETDEWEB)

    Carelli, M.D.; Conway, L.E.; Petrovic, B.; Paramonov, D.V. [Westinghouse Electric Comp., Pittsburgh, PA (United States); Galvin, M.; Todreas, N.E. [Massachusetts Inst. of Tech., Cambridge, MA (United States); Lombardi, C.V.; Maldari, F.; Ricotti, M.E. [Politecnico di Milano, Milan (Italy); Cinotti, L. [Ansaldo SpA, Genoa (Italy)

    2001-07-01

    IRIS (International Reactor Innovative and Secure) is a modular, integral, light water cooled, low-to-medium power (100-350 MWe) reactor which addresses the requirements defined by the US DOE for Generation IV reactors, i.e., proliferation resistance, enhanced safety, improved economics and fuel cycle sustainability. It relies on the proven technology of light water reactors and features innovative engineering, but it does not require new technology development. This paper discusses the current reference IRIS design, which features a 1000 MWt thermal core with proven 5%-enriched uranium oxide fuel and five-year long straight burn fuel cycle, integral reactor vessel housing helical tube steam generators and immersed spool pumps. Other major contributors to the high level of safety and economic attractiveness are the safety by design and optimized maintenance approaches, which allow elimination of some classes of accidents, lower capital cost, long operating cycle, and high capacity factors. (author)

  12. Reactor control device

    International Nuclear Information System (INIS)

    Fukami, Haruo; Morimoto, Yoshinori.

    1981-01-01

    Purpose: To operate a reactor always with safety operation while eliminating the danger of tripping. Constitution: In a reactor control device adapted to detect the process variants of a reactor, control a control rod drive controlling system based on the detected signal to thereby control the driving the control rods, control the reactor power and control the electric power generated from an electric generator by the output from the reactor, detection means is provided for the detection of the electric power from said electric generator, and a compensation device is provided for outputting control rod driving compensation signals to the control rod driving controlling system in accordance with the amount of variation in the detected value. (Seki, T.)

  13. Mirror reactor surface study

    International Nuclear Information System (INIS)

    Hunt, A.L.; Damm, C.C.; Futch, A.H.; Hiskes, J.R.; Meisenheimer, R.G.; Moir, R.W.; Simonen, T.C.; Stallard, B.W.; Taylor, C.E.

    1976-01-01

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included

  14. Nuclear reactor design

    CERN Document Server

    2014-01-01

    This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

  15. Reactor power control device

    International Nuclear Information System (INIS)

    Kobayashi, Akira.

    1980-01-01

    Purpose: To prevent misoperation in a control system for the adjustment of core coolant flow rate, and the increase in the neutron flux density caused from the misoperation in BWR type reactors. Constitution: In a reactor power control system adapted to control the reactor power by the adjustment of core flow rate, average neutron flux signals of a reactor core, entire core flow rate signals and operation state signals for coolant recycling system are inputted to a microcomputer. The outputs from the computer are sent to a recycling MG set speed controller to control the reactor core flow rate. The computer calculates the change ratio with time in the average neutron flux signals, correlation between the average neutron flux signals and the entire core flow rate signals, change ratio with time in the operation state signals for the coolant recycling system and the like and judges the abnormality in the coolant recycling system based on the calculated results. (Ikeda, J.)

  16. Status of French reactors

    International Nuclear Information System (INIS)

    Ballagny, A.

    1997-01-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm 3 . The OSIRIS reactor has already been converted to LEU. It will use U 3 Si 2 as soon as its present stock of UO 2 fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU

  17. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1984-08-01

    Research and development activities in the Department of Reactor Engineering in fiscal 1983 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

  18. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Hirota, Jitsuya; Asaoka, Takumi; Suzuki, Tomoo; Mitani, Hiroshi; Akino, Fujiyoshi

    1977-09-01

    Research activities in the Division of Reactor Engineering in fiscal 1976 are described. Works of the division concern mainly the development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and the development of Liquid Metal Fast Breeder Reactor in Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and activities of the Committee on Reactor Physics. (auth.)

  19. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1976-09-01

    Research activities conducted in Reactor Engineering Division in fiscal 1975 are summarized in this report. Works in the division are closely related to the development of multi-purpose High-temperature Gas Cooled Reactor, the development of Liquid Metal Fast Breeder Reactor by Power Reactor and Nuclear Fuel Development Corporation, and engineering research of thermonuclear fusion reactor. Many achievements are described concerning nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology and activities of the Committee on Reactor Physics. (auth.)

  20. Mirror reactor studies

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  1. Multi-purpose reactor

    International Nuclear Information System (INIS)

    1991-05-01

    The Multi-Purpose-Reactor (MPR), is a pool-type reactor with an open water surface and variable core arrangement. Its main feature is plant safety and reliability. Its power is 22MW t h, cooled by light water and moderated by beryllium. It has platetype fuel elements (MTR type, approx. 20%. enriched uranium) clad in aluminium. Its cobalt (Co 60 ) production capacity is 50000 Ci/yr, 200 Ci/gr. The distribution of the reactor core and associated control and safety systems is essentially based on the following design criteria: - upwards cooling flow, to waive the need for cooling flow inversion in case the reactor is cooled by natural convection if confronted with a loss of pumping power, and in order to establish a superior heat transfer potential (a higher coolant saturation temperature); - easy access to the reactor core from top of pool level with the reactor operating at full power, in order to facilitate actual implementation of experiments. Consequently, mechanisms associated to control and safety rods s,re located underneath the reactor tank; - free access of reactor personnel to top of pool level with the reactor operating at full power. This aids in the training of personnel and the actual carrying out of experiments, hence: - a vast water column was placed over the core to act as radiation shielding; - the core's external area is cooled by a downwards flow which leads to a decay tank beyond the pool (for N 16 to decay); - a small downwards flow was directed to stream downwards from above the reactor core in order to drag along any possibly active element; and - a stagnant hot layer system was placed at top of pool level so as to minimize the upwards coolant flow rising towards pool level

  2. Bir Ortaokul Matematik Öğretmeninin WebQuestin Uygulamasına Yönelik Görüşü

    Directory of Open Access Journals (Sweden)

    Aytaç Kurtuluş

    2014-03-01

    Full Text Available t. Bu çalışmada bir WebQuest etkinliğini sınıfında ilk defa uygulayan bir ortaokul matematik öğretmeninin WebQuestin uygulama sürecine ve öğrencileri üzerinde bıraktığı etkisine yönelik görüşü incelenmiştir. Çalışmaya katılan öğretmen histogram konusuna yönelik hazırlamış olduğu bir WebQuest etkinliğini 8. sınıf öğrencilerine proje ödevi olarak uygulamıştır. Bu çalışma olgubilim araştırması olarak tasarlanmış olup, veriler öğretmenle uygulama sırasında ve sonunda yapılan görüşmelerden ve uygulama sonunda öğrencilerle yapılan görüşmeler ve öğrenci sunumlarının gözlemlenmesi yoluyla toplanmıştır. Çalışma bulguları, WebQuest uygulamasının öğrencilerin motivasyonuna, özgüvenlerine olumlu katkıda bulunduğunu göstermiştir. Elde edilen öğretmen görüşleri, WebQuestlerin proje ve performans ödevi olarak uygulanabileceğini ve ortaokul matematik öğretim programını desteklediğini ortaya koymuşt

  3. ESR analyses for herbivore teeth and molluscs from Kharga, Dakhleh, and Bir Tarfawi Oases: Constraining water availability and hominin paleolithic activity in the Western Desert, Egypt

    Science.gov (United States)

    Blackwell, B. A. B.; Skinner, A. R.; Smith, J. R.; Hill, C. L.; Churcher, C. S.; Kieniewicz, J. M.; Adelsberger, K. A.; Blickstein, J. I. B.; Florentin, J. A.; Deely, A. E.; Spillar, K. V.

    2017-12-01

    Today, Bir Tarfawi, Kharga and Dakhleh Oases all sit in Egypt's hyperarid Western Desert. A dearth of naturally occurring surface water coupled with ≤ 0.1 mm/y of precipitation, and evaporation rates > 2 m/y make Bir Tarfawi uninhabitable today, while Dakhleh and Kharga depend on borehole water to support human inhabitation. Yet in scattered locations dotting the Quaternary surfaces and deposits near each oasis, Paleolithic artefacts, fossil ungulate teeth, and snails record times when surface water did exist in wetlands, small ponds, and even large lakes. At Bir Tarfawi in Marine Isotope Stages (MIS) 5, 7, and 13, wetlands or small lakes supported freshwater snails, large herbivores, and hominins. Dakhleh Oasis hosted a large lake in MIS 6 that provided a deep reliable water supply for many millennia subsequently. ESR dates on fossils and tufa dates show thriving lacustrine and terrestrial ecosystems at Dakhleh during MIS 5, 7, 9, 11, and 17, and in shorter episodes in MIS 1, 2, 3, 6, and 12. At Kharga Oasis, springs discharged along the Libyan Escarpment edge, but the water was ponded in small basins dammed within tufa deposits. These dated deposits and fossils attest that water existed there in MIS 2-11, and one spot dating to ∼ 2.3 Ma. This proxy evidence suggest that, thanks to higher rainfall and/or groundwater tables, sufficient water persisted for much of the Pleistocene, supporting food resources, like large herbivores and molluscs, to thrive and enabling hominin habitation. and activity in the Western Desert.

  4. Elucidating respective functions of two domains BIR and C-helix of human IAP survivin for precise targeted regulating mitotic cycle, apoptosis and autophagy of cancer cells.

    Science.gov (United States)

    Hu, Fabiao; Pan, Daxia; Zheng, Wenyun; Yan, Ting; He, Xiujuan; Ren, Fuzheng; Lu, Yiming; Ma, Xingyuan

    2017-12-26

    Survivin was the smallest member of the IAP family, which was over expressed in many different cancers, and considered to be a promising hot target for cancer therapy, and our previous study demonstrated that multiple dominant negative mutants from full-length survivin could have many complex effects on cancer cells, such as cell cycle, apoptosis, and autophagy. But it was not yet known what role the two main domains played in those functions, which would be very important for the design of targeted anticancer drugs and for the interpretation of their molecular mechanisms. In this study, based on preparation the two parts (BIR domain and CC domain) of survivin by genetic engineering and cell characterization assay, we discovered that BIR (T34A)-domain peptide could inhibit Bcap-37 cells growth in a dose- and time-dependent manner, increase the proportion of G2/M phase, and induce caspase-dependent apoptosis via the mitochondrial pathway. While CC (T117A)-domain peptide increased the proportion of S-phase cells and increased the level of the autophagy marker protein LC3B significantly. These further experiments confirmed that TAT-BIR (T34A) peptide could be used to inhibit cell proliferation, promote apoptosis, and block mitosis, and TAT-CC (T117A) peptide showed mainly to promote autophagy, process of DNA replication, and mitosis to breast cancer cells. This research will lay the foundation for interpreting the multifunction mechanism of survivin in cell fates, further make senses in developing the anticancer drugs targeting it precisely and efficiently.

  5. Mahalli Fıkra Tipine Bir Örnek: Erzurumlu Naim Hoca One Type of Anecdote of Local Example: Hoca Erzurumlu Naim

    Directory of Open Access Journals (Sweden)

    Yusuf KOTAN

    2012-09-01

    Full Text Available One of the important types of folk literature satire, in a large geographical area consisting of many thousands of years, products of oral tradition of folk literaturen. These products, although oral edebiyatımız as a kind of took its place in the literature long ago, particularly after the Tanzimat era has gained vitality. This vitality,though no doubt in some quarters that the jokes have suffered tab, inalmost every nation acquires an important social and cultural life.Feeling and thinking, of a nation, intelligence, humor, and mostimportantly the power of judgment to reflect the common opinion is ofgreat importance in terms of paragraphs. One of the important elementsin the formation of these clauses in the clause types. These types, asdescribed in the paragraph is the hero, as well as to express thecommon characteristics of living is important for society. These typeswith almost every region of Anatolia, and they faced a yararlanmaktayızthis narrative. Who live in this very important region in terms ofreflecting the properties of typecasting, giving expressions to represent aparticular feature of the local stage.Erzurum folklore, is a rich resource for Turkish folklore. Althoughthis has been a rich source folklorumuzun on the part of many researchstudies conducted on jokes is almost negligible. Based on theseapproaches, we also provide a contribution to the folklore of Erzurum inboth types of clause in Erzurum, an important place in the memory ofour people who had said Naim Hodja jokes we introduce this valuableanecdotes of people will try to share with you. Halk edebiyatımızın önemli türlerinden biri olan fıkralar, çok geniş bir coğrafi alan içinde oluşan binlerce yıldan beri sözlü gelenekte yaşayan halk edebiyatı ürünleridir. Bu ürünler, sözlü edebiyatımız içerisinde yerini çok öncelerden almış olsa da bir tür olarak edebiyatımızda bilhassa Tanzimat döneminden sonra canlılık kazanmıştır. Bu canl

  6. Dehydration of the off-flavor chemical 2-methylisoborneol by the R-limonene-degrading bacteria Pseudomonas sp. strain 19-rlim and Sphingomonas sp. strain BIR2-rlima.

    Science.gov (United States)

    Eaton, Richard W

    2012-04-01

    The terpene 2-methylisoborneol (MIB), a major cause of off-flavor in farm-raised catfish and drinking water, is transformed by various different terpene-degrading bacteria. Two of these, the R-limonene-degrading strains Pseudomonas sp. 19-rlim and Sphingomonas sp. BIR2-rlima, dehydrated MIB with the formation of odorless metabolites 2-methylenebornane and 4-methylcamphene. These metabolites which have a structural resemblance to camphor, could be further transformed by camphor-degrading bacteria to more oxidized products. The bacterial dehydrations demonstrated here may have application in removing MIB where it is a problem.

  7. Gezgin satıcı problemi için yeni bir meta-sezgisel: kör fare algoritması

    Directory of Open Access Journals (Sweden)

    Tevfik YILDIRIM

    2016-02-01

    Full Text Available Gezgin Satıcı Problemi (GSP, başlangıç ve bitiş şehirleri aynı olan ve her şehrin sadece bir kez ziyaret edildiği minimum mesafeli turu bulma problemidir. Şehir sayısı arttıkça, kesin yöntemler ile kabul edilebilir sürelerde bir optimum çözüm bulunması zordur. Bu nedenle, son elli yılda GSP’nin çözümü için doğadan ve biyolojiden esinlenen birçok meta-sezgisel yöntem geliştirilmiştir. Bu çalışmada, toprak altındaki bireysel tünel sistemlerinde yaşayan kör farelerin toprak altındaki engelleri geçme stratejisinden esinlenilerek GSP’nin çözümü için yeni bir meta-sezgisel tasarlanmıştır. Geliştirilen yönteme Kör Fare Algoritması adı verilmiştir. Bu yeni sezgisel ile farklı boyutlardaki simetrik test veri setleri için deneyler yapılmış ve sonuçları bilinen en iyi sonuçlar ile kıyaslanmıştır. Önerilen meta-sezgisel henüz literatürdeki diğer algoritmalarla yarışabilecek düzeyde olmamasına rağmen, başlangıç test çözümlerinin umut verici olduğu söylenebilir.Anahtar Kelimeler: Gezgin satıcı problemi, Kombinatoryel eniyileme, Meta-Sezgisel, Kör fare algoritması

  8. Örgütsel Çekicilik : Bir Ölçek Uyarlama Çalışması

    Directory of Open Access Journals (Sweden)

    Seda DURAL

    2014-12-01

    Full Text Available Bu çalışmanın amacı, Highhouse vd. (2003 tarafından geliştirilen Örgütsel Çekicilik Ölçeğini (ÖÇÖ Türkçe’ye kazandırmak ve geçerlik ve güvenirlik analizlerini yapmaktır. Ölçek, öncelikle araştırmacılar ve bir dil uzmanı tarafından Türkçe’ye çevrilmiş, ardından ifadeler iki dilli 15 uzmanın görüşüne başvurularak dil ve anlam uygunluğu bakımından değerlendirilmiştir. Öneriler doğrultusunda son şeklini alan Türkçe form iki aşamada uygulanmıştır. İlk aşamada, test-tekrar test güvenirliğini sınamak amacıyla ölçek iki hafta ara ile 50 öğrenciye uygulanmıştır. Test tekrar-test güvenirlik katsayısı birincil değerlendirme için 0,85, ikincil değerlendirme için 0,89 olarak bulunmuştur. Uygulamanın ikinci aşamasında anket 257 öğrenciye uygulanarak ölçeğin iç tutarlılık katsayısı 0,89 olarak bulunmuştur. Yapılan analizler sonucunda ÖÇÖ’nün özgün ölçekte olduğu gibi üç faktörlü bir yapı gösterdiği belirlenmiştir. Hiçbir madde atılmadan 15 madde ile üç boyutu ölçen geçerli ve güvenilir bir ölçek elde edilmiştir.

  9. Eğitimde Özelleştirme Tartışmaları: Kavramsal Bir Analiz Disscussions on Privatization in Education: A conceptual Analysis

    Directory of Open Access Journals (Sweden)

    Ramazan YİRCİ

    2013-09-01

    politika alanında önemli düşünce değişimlerin meydana geldiği bir dönem olmuştur. Bu değişimler toplumun hayatında önemli bir yere sahip olan eğitim sisteminde de değişik uygulamaların uygulanıp uygulanamayacağı sorusunu gündeme getirmiştir. Bu çalışma ile ekonomi alanında pek çok ülkede yaygın bir şekilde kullanılan özelleştirme kavramını ele almak, eğitimde özelleştirme ve finansman ilişkisini incelemek, eğitimde özelleştirmenin dünyadaki örneklerine göz atmak amaçlanmıştır. Eğitim insana yatırım yapan ve çıktısı yine insan olan önemli bir hizmet koludur. Devletin iyi eğitimli bireyler yetiştirmesi toplumun kalkınmasını sağlayacaktır. Bireylerin iyi yetiştirilmesi işi eğitim sistemi içinde faaliyet gösteren okulların etkili performanslarına bağlıdır. Bu çalışmada eğitimde özelleştirme uygulamalarının değişik ülkelerde gerçekleşme biçimine, eğitimin finansmanında devletin ve özel sektörün konumuna, eğitimde özelleştirmeyi destekleyenlerin ve karşı çıkanların görüşlerine yer verilmiştir. Eğitim gibi önemli bir konuda özel sektörün etkinliğini artırması devletin yükünü hafifletebilir. Burada dikkat edilecek husus özel kesimin daha fazla eğitim alanında faaliyet göstermesini sağlarken, eğitim kalitesinden ödün vermeden, toplumdaki sosyal adalet duygusunu incitmeden adımlar atabilmektir. Dünyadaki en iyi yüz üniversite sıralamasında özelleştirme uygulamalarının büyük ölçüde uygulandığı Amerika, İngiltere, Japonya gibi ülkelerden pek çok üniversitenin bulunması dikkat çekici bir durumdur. Aynı listeye Türkiye’den hiçbir üniversitenin girememiş olması da eğitim sisteminin yapısında yeniden yapılanmanın ne kadar büyük bir ihtiyaç olduğunu göstermektedir. Bu bağlamda özelleştirme eğitimde ülkemiz okullarının yaşadığı nitelik sorununa alternatif bir çözüm yolu geliştirmeye yardımcı olabilir.

  10. The Problem of Anonymity in Archives: A Literature Review=Arşivlerde Anonimlik Sorunu: Bir Literatür Değerlendirmesi

    Directory of Open Access Journals (Sweden)

    Emily Ross

    2013-12-01

    Full Text Available Archivists processing documents rely on factors such as authorship and provenance to contextualize their materials and render them searchable. But in my past experience as an archives user, I repeatedly came across instances of anonymity: letters and diaries by unnamed authors or to unknown recipients, photographs of unknown subjects. In some cases this anonymity is a loss of information that was once there, but in other case it enabled the material to come into existence in the first place: such as in the case of satirical political poetry, for which a writer might face legal censure. In this literature review, the issue of anonymity in the archives is explored, both in a pragmatic sense (recommended strategies for managing it, and a philosophical sense (according anonymous documents the same status as documents with known authors./Arşivcilikte belgelerin işlenmesi, materyallerin kavramsallaştırılması ve aranabilir hale gelmesinde önemli olan yazarlık ve kaynak (menşe gibi faktörlere dayanmaktadır. Ancak bir arşiv kullanıcısı olarak deneyimlerimizde defalarca isimsiz yazarlar tarafından bilinmeyen kişilere atfedilmiş mektuplar ve günlükler, bilinmeyen konuların fotoğrafları gibi anonim eserlerle karşılaşmaktayız. Bir zamanlar bu anonimlik bazen bir bilgi kaybı olarak görülürken bazen de belgenin yazarının yasal kınamaya maruz kalabildiği hicivli siyasi bir şiir örneğinde olduğu gibi eserin ilk etapta ortaya çıkmasını sağlamaktaydı. Bu literatür taramasında arşivlerde anonimlik sorunu hem pragmatik anlamda (konunun yönetimi için önerilen stratejiler hem de felsefi anlamda (anonim belgelere uygun olarak bilinen yazarlı belgelerle aynı statüde ele alınmaktadır.

  11. Bir Yemek Sosyolojisi Denemesi Örneği Olarak Tokat Mutfağı As A Case Of Sociology Of Food Tokat Cuisine

    Directory of Open Access Journals (Sweden)

    Adem SAĞIR

    2012-12-01

    Full Text Available The food fact which carries centuries of accumulation and diversity as historical part of society comes up rather than tge act of impregnating with part of cultural pattern too. In this contex, food is a basic fact in society behaviours, such as ceremonies, religious ceremonies, wedding ceremonies, entertainments, festivals, death ceremonies. As well, food appears on society with a instrumentalization status of social integration and social solidarity. The social phenomena which like entertainments, friend conversations, honor, wedding,engagement, oblation, holiday rituals, religious ceremonies cancontribute to the creation of a developed in paralled food culturedeveloped in parallel social phenomena in society can contribute to thecreation of a communication network in society. A study of foodsociology that movement of food culture as well, sociology of rituals, folkbeliefs and cousine too. The main purpose of this study is to discussthe place of food culture which has changed into social solidarity andintegration in the ceremonies, entertainments and festivals. Thastarting point of the study is the idea that cousine is a mirror thatreflects the history of a society in terms of spiritual, cultural, economicand politicak aspect. The field of the study is limited with cousine ofTokat and the description of this culture. With regards to the results,both the social origin of the food culture has been examined and fromthis context its effect on the social behaviours and habits. Therefore,this study has been designed as an experimentation of sociology of food.The study aimed at contribıuting to this field in respect to evaulateTokat cousine in context of sociology of food. Toplumların tarihsel bir parçası olarak yüzyılların birikimini ve çeşitliliğini taşıyan yemek olgusu, sadece bir karın doyurma eyleminden ziyade kültürel kalıpların da bir parçası olarak karşımıza çıkar. Bu bağlamda yemek, törenlerin, dinsel merasimlerin

  12. Reactor performance calculations for water reactors

    International Nuclear Information System (INIS)

    Hicks, D.

    1970-04-01

    The principles of nuclear, thermal and hydraulic performance calculations for water cooled reactors are discussed. The principles are illustrated by describing their implementation in the UKAEA PATRIARCH scheme of computer codes. This material was originally delivered as a course of lectures at the Technical University of Helsinki in Summer of 1969.

  13. Reactor scram device for FBR type reactor

    International Nuclear Information System (INIS)

    Kumasaka, Katsuyuki; Arashida, Genji; Itooka, Satoshi.

    1991-01-01

    In a control rod attaching structure in a reactor scram device of an FBR type reactor, an anti-rising mechanism proposed so far against external upward force upon occurrence of earthquakes relies on the engagement of a mechanical structure but temperature condition is not taken into consideration. Then, in the present invention, a material having curie temperature characteristics and which exhibits ferromagnetism only under low temperature condition and a magnet device are disposed to one of a movable control rod and a portion secured to the reactor. Alternatively, a bimetal member or a shape memory alloy which actuates to fix to the mating member only under low temperature condition is secured. The fixing device is adapted to operate so as to secure the control rods when the low temperature state is caused depending on the temperature condition. With such a constitution, when the control rods are separated from a driving device, they are prevented from rising even if they undergo external upward force due to earthquakes and so on, which can improve the reactor safety. (N.H.)

  14. Müşteri İlişkileri Yönetimi Programının Bir Parçası Olarak Satış Görüşmelerinde Müşteri Memnuniyetinin Ölçülmesi Üzerine Bir Pilot Araştırma

    OpenAIRE

    Ovalı, Elif

    2014-01-01

    Özet Rekabette üstünlük sağlayan bir faktör olarak müşteri memnuniyeti işletmeler için yaşamsal önem taşımaktadır. Müşteri memnuniyeti ise müşterinin beklentilerinin karşılanması ile sağlanmaktadır. Araştırmada, müşteri ilişkileri yönetiminin etkinliğini ve müşteri mem­nuniyetini ölçmeye yönelik özgün bir model oluşturulmuştur. Araştırma, servis ve satın alma deneyimini içeren satış sistemi memnuniyetini ölçmeyi hedeflemektedir. Araştırma Antakya'da faaliyet gösteren bir otomotiv bayiind...

  15. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    1993-09-01

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

  16. Reactor engineering department annual report

    International Nuclear Information System (INIS)

    1990-09-01

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

  17. İslami Takaful Sigortacılığının Zorluklarının Üstesinden Gelmek İçin Stratejik Bir Bakış

    OpenAIRE

    DAWABA, Ashraf

    2018-01-01

    Bu araştırma, bir nizam ve bir akit olarakİslami tekafül sigortacılık kavramının yanı sıra, İslami tekafülsigortacılığının hedefleri, genel ve özel ilkeleri, onunla gelenekselsigortacılık arasındaki temel farklar üzerinde durmayı amaçlamaktadır. Ayrıca,İslami tekafül sigortacılığının güçlü yanları ve karşılaştığı zorluklarıbelirtip bu zorlukların üstesinden gelmek için stratejik bir bakış ortayakoymayı hedeflemektedir.

  18. Reactor water sampling device

    International Nuclear Information System (INIS)

    Sakamaki, Kazuo.

    1992-01-01

    The present invention concerns a reactor water sampling device for sampling reactor water in an in-core monitor (neutron measuring tube) housing in a BWR type reactor. The upper end portion of a drain pipe of the reactor water sampling device is attached detachably to an in-core monitor flange. A push-up rod is inserted in the drain pipe vertically movably. A sampling vessel and a vacuum pump are connected to the lower end of the drain pipe. A vacuum pump is operated to depressurize the inside of the device and move the push-up rod upwardly. Reactor water in the in-core monitor housing flows between the drain pipe and the push-up rod and flows into the sampling vessel. With such a constitution, reactor water in the in-core monitor housing can be sampled rapidly with neither opening the lid of the reactor pressure vessel nor being in contact with air. Accordingly, operator's exposure dose can be reduced. (I.N.)

  19. Reactor safety protection system

    International Nuclear Information System (INIS)

    Nishi, Hiroshi; Yokoyama, Tsuguo.

    1989-01-01

    A plurality of neutron detectors are disposed around a reactor core and detection signals from optional two neutron detectors are inputted into a ratio calculation device. If the ratio between both of the neutron flux level signals exceeds a predetermined value, a reactor trip signal is generated from an alarm setting device. Further, detection signals from all of the neutron detection devices are inputted into an average calculation device and the reactor trip signal is generated also in a case where the average value exceeds a predetermined set value. That is, when the reactor core power is increased locally, the detection signal from the neutron detector nearer to the point of power increase is greater than the increase rate for the entire reactor core power, while the detection signal from the neutron detector remote from the point of power increase is smaller. Thus, the local power increase ratio in the FBR reactor core can be detected efficiently by calculating the ratio for the neutron flux level signals from two neutron detectors, thereby enabling to exactly recognize the local power increase rate in the reactor core. (N.H.)

  20. Reactor power control device

    International Nuclear Information System (INIS)

    Imaruoka, Hiromitsu.

    1994-01-01

    A high pressure water injection recycling system comprising injection pipelines of a high pressure water injection system and a flow rate control means in communication with a pool of a pressure control chamber is disposed to a feedwater system of a BWR type reactor. In addition, the flow rate control means is controlled by a power control device comprising a scram impossible transient event judging section, a required injection flow rate calculation section for high pressure water injection system and a control signal calculation section. Feed water flow rate to be supplied to the reactor is controlled upon occurrence of a scram impossible transient event of the reactor. The scram impossible transient event is judged based on reactor output signals and scram operation demand signals and injection flow rate is calculated based on a predetermined reactor water level, and condensate storage tank water or pressure control chamber pool water is injected to the reactor. With such procedures, water level can be ensured and power can be suppressed. Further, condensate storage tank water of low enthalpy is introduced to the pressure suppression chamber pool to directly control elevation of water temperature and ensure integrity of the pressure vessel and the reactor container. (N.H.)

  1. Nuclear reactor containing facility

    International Nuclear Information System (INIS)

    Hidaka, Masataka; Murase, Michio.

    1994-01-01

    In a reactor containing facility, a condensation means is disposed above the water level of a cooling water pool to condensate steams of the cooling water pool, and return the condensated water to the cooling water pool. Upon occurrence of a pipeline rupture accident, steams generated by after-heat of a reactor core are caused to flow into a bent tube, blown from the exit of the bent tube into a suppression pool and condensated in a suppression pool water, thereby suppressing the pressure in the reactor container. Cooling water in the cooling water pool is boiled by heat conduction due to the condensation of steams, then the steams are exhausted to the outside of the reactor container to remove the heat of the reactor container to the outside of the reactor. In addition, since cooling water is supplied to the cooling water pool quasi-permanently by gravity as a natural force, the reactor container can be cooled by the cooling water pool for a long period of time. Since the condensation means is constituted with a closed loop and interrupted from the outside, radioactive materials are never released to the outside. (N.H.)

  2. Reactor Safety Research Programs

    Energy Technology Data Exchange (ETDEWEB)

    Edler, S. K.

    1981-07-01

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipeto- pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-ofcoolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  3. The integral fast reactor

    International Nuclear Information System (INIS)

    Till, C.E.

    1987-01-01

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

  4. Water cooled nuclear reactors

    International Nuclear Information System (INIS)

    Donaldson, A.J.

    1989-01-01

    In order to reduce any loss of primary water coolant from around a reactor core of a water cooled nuclear reactor caused by any failure of a pressure vessel, an inner vessel is positioned within and spaced from the pressure vessel. The reactor core and main portion of the primary water coolant circuit and a heat exchanger are positioned within the inner vessel to maintain some primary water coolant around the reactor core and to allow residual decay heat to be removed from the reactor core by the heat exchanger. In the embodiment shown an aperture at the upper region of the inner vessel is dimensioned configured and arranged to prevent steam from a steam space of an integral pressurised water cooled nuclear reactor for a ship entering the main portion of the primary water coolant circuit in the inner vessel if the longitudinal axis of the nuclear reactor is displaced from its normal substantially vertical position to an abnormal position at an angle to the vertical direction. Shields are integral with the inner vessel. (author)

  5. Slurry reactor design studies

    Energy Technology Data Exchange (ETDEWEB)

    Fox, J.M.; Degen, B.D.; Cady, G.; Deslate, F.D.; Summers, R.L. (Bechtel Group, Inc., San Francisco, CA (USA)); Akgerman, A. (Texas A and M Univ., College Station, TX (USA)); Smith, J.M. (California Univ., Davis, CA (USA))

    1990-06-01

    The objective of these studies was to perform a realistic evaluation of the relative costs of tublar-fixed-bed and slurry reactors for methanol, mixed alcohols and Fischer-Tropsch syntheses under conditions where they would realistically be expected to operate. The slurry Fischer-Tropsch reactor was, therefore, operated at low H{sub 2}/CO ratio on gas directly from a Shell gasifier. The fixed-bed reactor was operated on 2.0 H{sub 2}/CO ratio gas after adjustment by shift and CO{sub 2} removal. Every attempt was made to give each reactor the benefit of its optimum design condition and correlations were developed to extend the models beyond the range of the experimental pilot plant data. For the methanol design, comparisons were made for a recycle plant with high methanol yield, this being the standard design condition. It is recognized that this is not necessarily the optimum application for the slurry reactor, which is being proposed for a once-through operation, coproducing methanol and power. Consideration is also given to the applicability of the slurry reactor to mixed alcohols, based on conditions provided by Lurgi for an Octamix{trademark} plant using their standard tubular-fixed reactor technology. 7 figs., 26 tabs.

  6. Reactor monitoring device

    International Nuclear Information System (INIS)

    Kono, Shigehiro.

    1996-01-01

    The device of the present invention monitors the stability of a power of a BWR type reactor by using each of recycling flow rates in addition to a reactor core flow rate to improve monitoring accuracy. Namely, a set value registering means is disposed for registering reactor core flow rate set values corresponding to the number of recycling flow rates not reaching a reference value for each of the recycling flow rates. A reactor flow rate take-out means judges whether each of the recycling flow rates reaches the reference value or not. The set values of the set value registering means are taken out based on the number of each of the recycling flow rate signals not reaching the reference values. The taken out set value and calculated reactor core flow rate value are compared by an abnormal alarm means. When calculated value is smaller than the set value, abnormality is informed. The accuracy for the monitoring is improved by monitoring the reactor power by using each of recycling flow rates in addition to the reactor core flow rate. (I.S.)

  7. Nuclear reactor control column

    International Nuclear Information System (INIS)

    Bachovchin, D.M.

    1982-01-01

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

  8. The integral fast reactor

    International Nuclear Information System (INIS)

    Till, C.E.

    1987-01-01

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

  9. Reactor container cooling device

    Energy Technology Data Exchange (ETDEWEB)

    Ando, Koji; Kinoshita, Shoichiro

    1995-11-10

    The device of the present invention efficiently lowers pressure and temperature in a reactor container upon occurrence of a severe accident in a BWR-type reactor and can cool the inside of the container for a long period of time. That is, (1) pipelines on the side of an exhaustion tower of a filter portion in a filter bent device of the reactor container are in communication with pipelines on the side of a steam inlet of a static container cooling device by way of horizontal pipelines, (2) a back flow check valve is disposed to horizontal pipelines, (3) a steam discharge valve for a pressure vessel is disposed closer to the reactor container than the joint portion between the pipelines on the side of the steam inlet and the horizontal pipelines. Upon occurrence of a severe accident, when the pressure vessel should be ruptured and steams containing aerosol in the reactor core should be filled in the reactor container, the inlet valve of the static container cooling device is closed. Steams are flown into the filter bent device of the reactor container, where the aerosols can be removed. (I.S.).

  10. Reactor safety device

    International Nuclear Information System (INIS)

    Okada, Yasumasa.

    1987-01-01

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

  11. Inherently safe reactors

    International Nuclear Information System (INIS)

    Maartensson, Anders

    1992-01-01

    A rethinking of nuclear reactor safety has created proposals for new designs based on inherent and passive safety principles. Diverging interpretations of these concepts can be found. This article reviews the key features of proposed advanced power reactors. An evaluation is made of the degree of inherent safety for four different designs: the AP-600, the PIUS, the MHTGR and the PRISM. The inherent hazards of today's most common reactor principles are used as reference for the evaluation. It is concluded that claims for the new designs being inherently, naturally or passively safe are not substantiated by experience. (author)

  12. Reactor safety assessment system

    International Nuclear Information System (INIS)

    Sebo, D.E.; Bray, M.A.; King, M.A.

    1987-01-01

    The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSA is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category

  13. Fast breeder reactors

    International Nuclear Information System (INIS)

    1978-01-01

    The subject of this invention is a liquid metal cooled nuclear reactor construction in which a concrete pit is lagged to protect it from the heat radiated from the reactor in normal operation but in which the efficiency of the lagging is reduced in case of emergency to allow the excess heat generated by the reactor to be dissipated throughout the pit. The lagging is in two layers, the first covering the internal surface of the pit wall is impermeable to the liquid metal, whilst the second layer over the first is permeable [fr

  14. Reactor shutdown device

    International Nuclear Information System (INIS)

    Masuda, Hiroyuki.

    1983-01-01

    Purpose : To provide a reactor shutdown device suitable to the low temperature shutdown of a heavy water-moderated type nuclear reactor and capable of ensuring an adequate shutdown margin. Constitution : Xenon reactivity is calculated based on the detection signals for reactor neutrons, the temperature reactivity is calculated based on the temperature of the moderators and of the coolants and, further, poisons in the moderators are detected. Injection amount of the poisons is calculated based on the result of the calculation and the detection, and the calculated amount of poisons is injected into the moderators. (Kamimura, M.)

  15. Mirror machine reactors

    International Nuclear Information System (INIS)

    Carlson, G.A.; Moir, R.W.

    1976-01-01

    Recent mirror reactor conceptual design studies are described. Considered in detail is the design of ''standard'' Yin-Yang fusion power reactors with classical and enhanced confinement. It is shown that to be economically competitive with estimates for other future energy sources, mirror reactors require a considerable increase in Q, or major design simplifications, or preferably both. These improvements may require a departure from the ''standard'' configuration. Two attractive possibilities, both of which would use much of the same physics and technology as the ''standard'' mirror, are the field reversed mirror and the end-stoppered mirror

  16. Reactor flux calculations

    Energy Technology Data Exchange (ETDEWEB)

    Lhuillier, D. [Commissariat à l' Énergie Atomique et aux Énergies Alternatives, Centre de Saclay, IRFU/SPhN, 91191 Gif-sur-Yvette (France)

    2013-02-15

    The status of the prediction of reactor anti-neutrino spectra is presented. The most accurate method is still the conversion of total β spectra of fissionning isotopes as measured at research reactors. Recent re-evaluations of the conversion process led to an increased predicted flux by few percent and were at the origin of the so-called reactor anomaly. The up to date predictions are presented with their main sources of error. Perspectives are given on the complementary ab-initio predictions and upcoming experimental cross-checks of the predicted spectrum shape.

  17. Reactor pressure tank

    International Nuclear Information System (INIS)

    Dorner, H.; Scholz, M.; Jungmann, A.

    1975-01-01

    In a reactor pressure tank for a nuclear reactor, self-locking hooks engage a steel ring disposed over the removable cover of the steel vessel. The hooks exert force upon the cover to maintain the cover in a closed position during operation of the reactor pressure tank. The force upon the removal cover is partly the result of the increasing temperature and thermal expansion of the steel vessel during operation. The steel vessel is surrounded by a reinforced-concrete tank. (U.S.)

  18. Licensed operating reactors

    International Nuclear Information System (INIS)

    1990-04-01

    The Operating Units Status Report --- Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff on NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non- power reactors in the US

  19. Reactor BR2: Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. A safety audit was conduced by the IAEA, the conclusions of which demonstrated the excellent performance of the plant in terms of operational safety. In 1999, the CALLISTO facility was extensively used for various programmes involving LWR pressure vessel materials, IASCC of LWR structural materials, fusion reactor materials and martensic steels for use in ADS systems. In 1999, BR2's commercial programmes were further developed

  20. Nuclear reactor theory

    International Nuclear Information System (INIS)

    Sekimoto, Hiroshi

    2007-09-01

    This textbook is composed of two parts. Part 1 'Elements of Nuclear Reactor Theory' is composed of only elements but the main resource for the lecture of nuclear reactor theory, and should be studied as common knowledge. Much space is therefore devoted to the history of nuclear energy production and to nuclear physics, and the material focuses on the principles of energy production in nuclear reactors. However, considering the heavy workload of students, these subjects are presented concisely, allowing students to read quickly through this textbook. (J.P.N.)

  1. Power reactor design trends

    International Nuclear Information System (INIS)

    Hogan, W.J.

    1985-01-01

    Cascade and Pulse Star represent new trends in ICF power reactor design that have emerged in the last few years. The most recent embodiments of these two concepts, and that of the HYLIFE design with which they will compare them, are shown. All three reactors depend upon protecting structural elements from neutrons, x rays and debris by injecting massive amounts of shielding material inside the reaction chamber. However, Cascade and Pulse Star introduce new ideas to improve the economics, safety, and environmental impact of ICF reactors. They also pose different development issues and thus represent technological alternatives to HYLIFE

  2. Reactor power control system

    International Nuclear Information System (INIS)

    Tomisawa, Teruaki.

    1981-01-01

    Purpose: To restore reactor-power condition in a minimum time after a termination of turbine bypass by reducing the throttling of the reactor power at the time of load-failure as low as possible. Constitution: The transient change of the internal pressure of condenser is continuously monitored. When a turbine is bypassed, a speed-control-command signal for a coolant recirculating pump is generated according as the internal pressure of the condenser. When the signal relating to the internal pressure of the condenser indicates insufficient power, a reactor-control-rod-drive signal is generated. (J.P.N.)

  3. 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

  4. Reactors of the world

    International Nuclear Information System (INIS)

    1971-01-01

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

  5. Elmo Bumpy Torus Reactor

    International Nuclear Information System (INIS)

    McAlees, D.G.; Uckan, N.A.; Lidsky, L.M.

    1976-01-01

    In the Elmo Bumpy Torus Reactor (EBTR) study the feasibility of achieving a fusion power plant based on the EBT confinement concept was evaluated. If the present understanding of the physics can be extrapolated to reactor scale devices the reactor could operate at high beta, high power density, and at steady state. The high aspect ratio of the device eases the accessibility, structural design and remote maintenance problems which are common to low aspect ratio machines. A version of the EBTR reference design described here could be constructed with only minor extrapolations in available technology

  6. Nuclear reactor safety system

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1983-01-01

    The invention provides a safety system for a nuclear reactor which uses a parallel combination of computer type look-up tables each of which receives data on a particular parameter (from transducers located in the reactor system) and each of which produces the functional counterpart of that particular parameter. The various functional counterparts are then added together to form a control signal for shutting down the reactor. The functional counterparts are developed by analysis of experimental thermal and hydraulic data, which are used to form expressions that define safe conditions

  7. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2001-01-01

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the behaviour of fusion reactor materials and components during and after irradiation. Ongoing projects include: the study of the mechanical behaviour of structural materials under neutron irradiation; the investigation of the characteristics of irradiated first wall material such as beryllium; the detection of abrupt electrical degradation of insulating ceramics under high temperature and neutron irradiation; and the study of dismantling and waste disposal strategy for fusion reactors. Progress and achievements in these areas in 2000 are discussed

  8. First Algerian research reactor

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    In 1985, both the Algerian Commissariat of New Energies and the Argentine National Atomic Energy Commission plus the firm INVAP S.E., started a series of mutual visits aimed at defining the mechanisms for cooperation in the nuclear field. Within this framework, a commercial contract was undersigned covering the supply of a low-power reactor (RUN), designed for basic and applied research in the fields of reactor physics and nuclear engineering. The reactor may also be used for performing experiences with neutron beams, for the irradiation of several materials and for the training of technicians, scientists and operators [es

  9. Fast Breeder Reactor studies

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.; Kittel, J.H.; Fauske, H.K.; Lineberry, M.J.; Stevenson, M.G.; Amundson, P.I.; Dance, K.D.

    1980-07-01

    This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts

  10. NUCLEAR REACTOR FUEL SYSTEMS

    Science.gov (United States)

    Thamer, B.J.; Bidwell, R.M.; Hammond, R.P.

    1959-09-15

    Homogeneous reactor fuel solutions are reported which provide automatic recombination of radiolytic gases and exhibit large thermal expansion characteristics, thereby providing stability at high temperatures and enabling reactor operation without the necessity of apparatus to recombine gases formed by the radiolytic dissociation of water in the fuel and without the necessity of liquid fuel handling outside the reactor vessel except for recovery processes. The fuels consist of phosphoric acid and water solutions of enriched uranium, wherein the uranium is in either the hexavalent or tetravalent state.

  11. Fast Breeder Reactor studies

    Energy Technology Data Exchange (ETDEWEB)

    Till, C.E.; Chang, Y.I.; Kittel, J.H.; Fauske, H.K.; Lineberry, M.J.; Stevenson, M.G.; Amundson, P.I.; Dance, K.D.

    1980-07-01

    This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts.

  12. Fusion reactor radioactive waste management

    International Nuclear Information System (INIS)

    Kaser, J.D.; Postma, A.K.; Bradley, D.J.

    1976-01-01

    Quantities and compositions of non-tritium radioactive waste are estimated for some current conceptual fusion reactor designs, and disposal of large amounts of radioactive waste appears necessary. Although the initial radioactivity of fusion reactor and fission reactor wastes are comparable, the radionuclides in fusion reactor wastes are less hazardous and have shorter half-lives. Areas requiring further research are discussed

  13. Special lecture on nuclear reactor

    International Nuclear Information System (INIS)

    Jo, Nam Jin

    1993-08-01

    This book gives a special lecture on nuclear reactor, which is divided into two parts. The first part has explanation on nuclear design of nuclear reactor and analysis of core with theories of integral transports, diffusion Nodal, transports Nodal and Monte Carlo skill parallel computer and nuclear calculation and speciality of transmutation reactor. The second part deals with speciality of nuclear reactor and control with nonlinear stabilization of nuclear reactor, nonlinear control of nuclear reactor, neural network and control of nuclear reactor, control theory of observer and analysis method of Adomian.

  14. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    1975-11-01

    Research activities in fiscal 1974 in Reactor Engineering Division of eight laboratories and computing center are described. Works in the division are closely related with the development of a multi-purpose High-temperature Gas Cooled Reactor, the development of a Liquid Metal Fast Breeder Reactor in Power Reactor and Nuclear Fuel Development Corporation, and engineering of thermonuclear fusion reactors. They cover nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology and aspects of the computing center. (auth.)

  15. RA Reactor applications, Annex A

    International Nuclear Information System (INIS)

    Cupac, S.; Vukadin, Z.

    2000-01-01

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

  16. RA Reactor applications, Annex A

    International Nuclear Information System (INIS)

    Cupac, S.; Vukadin, Z.

    1998-01-01

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

  17. RA Reactor applications, Annex A

    International Nuclear Information System (INIS)

    Cupac, S.; Vukadin, Z.

    1996-01-01

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

  18. Nuclear reactor container

    International Nuclear Information System (INIS)

    Takahashi, Hiroyuki.

    1987-01-01

    Purpose: To improve the earthquake proofness and also increase the safety to a nuclear reactor container by preventing bucklings upon earthquake. Constitution: A device for absorbing the deformation exerted from nuclear reactor buildings is disposed to a suppression chamber constituting a reactor container. When a nclear power plant encounters earthquakes, the entire reactor buildings are shaken and deformations of buildings are transmitted by way of building shell walls to a container and the forcive deforming forces are absorbed in the deformation absorbing device. That is, bellows are formed at the base of the container, which are deformed by the deforming forces to absorb the forcive deforming amount to moderate the stresses resulted to the suppression chamber. Thus, the rigidity to the bending of the container can be reduced and allowable displacement to the bucklings can be increased to prevent the buckling, by which earthquake proofness is improved and the safety is increased. (Kamimura, M.)

  19. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E.D.

    1981-01-01

    An array of rods comprising zirconium alloy sheathed nuclear fuel pellets assembled to form a fuel element for a pressurised water reactor is claimed. The helium gas pressure within each rod differs substantially from that of its closest neighbours

  20. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Hindle, E.D.

    1984-01-01

    The fuel elements for a pressurised water reactor comprise arrays of rods of zirconium alloy sheathed nuclear fuel pellets. The helium gas pressure within each rod differs substantially from that of its closest neighbours

  1. Nuclear reactor (1960)

    International Nuclear Information System (INIS)

    Maillard, M.L.

    1960-01-01

    The first French plutonium-making reactors G1, G2 and G3 built at Marcoule research center are linked to a power plant. The G1 electrical output does not offset the energy needed for operating this reactor. On the contrary, reactors G2 and G3 will each generate a net power of 25 to 30 MW, which will go into the EDF grid. This power is relatively small, but the information obtained from operation is great and will be helpful for starting up the power reactor EDF1, EDF2 and EDF3. The paper describes how, previous to any starting-up operation, the tests performed, especially those concerned with the power plant and the pressure vessel, have helped to bring the commissioning date closer. (author) [fr

  2. Backfitting of research reactors

    International Nuclear Information System (INIS)

    Delrue, R.; Noesen, T.

    1985-01-01

    The backfitting of research reactors covers a variety of activities. 1. Instrumentation and control: Control systems have developed rapidly and many reactor operators wish to replace obsolete equipment by new systems. 2. Pool liners: Some pools are lined internally with ceramic tiles. These may become pervious with time necessitating replacement, e.g. by a new stainless steel liner. 3. Heat removal system: Deficiencies can occur in one or more of the cooling system components. Upgrading may require modifications of the system such as addition of primary loops, introduction of deactivation tanks, pump replacement. Recent experience in such work has shown that renewal, backfitting and upgrading of an existing reactor is economically attractive since the related costs and delivery times are substantially lower than those required to install a new research reactor

  3. Ageing of research reactors

    International Nuclear Information System (INIS)

    Ciocanescu, M.

    2001-01-01

    Historically, many of the research institutions were centred on a research reactor facility as main technological asset and major source of neutrons for research. Important achievements were made in time in these research institutions for development of nuclear materials technology and nuclear safety for nuclear energy. At present, ageing of nuclear research facilities among these research reactors and ageing of staff are considerable factors of reduction of competence in research centres. The safe way of mitigation of this trend deals with ageing management by so called, for power reactors, Plant Life Management and new investments in staff as investments in research, or in future resources of competence. A programmatic approach of ageing of research reactors in correlation with their actual and future utilisation, will be used as a basis for safety evaluation and future spending. (author)

  4. Integrated nuclear reactor

    International Nuclear Information System (INIS)

    Pales, I.; Hasko, V.

    1984-01-01

    The reactor is provided with an integrated circuit of primary medium circulation with hydraulic pump drive. The pump drive which is a blade hydraulic facility is placed in the reactor vessel together with the pump. The primary medium flows through the core and enters the inter-tube space of the secondary circuit heat exchanger. The secondary circuit medium is supplied under the bottom tube plate with a supply pipe. From it the flow of secondary medium is directed to the blades of the hydraulic facility, e.g. the turbine. The turbine drives the pump which transports the primary medium to the reactor core. The secondary medium enters the heat exchanger tubes and through their walls receives the heat from the primary medium. This design reduces capital costs of the reactor and increases its safety. (E.S.)

  5. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2001-04-01

    The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given.

  6. Inertial thermonuclear reactors

    International Nuclear Information System (INIS)

    Madarame, Haruki; Oomura, Hiroshi; Nakamura, Norio.

    1984-01-01

    Purpose: To improve the durability of the first wall. Constitution: A reactor cavity for performing inertial thermofusion is defined within a vessel of a thermonuclear reactor, and the first wall of a tubular structure flowing coolants for taking out thermonuclear energy generated in the reactor cavity as the heat energy to the outside of the reactor is disposed, in which jet nozzles are disposed to the inside of the first wall that pulse-width jet coolants to form coolant membranes on the inner circumferential surface of the first wall to thereby surround the fire ball by the membrane of the coolants. Thus, the energy of the fire ball can be reduced by the membrane of the coolants, whereby the thermal loads and impact loads to the first wall can be moderated to substantially increase the working life and improve the safety of the first wall for which the greatest stress load is expected. (Yoshihara, H.)

  7. Reactor pressure vessel support

    International Nuclear Information System (INIS)

    Butti, J.P.

    1978-01-01

    A link and pin support system provides the primary vertical and lateral support for a nuclear reactor pressure vessel without restricting thermally induced radial and vertical expansion and contraction

  8. Pressure tube reactor

    International Nuclear Information System (INIS)

    Matsumoto, Tomoyuki; Fujino, Michihira.

    1980-01-01

    Purpose: To equalize heavy water flow distribution by providing a nozzle for externally injecting heavy water from a vibration preventive plate to the upper portion to feed the heavy water in a pressure tube reactor and swallowing up heavy water in a calandria tank to supply the heavy water to the reactor core above the vibration preventive plate. Constitution: A moderator injection nozzle is mounted on the inner wall of a calandria tank. Heavy water is externally injected above the vibration preventive plate, and heavy water in the calandria tank is swallowed up to supply the heavy water to the core reactor above the vibration preventive plate. Therefore, the heavy water flow distribution can be equalized over the entire reactor core, and the distribution of neutron absorber dissolved in the heavy water is equalized. (Yoshihara, H.)

  9. Nuclear reactor core catcher

    International Nuclear Information System (INIS)

    1977-01-01

    A nuclear reactor core catcher is described for containing debris resulting from an accident causing core meltdown and which incorporates a method of cooling the debris by the circulation of a liquid coolant. (U.K.)

  10. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Till, C.E.

    1985-01-01

    During the past two years, scientists from Argonne have developed an advanced breeder reactor with a closed self contained fuel cycle. The Integral Fast Reactor (IFR) is a new reactor concept, adaptable to a variety of designs, that is based on a fuel cycle radically different from the CRBR line of breeder development. The essential features of the IFR are metal fuel, pool layout, and pyro- and electro-reprocessing in a facility integral with the reactor plant. The IFR shows promise to provide an inexhaustible, safe, economic, environmentally acceptable, and diversion resistant source of nuclear power. It shows potential for major improvement in all of the areas that have led to concern about nuclear power

  11. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2002-01-01

    The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system

  12. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2002-04-01

    The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system.

  13. Fusion Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2002-04-01

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed.

  14. Reactor vessel sealing plug

    International Nuclear Information System (INIS)

    Dooley, R.A.

    1986-01-01

    This invention relates to an apparatus and method for sealing the cold leg nozzles of a nuclear reactor pressure vessel from a remote location during maintenance and inspection of associated steam generators and pumps while the pressure vessel and refueling canal are filled with water. The apparatus includes a sealing plug for mechanically sealing the cold leg nozzle from the inside of a reactor pressure vessel. The sealing plugs include a primary and a secondary O-ring. An installation tool is suspended within the reactor vessel and carries the sealing plug. The tool telescopes to insert the sealing plug within the cold leg nozzle, and to subsequently remove the plug. Hydraulic means are used to activate the sealing plug, and support means serve to suspend the installation tool within the reactor vessel during installation and removal of the sealing plug

  15. Small reactor operating mode

    International Nuclear Information System (INIS)

    Snell, V.G.

    1997-01-01

    There is a potential need for small reactors in the future for applications such as district heating, electricity production at remote sites, and desalination. Nuclear power can provide these at low cost and with insignificant pollution. The economies required by the small scale application, and/or the remote location, require a review of the size and location of the operating staff. Current concepts range all the way from reactors which are fully automatic, and need no local attention for days or weeks, to those with reduced local staff. In general the less dependent a reactor is on local human intervention, the greater its dependence on intrinsic safety features such as passive decay heat removal, low-stored energy and limited reactivity speed and depth in the control systems. A case study of the design and licensing of the SLOWPOKE Energy System heating reactor is presented. (author)

  16. New reactor type proposed

    CERN Multimedia

    2003-01-01

    "Russian scientists at the Research Institute of Nuclear Power Engineering in Moscow are hoping to develop a new reactor that will use lead and bismuth as fuel instead of uranium and plutonium" (1/2 page).

  17. Pulsed fusion reactors

    International Nuclear Information System (INIS)

    1975-01-01

    This summer school specialized in examining specific fusion center systems. Papers on scientific feasibility are first presented: confinement of high-beta plasma, liners, plasma focus, compression and heating and the use of high power electron beams for thermonuclear reactors. As for technological feasibility, lectures were on the theta-pinch toroidal reactors, toroidal diffuse pinch, electrical engineering problems in pulsed magnetically confined reactors, neutral gas layer for heat removal, the conceptual design of a series of laser fusion power plants with ''Saturn'', implosion experiments and the problem of the targets, the high brightness lasers for plasma generation, and topping and bottoming cycles. Some problems common to pulsed reactors were examined: energy storage and transfer, thermomechanical and erosion effects in the first wall and blanket, the problems of tritium production, radiation damage and neutron activation in blankets, and the magnetic and inertial confinement

  18. Pressurized water reactor systems

    International Nuclear Information System (INIS)

    Meyer, P.J.

    1975-01-01

    Design and mode of operation of the main PWR components are described: reactor core, pressure vessel and internals, cooling systems with pumps and steam generators, ancillary systems, and waste processing. (TK) [de

  19. Açıklıklı Kutuların Analizinde Etkin Bir Hibrid MoM/FEM Yöntemi

    Directory of Open Access Journals (Sweden)

    SİBEL YENİKAYA

    2011-03-01

    Full Text Available Bu makalede, açıklığa sahip bir kutunun içerisindeki alan dağılımını bulmak için frekans domeninde moment metodu (MoM ile kenar tabanlı vektörel sonlu elemanlar metodunu (FEM birleştiren hibrit bir formülasyon sunuldu. Açıklıktaki sınır koşulundan elde edilen integral denklemin çözümü için moment metodu kullanılırken, kutunun içerisindeki elektromanyetik alanların çözümü için sonlu elemanlar metodu kullanıldı. Açıklığa sahip kutunun ekranlama etkinliği ve depolanan elektriksel enerji hibrit yöntem ile hesaplandı ve literatürdeki sonuçlar ile karşılaştırılarak doğrulandı. Daha sonra bu yöntem farklı açıklık boyutlarına sahip farklı kutulara uygulandı.

  20. Ayran Üretim Metotları Üzerine Karşılaştırmalı Bir Çalışma

    Directory of Open Access Journals (Sweden)

    Celalettin Koçak

    2015-02-01

    Full Text Available Ayran, yoğurt, tuz ve sudan oluşan, geleneksel bir Türk içeceğidir. Ticari olarak Ayran iki şekilde üretilmektedir. Bu iki üretim şekli arasındaki başlıca fark, inkübasyondan önce Ayran sütüne su ilave edilmesi veya inkübasyondan sonra yoğurda suyun ilave edilmesidir. Bu nedenle bu araştırma, bu iki üretim metodunun Ayranın kimyasal, mikrobiyolojik ve duyusal özellikleri üzerindeki etkilerini araştırmayı amaçlamaktadır. Elde edilen sonuçlar, üretim metotlarının Ayranın genel bileşimi ve tüketici beğenisi üzerinde herhangi bir etkilerinin bulunmadığını göstermiştir (P >0.05. Ancak, yoğurda su katılarak üretilen ayranların asetaldehit içeriklerinde 7. gün depolamada, S. thermophilus içeriğinde ise 1. gün depolamada diğer metoda göre daha düşük değerler elde edilmiştir (P < 0.05.

  1. İş havacılığı teknisyenlerinde iş tatmini ve bir araştırma

    OpenAIRE

    Uyar, Tevfik

    2012-01-01

    Havacılık faaliyetleri doğaları gereği çeşitli riskler içerir ve bu risklerin bertaraf edilmesi için verimli bir emniyet yönetimi gerçekleştirilmesi zorunludur. Emniyet yönetimi kazaların sebeplerini kaza öncesi ya da sonrasında anlayarak bu sebeplerin bertarafı yoluyla kazaların gerçekleşmesini önlemeyi amaçlar. Günümüzdeki kazaların çok büyük bir çoğunluğu makina ya da teknoloji kaynaklı değil, insan kaynaklıdır. Havacılık emniyet yönetiminde en çok kullanılan iki model, Reason ve SHELL mod...

  2. Kronik Enfekte Yaralı Bir Köpekte Kına (Lawsonia inermis) Bitkisinin Tedavi Amaçlı Kullanılması

    OpenAIRE

    POLAT, Eren

    2014-01-01

    Bu çalışmada olgumuzu, Fırat Üniversitesi Veteriner Fakültesi Hayvan Hastanesi Cerrahi Kliniği’ne getirilen ön sol bacağının anterior yüzü ile medialinde, arka sol bacağının ise medialinde iki adet maddi kayıplı yarası bulunan bir sokak köpeği oluşturmuştur. Bu çalışmada her iki yara içinde belli oranlarda kına, tereyağı ve tentürdiyottan oluşan karışım hazırlanarak bölgeye tatbik edilmiş ve 3., 6., 9., 12., 15. ve 18. günlerde yaralar kontrol edilmiştir. Sonuç olarak; çalışmada hızlı bir yar...

  3. Librarians and Marketing: An Ambiguous Relationship Kütüphaneciler ve Pazarlama: Belirsizlikler Taşıyan Bir İlişki

    Directory of Open Access Journals (Sweden)

    Rejean Savard

    1996-12-01

    Full Text Available While librarians show a growing interest for marketing, their concept of marketing seems inaccurate. Librarians' outlook is mostly organizational, and focused on salesand product-oriented strategies which fail to embrace a truly client-centered marketing orientation. After a brief review of the literature, the author reports on a qualitative study confirming that the marketing orientation, as defined by experts, is insufficiently developed among librarians. Kütüphanecilerin pazarlama konusuna olan ilgileri artmakla beraber, pazarlama kavramı konusundaki bilgileri hatalı görünmektedir. Kütüphaneciler, genelde kurumsal bir yaklaşımı benimsemiş görünmektedirler ve üzerinde yoğunlaştıkları satış ve-ürün odaklı stratejiler, gerçek anlamda müşteri-odaklı pazarlama yaklaşımını kapsamaktan uzaktır. Yazar, konuyla ilgili yayınları kısaca gözden geçirdikten sonra, kütüphaneciler arasında, uzmanlarca tanımlanan pazarlama yönetiminin yeterince gelişmediğini doğrulayan niteliksel bir araştırma hakkında bilgi vermektedir.

  4. Majör Depresif Bozuklukta Tedaviye (Kýsa Mesaj SMS eklemesi: Bir Pilot Çalýþma

    Directory of Open Access Journals (Sweden)

    Direnç SAKARYA

    2013-04-01

    Full Text Available Mobil saðlýk uygulamalarý, özellikle koruyucu saðlýk hizmeti sunma anlamýnda giderek yaygýnlaþmaktadýr (Pal 2003. Uygulamalar internet ve cep telefonu gibi mevcut teknolojik altyapýlar aracýlýðý ile sunulmaktadýr. Bu alanda daha önce yapýlan çalýþmalardaki müdahaleler büyük oranda davranýþ deðiþimine odaklanmakta ve genellikle beden aðýrlýðýnýn azaltýlmasý ya da kontrolünü hedeflemektedir (Cole-Lewis ve Kershaw 2010. Göreceli olarak eski bir teknoloji olmasý nedeniyle kýsa mesaj (SMS, mobil saðlýk alanýnda hastaya ulaþýmda tercih edilen yollardan biridir. Araþtýrmamýzda, hastalara her gün gönderilen SMS’lerin depresif bozukluklarýn tedavisinde, standart tedavilere ek olarak herhangi bir olumlu etkisinin olup olmadýðýný saptamayý hedefledik. [JCBPR 2013; 2(1.000: 60-61

  5. Coğrafi Bilgi Sistemlerinde Etik Tartışmalar: Eleştirel CBS’ye Yönelik Bir Literatür Analizi

    OpenAIRE

    ŞEREMET, Mehmet; ALAEDDİNOĞLU, Faruk

    2017-01-01

    Coğrafya’nın kantitatif devriminden sonra CBS’ye yönelik üretilen eleştirilere ek olarak CBS’nin eleştirel Coğrafya için önemini ve etkileşimini ortaya koymak amacıyla 1990’ların sonlarına doğru ortaya çıkmış ve Coğrafya araştırmalarının yakın tarihinde önemli bir yere sahip olmuştur. Bu bağlamda, E-CBS’nin Coğrafya’nın eleştirel kuramlarıyla (Marksist ve Feminist Coğrafya gibi) etkileşimli bir şekilde ortaya çıktığını ifade etmek çokta yanlış olmayacaktır. Temel olarak, E-CBS’yi özellikle 90...

  6. John Brown as an Independent Character from Warburton Circle / Warburton Camiası’ndan Bağımsız Bir Karakter Olarak John Brown

    Directory of Open Access Journals (Sweden)

    Pervin Yigit

    2017-09-01

    Full Text Available Abstract John Brown (1715-1766 and William Warburton (1698-1779 were two leading characters of the English Enlightenment. The enlightenment associated with their works could provide a political, social and intellectual situation of eighteenth century Britain. Therefore, they are worthy of attention. Britain became a trans-oceanic commercial and colonial power in the first half of the century and thus the growth of commercial society and empire changed the character of the nation. Warburton’s works were presenting a complicated programme for reform. Warburton and also his party (Warburton circle aimed to preserve the Great Britain from the effects of intolerance, superstition, religious enthusiasm and religious division. They aimed to maintain the Anglican establishment. Brown who was considered as a loyal member of Warburton circle, regardless their fall out later, introduced reform strategies for the eighteenth century Britain like other members. In this paper it is indicated that Brown was developing a different reform agenda to that of William Warburton. I argue that the Brown’s main work “An Estimate of the Manners and Principles of The Times” (1757 can actually be read as a refutation of Warburton’s thoughts and of the reform strategies developed by members of his circle and thus Brown need to be considered as a self-directed political reformist.   Öz John Brown (1715-1766 ve William Warburton (1698-1779 İngiliz Aydınlaması’nın en önemli karakterlerindendir. Her ikisinin de yapıtları 18. yüzyıl İngilteresi’nin siyasi, sosyal ve entellektüel durumunu ve dolayısı ile İngiliz Aydınlanması’nı bize gösterdikleri için, çalışmaya değerdir. Britanya 18. yüzyılın ilk yarısında okyanus aşırı ticari bir güç ve bir sömürge imparatorluğu olduğu için, ulusun karakteri değişikliğe uğramıştır. Bu sebepten Warburton, eserleri aracılığı ile İngiltere için ulusal bir reform program sunar. O

  7. K-Reactor readiness

    International Nuclear Information System (INIS)

    Rice, P.D.

    1991-01-01

    This document describes some of the more significant accomplishments in the reactor restart program and details the magnitude and extent of the work completed to bring K-Reactor to a state of restart readiness. The discussion of restart achievements is organized into the three major categories of personnel, programs, and plant. Also presented is information on the scope and extent of internal and external oversight of the efforts, as well as some details on the startup plan

  8. Polymeric Membrane Reactors

    OpenAIRE

    José M. Sousa; Luís M. Madeira; João C. Santos; Adélio Mendes

    2008-01-01

    The aim of this chapter is the study of membrane reactors with polymeric membranes, particularly catalytic polymeric membranes. After an introduction where the main advantages and disadvantages of the use of polymeric membranes are summarised, a review of the main areas where they have been applied, integrated in chemical reactors, is presented. This excludes the field of bio-membranes processes, which is analysed in a specific chapter of this book. Particular attention is then given to model...

  9. Alternative breeder reactor technologies

    International Nuclear Information System (INIS)

    Spinrad, B.I.

    1978-01-01

    The significance of employing breeder reactors to stretch the world resources of nuclear fuels is briefly discussed, and the various types of breeder concepts are described. General descriptions, advantages, and disadvantages of the liquid metal cooled fast breeder, gas cooled fast breeder, molten salt breeder, thermal breeders, and spectral-shift control reactors are presented. Aspects of safeguarding fissile material connected with breeder operation are examined. 31 references

  10. Reactor Neutron Sources

    International Nuclear Information System (INIS)

    Aksenov, V.L.

    1994-01-01

    The present status and the prospects for development of reactor neutron sources for neutron scattering research in the world are considered. The fields of application of neutron scattering relative to synchrotron radiation, the creation stages of reactors (steady state and pulsed) and their position in comparison with spallation neutron sources at present and in the foreseen future are discussed. (author). 15 refs.; 8 figs.; 3 tabs

  11. KS-150 reactor control

    International Nuclear Information System (INIS)

    Wagner, K.

    1974-01-01

    A thorough description is presented of the control and protection system of the Bohunice A-1 reactor. The system including auxiliary facilities was developed, manufactured and installed at the reactor by the SKODA Works, Plzen. The system parameters are listed and a brief account is also given of the development efforts and of the physical and power start-up of the A-1 nuclear power plant. (L.O.)

  12. The replacement research reactor

    International Nuclear Information System (INIS)

    Cameron, R.; Horlock, K.

    2001-01-01

    The contract for the design, construction and commissioning of the Replacement Research Reactor was signed in July 2000. This was followed by the completion of the detailed design and an application for a construction licence was made in May 2001. This paper will describe the main elements of the design and their relation to the proposed applications of the reactor. The future stages in the project leading to full operation are also described

  13. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    Butterfield, C.E.; Waite, E.

    1982-01-01

    A nuclear reactor fuel element comprising a column of vibration compacted fuel which is retained in consolidated condition by a thimble shaped plug. The plug is wedged into gripping engagement with the wall of the sheath by a wedge. The wedge material has a lower coefficient of expansion than the sheath material so that at reactor operating temperature the retainer can relax sufficient to accommodate thermal expansion of the column of fuel. (author)

  14. OECD Halden reactor project

    International Nuclear Information System (INIS)

    1978-01-01

    This report summarizes the activities of the OECD Halden Reactor Project for the year 1976. The main items reported on are: a) the process supervision and control which have focused on core monitoring and control, and operator-process communication; b) the fuel performance and safety behavior which have provided data and analytical descriptions of the thermal, mechanical and chemical behavior of fuel under various operating conditions; c) the reactor operations and d) the administration and finance

  15. Generation IV reactors: economics

    International Nuclear Information System (INIS)

    Dupraz, B.; Bertel, E.

    2003-01-01

    The operating nuclear reactors were built over a short period: no more than 10 years and today their average age rounds 18 years. EDF (French electricity company) plans to renew its reactor park over a far longer period : 30 years from 2020 to 2050. According to EDF this objective implies 3 constraints: 1) a service life of 50 to 60 years for a significant part of the present operating reactors, 2) to be ready to built a generation 3+ unit in 2020 which infers the third constraint: 3) to launch the construction of an EPR (European pressurized reactor) prototype as soon as possible in order to have it operating in 2010. In this scheme, generation 4 reactor will benefit the feedback experience of generation 3 and will take over in 2030. Economic analysis is an important tool that has been used by the generation 4 international forum to select the likely future reactor systems. This analysis is based on 4 independent criteria: the basic construction cost, the construction time, the operation and maintenance costs and the fuel cycle cost. This analysis leads to the evaluation of the global cost of electricity generation and of the total investment required for each of the reactor system. The former defines the economic competitiveness in a de-regulated energy market while the latter is linked to the financial risk taken by the investor. It appears, within the limits of the assumptions and models used, that generation 4 reactors will be characterized by a better competitiveness and an equivalent financial risk when compared with the previous generation. (A.C.)

  16. Department of Reactor Technology

    DEFF Research Database (Denmark)

    Risø National Laboratory, Roskilde

    The general development of the Department of Reactor Technology at Risø during 1981 is presented, and the activities within the major subject fields are described in some detail. Lists of staff, publications, and computer programs are included.......The general development of the Department of Reactor Technology at Risø during 1981 is presented, and the activities within the major subject fields are described in some detail. Lists of staff, publications, and computer programs are included....

  17. Regulations for RA reactor operation

    International Nuclear Information System (INIS)

    1980-09-01

    Regulations for RA reactor operation are written in accordance with the legal regulations defined by the Law about radiation protection and related legal acts, as well as technical standards according to the IAEA recommendations. The contents of this book include: fundamental data about the reactor; legal regulations for reactor operation; organizational scheme for reactor operation; general and detailed instructions for operation, behaviour in the reactor building, performing experiments; operating rules for operation under steady state and accidental conditions [sr

  18. Reactor of the XXI century

    International Nuclear Information System (INIS)

    Zhotabaev, Zh.R.; Solov'ev, Yu.A.

    2001-01-01

    The advantages of both molten salt reactors (MSR) and homogenous molten salt reactors (HMSR) are illuminated. It is noted that the MSR possess accident probability A=10 -6 1/reactor.years and the HMSR with integral configuration has A=10 -7 1/reactor.years. The methods for these reactors technological problems solution - tritium removal, salt melt circulation and capacity pick up - are discussed

  19. Licensing of nuclear reactor operators

    International Nuclear Information System (INIS)

    1979-09-01

    Recommendations are presented for the licensing of nuclear reactor operators in units licensed according to the legislation in effect. They apply to all physical persons designated by the Operating Organization of the nuclear reactor or reactors to execute any of the following functional activities: a) to manipulate the controls of a definite reactor b) to direct the authorized activities of the reactor operators licesed according to the present recommendations. (F.E.) [pt

  20. Reactor power measuring device

    International Nuclear Information System (INIS)

    Ichige, Masayuki; Ishige, Takanori.

    1997-01-01

    The present invention provides a device for measuring a power such as of a nuclear fission reactor or a thermonuclear reactor by utilizing a light emitting phenomenon by radiation rays of gases. Namely, a measuring vessel sealed with a gas scintillator is inserted to the inside of a reactor. The measuring vessel is optically connected to a photoelectric convertor. The photoelectric convertor is electrically connected with a signal processing device. With such a constitution, gases sealed in the measuring vessel are ionized by radiation rays released in proportion to the power of the reactor to cause scintillation emission. The light is converted into electric signals by the photoelectric convertor. Reactor power can be monitored by the signal processing device having the electric signals as an input. According to the present invention, since the gas scintillation detector is used, the device is simplified and time responsiveness can be improved. As a result, the function of the reactor power measuring device can be improved. (I.S.)

  1. Materials for fusion reactors

    International Nuclear Information System (INIS)

    Ehrlich, K.; Kaletta, D.

    1978-03-01

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

  2. Fast breeder reactors

    International Nuclear Information System (INIS)

    Waltar, A.E.; Reynolds, A.B.

    1981-01-01

    This book describes the major design features of fast breeder reactors and the methods used for their design and analysis. The foremost objective of this book is to fulfill the need for a textbook on Fast Breeder Reactor (FBR) technology at the graduate level or the advanced undergraduate level. It is assumed that the reader has an introductory understanding of reactor theory, heat transfer, and fluid mechanics. The book is expected to be used most widely for a one-semester general course on fast breeder reactors, with the extent of material covered to vary according to the interest of the instructor. The book could also be used effectively for a two-quarter or a two-semester course. In addition, the book could serve as a text for a course on fast reactor safety since many topics other than those appearing in the safety chapters relate to FBR safety. Methodology in fast reactor design and analysis, together with physical descriptions of systems, is emphasized in this text more than numerical results. Analytical and design results continue to change with the ongoing evolution of FBR design whereas many design methods have remained fundamentally unchanged for a considerable time

  3. Nuclear reactors to come

    International Nuclear Information System (INIS)

    Lung, M.

    2002-01-01

    The demand for nuclear energy will continue to grow at least till 2050 because of mainly 6 reasons: 1) the steady increase of the world population, 2) China, India and Indonesia will reach higher social standard and their energy consumption will consequently grow, 3) fossil energy resources are dwindling, 4) coal will be little by little banned because of its major contribution to the emission of green house effect gas, 5) renewable energies need important technological jumps to be really efficient and to take the lead, and 6) fusion energy is not yet ready to take over. All these reasons draw a promising future for nuclear energy. Today 450 nuclear reactors are operating throughout the world producing 17% of the total electrical power demand. In order to benefit fully of this future, nuclear industry has to improve some characteristics of reactors: 1) a more efficient use of uranium (it means higher burnups), 2) a simplification and automation of reprocessing-recycling chain of processes, 3) efficient measures against proliferation and against any misuse for terrorist purposes, and 4) an enhancement of safety for the next generation of reactors. The characteristics of fast reactors and of high-temperature reactors will likely make these kinds of reactors the best tools for energy production in the second half of this century. (A.C.)

  4. BWR type reactor

    International Nuclear Information System (INIS)

    Watanabe, Shoichi

    1988-01-01

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

  5. Reactor operation method

    International Nuclear Information System (INIS)

    Osumi, Katsumi; Miki, Minoru.

    1979-01-01

    Purpose: To prevent stress corrosion cracks by decreasing the dissolved oxygen and hydrogen peroxide concentrations in the coolants within a reactor container upon transient operation such as at the start-up or shutdown of bwr type reactors. Method: After a condensate has been evacuated, deaeration operation is conducted while opening a main steam drain line, as well as a main steam separation valve and a by-pass valve in a turbine by-pass line connecting the main steam line and the condenser without by way of a turbine, and the reactor is started-up by the extraction of control rods after the concentration of dissolved oxygen in the cooling water within a pressure vessel has been decreased below a predetermined value. Nuclear heating is started after the reactor water has been increased to about 150 0 C by pump heating after the end of the deaeration operation for preventing the concentration of hydrogen peroxide and oxygen in the reactor water from temporarily increasing immediately after the start-up. The corrosive atmosphere in the reactor vessel can thus be moderated. (Horiuchi, T.)

  6. LMFBR type reactor

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  7. OECD Halden reactor project

    International Nuclear Information System (INIS)

    1979-01-01

    This is the nineteenth annual Report on the OECD Halden Reactor Project, describing activities at the Project during 1978, the last year of the 1976-1978 Halden Agreement. Work continued in two main fields: test fuel irradiation and fuel research, and computer-based process supervision and control. Project research on water reactor fuel focusses on various aspects of fuel behavior under normal, and off-normal transient conditions. In 1978, participating organisations continued to submit test fuel for irradiation in the Halden boiling heavy-water reactor, in instrumented test assemblies designed and manufactured by the Project. Work included analysis of the impact of fuel design and reactor operating conditions on fuel cladding behavior. Fuel performance modelling included characterization of thermal and mechanical behavior at high burn-up, of fuel failure modes, and improvement of data qualification procedures to reduce and quantify error bands on in-reactor measurements. Instrument development yielded new or improved designs for measuring rod temperature, internal pressure, axial neutron flux shape determination, and for detecting cladding defects. Work on computer-based methods of reactor supervision and control included continued development of a system for predictive core surveillance, and of special mathematical methods for core power distribution control

  8. The reactor antineutrino anomalies

    Energy Technology Data Exchange (ETDEWEB)

    Haser, Julia; Buck, Christian; Lindner, Manfred [Max-Planck-Institut fuer Kernphysik, Heidelberg (Germany)

    2016-07-01

    Major discoveries were made in the past few years in the field of neutrino flavour oscillation. Nuclear reactors produce a clean and intense flux of electron antineutrinos and are thus an essential neutrino source for the determination of oscillation parameters. Most currently the reactor antineutrino experiments Double Chooz, Daya Bay and RENO have accomplished to measure θ{sub 13}, the smallest of the three-flavour mixing angles. In the course of these experiments two anomalies emerged: (1) the reanalysis of the reactor predictions revealed a deficit in experimentally observed antineutrino flux, known as the ''reactor antineutrino anomaly''. (2) The high precision of the latest generation of neutrino experiments resolved a spectral shape distortion relative to the expected energy spectra. Both puzzles are yet to be solved and triggered new experimental as well as theoretical studies, with the search for light sterile neutrinos as most popular explanation for the flux anomaly. This talk outlines the two reactor antineutrino anomalies. Discussing possible explanations for their occurrence, recent and upcoming efforts to solve the reactor puzzles are highlighted.

  9. Gezi’nin Dili: Göstergebilimsel Bir İnceleme / The Language of Taksim Gezi Park Protests: A Semiotic Review

    Directory of Open Access Journals (Sweden)

    Ahmet GÜVEN

    2014-09-01

    Full Text Available Türkiye’nin yakın tarihinde meydana gelmiş olan ve birçok açıdan ilkleri barındıran Gezi Parkı Olayları, göstericilerin kullandıkları dil açısından da dikkat çekicidir. Özellikle sloganlar ve duvar yazıları şeklinde karşımıza çıkan bu farklı dil, olaylar esnasında da sıkça dile getirilmiş, pek çok köşe yazısına ve mizah dergisine de konu olmuştur. Önceki dönemlerdeki gösteri ve protestoların dillerine kıyasla Gezi’nin dili belirgin bir farklılık arz etmektedir. Dildeki bu değişim/dönüşüm toplumsal olayları okumak açısından anahtar niteliğindedir. Kültürün ve dolayısıyla toplumsal olayların dil gibi yapılandığı kabul edildiğinde doğrudan göstergebilimsel bir incelemenin alanına girilmiş olur. Bu çalışmada Gezi Parkı Olaylarındaki söylem göstergebilim kavramlarından olan metaforik ve metonimik bağlamlarda incelenecektir. Bunu yaparken Gezi Parkı Olayları sürecinde kullanılan sloganlar ve duvar yazıları temel alınacaktır. Bu slogan ve duvar yazılarının yapılarında metaforik düzlemden metonimik düzleme doğru bir dönüşüm olduğunu varsayıyoruz. Metonimik düzleme doğru meydana gelen dönüşümü ise toplumsal dönüşümün okunabilmesi için uygun bir anahtar olarak değerlendiriyoruz. / The protesters’ language used in Taksim Gezi Park Protests which has included many initials in many aspects in Turkey is remarkable. That this different language has been manifested especially in the form of slogans and graffitis has been subjected to many column and humor magazines during the protests. In comparison to older protests Gezi has many distinct differences. This transformation in language has played a key role to understand social movements. When we accept the culture and accordingly social movements are structured as language we enter the field of semiotics directly. The aim of this study is to examine the discourse of Gezi Park Protests in the

  10. The reactor Cabri

    International Nuclear Information System (INIS)

    Ailloud, J.; Millot, J.P.

    1964-01-01

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

  11. SM-2 reactor potentialities for investigation of fusion reactor materials

    International Nuclear Information System (INIS)

    Tsykanov, V.A.; Samsonov, B.V.; Markina, N.V.; Polyakov, Yu.N.; Sluzhaev, V.I.; Losev, N.P.; Lobanov, G.P.

    1981-01-01

    The possibility of utilization of the SM-2 type reactors for fusion reactor (FR) materials testing is discussed. The measuring and calculational results, while estimating irradiation conditions in the SM-2 reactor channels, are given. The basic characteristics, necessary for correct simulation of FR parameters in fission reactors such as neutron flux density, radiation damage in the shift per atom values, gas accumulation, are considered. The characteristics of existing and tested in the SM-2 reactor investigational methods for studying structural and isolation materials are given. The conclusion about the possibility of SM-2 reactor utilization for the FR materials testing is made [ru

  12. Materials for nuclear reactors

    International Nuclear Information System (INIS)

    Banerjee, S.; Kamath, H.S.

    2005-01-01

    The improved performance of present generation nuclear reactors and the realization of advanced reactor concepts, both, require development of better materials. Physical metallurgy/materials science principles which have been exploited in meeting the exacting requirements of nuclear reactor materials (fuels and structural materials), are outlined citing a few specific examples. While the incentive for improvement of traditional fuels (e.g., UO 2 fuel) is primarily for increasing the average core burn up, the development of advanced fuels (e.g., MOX, mixed carbide, nitride, silicide and dispersion fuels) are directed towards better utilization of fissile and fertile inventories through adaptation of innovative fuel cycles. As the burn up of UO 2 fuel reaches higher levels, a more detailed and quantitative understanding of the phenomena such as fission gas release, fuel restructuring induced by radiation and thermal gradients and pellet-clad interaction is being achieved. Development of zirconium based alloys for both cladding and pressure tube applications is discussed with reference to their physical metallurgy, fabrication techniques and in-reactor degradation mechanisms. The issue of radiation embrittlement of reactor pressure vessels (RPVs) is covered drawing a comparison between the western and eastern specifications of RPV steels. The search for new materials which can stand higher rates of atomic displacement due to radiation has led to the development of swelling resistant austenitic and ferritic stainless steels for fast reactor applications as exemplified by the development of the D-9 steel for Indian fast breeder reactor. The presentation will conclude by listing various materials related phenomena, which have a strong bearing on the successful development of future nuclear energy systems. (author)

  13. Method of operating a reactor

    International Nuclear Information System (INIS)

    Oosumi, Katsumi; Yamamoto, Michiyoshi.

    1980-01-01

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

  14. Sodium-cooled nuclear reactors

    International Nuclear Information System (INIS)

    Berthoud, Georges; Ducros, Gerard; Feron, Damien; Guerin, Yannick; Latge, Christian; Limoge, Yves; Santarini, Gerard; Seiler, Jean-Marie; Vernaz, Etienne; Guidez, Joel; Andrieux, Catherine; Baque, Francois; Bonin, Bernard; Boullis, Bernard; Cabet, Celine; Carre, Frank; Dufour, Philippe; Gauche, Francois; Grouiller, Jean-Paul; Jeannot, Jean-Philippe; Le Flem, Marion; Le Coz, Pierre; Martin, Laurent; Masson, Michel; Mathonniere, Gilles; Nokhamzon, Jean-Guy; Pelletier, Michel; Rodriguez, Gilles; Saez, Manuel; Seran, Jean-Louis; Varaine, Frederic; Zaetta, Alain; Behar, Christophe; Provitina, Olivier; Lecomte, Michael; Forestier, Alain; Bender, Alexandra; Parisot, Jean-Francois; Finot, Pierre

    2014-01-01

    This book first explains the choice of sodium-cooled reactors by outlining the reasons of the choice of fast neutron reactors (fast neutrons instead of thermal neutrons, recycling opportunity for plutonium, full use of natural uranium, nuclear waste optimization, flexibility of fast neutron reactors in nuclear material management, fast neutron reactors as complements of water-cooled reactors), and by outlining the reasons for the choice of sodium as heat-transfer material. Physical, chemical, and neutron properties of sodium are presented. The second part of the book first presents the main design principles for sodium-cooled fast neutron reactors and their core. The third part proposes an historical overview and an assessment of previously operated sodium-cooled fast neutron reactors (French reactors from Rapsodie to Superphenix, other reactors in the world), and an assessment of the main incidents which occurred in these reactors. It also reports the experience and lessons learned from the dismantling of various sodium-cooled fast breeder reactors in the world. The next chapter addresses safety issues (technical and safety aspects related to the use of sodium) and environmental issues (dosimetry, gaseous and liquid releases, solid wastes, and cooling water). Then, various technological aspects of these reactors are addressed: the energy conversion system, main components, sodium chemistry, sodium-related technology, advances in in-service inspection, materials used in reactors and their behaviour, and fuel system. The next chapter addresses the fuel cycle in these reactors: its integrated specific character, report of the French experience in fast neutron reactor fuel processing, description of the transmutation of minor actinides in these reactors. The last chapter proposes an overview of reactors currently projected or under construction in the world, presents the Astrid project, and gives an assessment of the economy of these reactors. A glossary and an index

  15. Seyyid Vehbi'nin Divanında Yer Almayan Bir Kasidesi The Kaside That Doesn’t Take Place In Divan Of Seyyid Vehbi

    Directory of Open Access Journals (Sweden)

    Haluk GÖKALP

    2013-03-01

    Full Text Available Perodicals include kinds of poems. In addition they comprise artistic and cultural accumulation when they were written. Pastiche collections give knowledge abaut pastiche tradition and interactions between poets. Poem notebooks which can collect diffrent subjects contribute to history of literatüre. So, pastiche collections or other collections are one of the main source of classical poetry. Contributions of periodicals to classical school of poetry investigating, may be collected with three groups. Firsh of all, periodicals reflect the plcasure of poem when they were written and poems which were approued can be determined. Second one, they contribute to recognition of poets who weren’t mentioned in history of literature. Third one, investigetors can benefit from periodicals for poems which weren’t mentioned in poet’s divan which include their poems. By this way, investigators can collect all poems of poet. İn this study, we evalvated the contributions of periodicals to classical poetry investigators. And than we are going to publish Seyyid Vehbi’s kaside in “Sıhhatname ve Sur-ı Hıtana Müteallik Kasaid” which was found from Topkapı Palace Library. With this study, Seyyid Vehbi’s poem which weren’t mentioned in other 31 copy is going to be presented to investigator’s advantage. Şiir mecmuaları çeşitli şiirleri derlemekle birlikte yazıldığı devrin sanat ve kültür birikimini de bir araya getirirler. Nazire mecmuaları nazire geleneğini ve şairler arası etkileşimi örnekleriyle gözler önüne sererken, farklı konular etrafında toplanan ya da -tamamen okuyucunun zevkine göre gelişigüzel toplanan- şiir defterleri edebiyat tarihini bir bütünlük içinde görmemize olumlu katkılar sağlar. Bu nedenle nazire mecmuaları ya da diğer şiir mecmuaları, divan şiiri araştırmalarının başlıca kaynaklarındandır. Genel olarak baktığımızda mecmuaların divan edebiyatı araştırmalarına katk

  16. 2. Bölgesel TIAFT (Uluslararası Adli Toksikologlar Birliği Toplantısı Sonuç Bildirgesi

    Directory of Open Access Journals (Sweden)

    Halis Dokgöz

    2016-12-01

    Full Text Available Adli ve Klinik Toksikoloji Derneği (AKTOD tarafından, Adli Tıp Kurumu, Adli Tıp Uzmanları Derneği, TUBİM, Jandarma Kriminal Daire Başkanlığı, Türk Farmakoloji Derneği, Türkiye Acil Tıp Derneği destekleri ile, 30 Ekim 2 Kasım 2016 tarihleri arasında 2. Bölgesel TIAFT (The International Association of Forensic Toxicologists-http://www.tiaftturkey2016.org Toplantısı, Antalya WOW Topkapı Palace Oteli’nde düzenlenmiştir. Kongreye The International Association of Forensic Toxicologists (TIAFT, European Workplace Drug Testing Society, Regional Anti-Doping Center of Turin,  National Institute on Drug Abuse (NIDA, UCSF School of Medicine, Society of Forensic Toxicologists (USA, National Institute of Toxicology and Forensic Sciences, Ministery of Justice (Spain Driving Under the Influence Drugs – ROSITA projesi gibi birçok alanda bilim adamları çalışmalarını paylaşmışlardır. Ülkemiz ulusal uyuşturucu politika ve stratejisi kapsamında, “Uyuşturucu Maddelerle Mücadele” Üst Kurulundan (Adalet Bakanlığı Müsteşar Yardımcısı, Sağlık Bakanlığı Müsteşar Yardımcısı, Adalet Bakanlığı Ceza İşleri Müdürlüğü hâkimleri ve AB Devletlerinden bu alanda aktif olarak çalışmış yöneticiler tarafından sunulan faaliyet raporları, güncel gelişmeler ve yeni eylem planları “Uyuşturucu ile Mücadele” oturumunda; sunulmuştur. Bu oturumda; arz ve taleple mücadelede, suçun delillendirilmesi ve Denetimli Serbestlik hakkından yararlanılması aşamasında laboratuvar sonucunun bilimsel kanıt/somut veri olması nedeniyle bu analizden sorumlu “Referans adli toksikoloji laboratuvarları” nın önemi ve özellikleri, bu laboratuvarlarda çalışacak kişilerin ilgili bilimsel kurul tarafından onaylanması konuları tartışılmıştır ve yurtdışı örnekleri incelenmiştir. Bu açıklamalar kapsamında; madde bağımlılığında madde testinin birçok amaçla yapılabildiği, klinik

  17. BR2 Reactor: Introduction

    International Nuclear Information System (INIS)

    Moons, F.

    2007-01-01

    The irradiations in the BR2 reactor are in collaboration with or at the request of third parties such as the European Commission, the IAEA, research centres and utilities, reactor vendors or fuel manufacturers. The reactor also contributes significantly to the production of radioisotopes for medical and industrial applications, to neutron silicon doping for the semiconductor industry and to scientific irradiations for universities. Along the ongoing programmes on fuel and materials development, several new irradiation devices are in use or in design. Amongst others a loop providing enhanced cooling for novel materials testing reactor fuel, a device for high temperature gas cooled fuel as well as a rig for the irradiation of metallurgical samples in a Pb-Bi environment. A full scale 3-D heterogeneous model of BR2 is available. The model describes the real hyperbolic arrangement of the reactor and includes the detailed 3-D space dependent distribution of the isotopic fuel depletion in the fuel elements. The model is validated on the reactivity measurements of several tens of BR2 operation cycles. The accurate calculations of the axial and radial distributions of the poisoning of the beryllium matrix by 3 He, 6 Li and 3T are verified on the measured reactivity losses used to predict the reactivity behavior for the coming decades. The model calculates the main functionals in reactor physics like: conventional thermal and equivalent fission neutron fluxes, number of displacements per atom, fission rate, thermal power characteristics as heat flux and linear power density, neutron/gamma heating, determination of the fission energy deposited in fuel plates/rods, neutron multiplication factor and fuel burn-up. For each reactor irradiation project, a detailed geometry model of the experimental device and of its neighborhood is developed. Neutron fluxes are predicted within approximately 10 percent in comparison with the dosimetry measurements. Fission rate, heat flux and

  18. Kuş Gözlemciliği ve Turizm İlişkisi: Burdur Gölü Üzerine Bir Tartışma (The Relationship between Birdwatching and Tourism: A Discussion on Lake Burdur)

    OpenAIRE

    Serhat Adem SOP

    2015-01-01

    Sop, S.A. (2015). Kuş Gözlemciliği ve Turizm İlişkisi: Burdur Gölü Üzerine Bir Tartışma*. I. Teke Yöresi Sempozyumu (04–06 March). Burdur, Turkey. p: 543-549. *The Relationship between Birdwatching and Tourism: A Discussion on Lake Burdur

  19. Râzî’nin, Kur’an’daki Yeryüzü (Arz Âyetleriyle İlgili Tefsir-i Kebir’deki Yorumları: Modern Jeoloji Biliminin Verileriyle Kısa Bir Mukayese

    Directory of Open Access Journals (Sweden)

    Enver BAYRAM

    2012-03-01

    Full Text Available Batı dünyasında bilimsel buluş ve keşiflerin yeni başladığı bir dönemde, İslam dünyasında birçok bilimsel buluş ve keşif Müslüman bilim adamları tarafından ortaya konulmuştur. Bu buluş ve keşiflerin yapıldığı alanlardan biri de Jeoloji (yer ilmidir. Bu konuyu tefsirinde etraflıca ele alan Râzî (ö. 606/1210, yer ile ilgili âyetleri kendi döneminin ilmi verileri doğrultusunda ayrıntılı bir şekilde tefsir etmiştir. Bu yüzden onun bazı açıklamaları, zaman zaman modern Jeoloji ilminin verilerine ters düşebilmektedir. Onun, bu âyetleri tefsir ederken en temel amacı, bunları Allah’ın varlığına ve birliğine delil getirmesi olmuştur.

  20. Radiation detectors for reactors

    International Nuclear Information System (INIS)

    Balagi, V.

    2005-01-01

    Detection and measurement of radiation plays a vital role in nuclear reactors from the point of view of control and safety, personnel protection and process control applications. Various types of radiation are measured over a wide range of intensity. Consequently a variety of detectors find use in nuclear reactors. Some of these devices have been developed in Electronics Division. They include gas-filled detectors such as 10 B-lined proportional counters and chambers, fission detectors and BF 3 counters are used for the measurement of neutron flux both for reactor control and safety, process control as well as health physics instrumentation. In-core neutron flux instrumentation employs the use detectors such as miniature fission detectors and self-powered detectors. In this development effort, several indigenous materials, technologies and innovations have been employed to suit the specific requirement of nuclear reactor applications. This has particular significance in view of the fact that several new types of reactors such as P-4, PWR and AHWR critical facilities, FBTR, PFBR as well as the refurbishment of old units like CIRUS are being developed. The development work has sought to overcome some difficulties associated with the non-availability of isotopically enriched neutron-sensing materials, achieving all-welded construction etc. The present paper describes some of these innovations and performance results. (author)

  1. Reactors PMT backlog

    International Nuclear Information System (INIS)

    Olson, H.P.

    1986-01-01

    The overall backlog of action items within the Reactors Priority Maintenance Tracking Systems (PMT) is similar to that resulting from Reactor Incident Reports. At least 1000 open action items are being tracked (excluding procedure revisions); the exact number is not obvious because some items are being tracked in more than one tracking document. About 20 to 25% of the incomplete items are directly related to reactor safety. About 70% of these were initiated within the last two years. A few of the remaining 30% date back to the 1977-1980 time frame. The tracking systems that are in place serve particular needs but they are unconnected and do not provide a means to understand and manage the overall Reactors PMT backlog. Shortcomings are summarized. Several initiatives are in progress or planned by Reactors PMT to facilitate improved tracking of backlog items with computer software systems. Under consideration is the Integrated Living Schedule (ILS) approach to prioritize work items and schedule resources to manage the backlog in the most effective way. ILS systems are being used effectively by a number of nuclear power utilities. 6 refs., 6 figs., 1 tab

  2. Generalities about nuclear reactors

    International Nuclear Information System (INIS)

    Jaouen, C.; Beroux, P.

    2012-01-01

    From Zoe, the first nuclear reactor, till the current EPR, the French nuclear industry has always advanced by profiting from the feedback from dozens of years of experience and operations, in particular by drawing lessons from the most significant events in its history, such as the Fukushima accident. The new generations of reactors must improve safety and economic performance so that the industry maintain its legitimacy and its share in the production of electricity. This article draws the history of nuclear power in France, gives a brief description of the pressurized water reactor design, lists the technical features of the different versions of PWR that operate in France and compares them with other types of reactors. The feedback experience concerning safety, learnt from the major nuclear accidents Three Miles Island (1979), Chernobyl (1986) and Fukushima (2011) is also detailed. Today there are 26 third generation reactors being built in the world: 4 EPR (1 in Finland, 1 in France and 2 in China); 2 VVER-1200 in Russia, 8 AP-1000 (4 in China and 4 in the Usa), 8 APR-1400 (4 in Korea and 4 in UAE), and 4 ABWR (2 in Japan and 2 in Taiwan)

  3. Mirror reactor studies

    International Nuclear Information System (INIS)

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

    1976-01-01

    Design studies of a fusion mirror reactor, a fusion-fission mirror reactor, and two small mirror reactors are summarized. The fusion reactor uses 150-keV neutral-beam injectors based on the acceleration of negative ions. The injectors provide over 1 GW of continuous power at an efficiency greater than 80 percent. The fusion reactor has three-stage, modularized, Venetian blind, plasma direct converter with a predicted efficiency of 59 percent and a new concept for removal of the lune-shaped blanket: a crane is brought between the two halves of the Yin-Yang magnet, which are separated by a float. The design has desirable features such as steady-state operation, minimal impurity problems, and low first-wall thermal stress. The major disadvantage is low Q resulting in high recirculating power and hence high cost of electrical power. However, the direct capital cost per unit of gross electrical power is reasonable [$1000/kW(e)

  4. Reactor core control device

    International Nuclear Information System (INIS)

    Sano, Hiroki

    1998-01-01

    The present invention provides a reactor core control device, in which switching from a manual operation to an automatic operation, and the control for the parameter of an automatic operation device are facilitated. Namely, the hysteresis of the control for the operation parameter by an manual operation input means is stored. The hysteresis of the control for the operation parameter is collected. The state of the reactor core simulated by an operation control to which the collected operation parameters are manually inputted is determined as an input of the reactor core state to the automatic input means. The record of operation upon manual operation is stored as a hysteresis of control for the operation parameter, but the hysteresis information is not only the result of manual operation of the operation parameter. This is results of operation conducted by a skilled operator who judge the state of the reactor core to be optimum. Accordingly, it involves information relevant to the reactor core state. Then, it is considered that the optimum automatic operation is not deviated greatly from the manual operation. (I.S.)

  5. Reactor physics computations

    International Nuclear Information System (INIS)

    Shapiro, A.

    1977-01-01

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

  6. Nuclear reactor apparatus

    International Nuclear Information System (INIS)

    Braun, H.E.; Bonnet, H.P.

    1978-01-01

    The reactor and its containment, instead of being supported on a solid concrete pad, are supported on a truss formed of upper and lower reinforced horizontal plates and vertical walls integrated into a rigid structure. The plates and walls from chambers within which the auxiliary components of the reactor, such as valves, pumping equipment and various tanks, are disposed. Certain of the chambers are also access passages for personnel, pipe chases, valve chambers and the like. In particular the truss includes an annular chamber. This chamber is lined and sealed by a corrosion-resistant liner and contains coolant and serves as a refueling cooling storage tank. This tank is directly below the primary-coolant conductor loops which extend from the reactor above the upper plate. The upper plate includes a sump connected to the tank through which coolant flows into the tank in the event of the occurrence of a loss-of-coolant accident. The truss extends beyond the containment and has chambers in the extending annulus. Pumps for circulating the coolant between the refueling coolant storage tank and the reactor are provided in certain of these chambers. The pumps are connected to the reactor by relatively short coolant conductors. Access to these pumps is readily afforded through hatches in the extending annulus

  7. Reactor power control device

    International Nuclear Information System (INIS)

    Nishiyama, Hiroyuki.

    1991-01-01

    The device of the present invention prevents unnecessary automatic reactor shutdown, without increasing operator's burden by automatic insertion of selected control rods in case if a recycling pump in a BWR reaction should stop. That is, the device of the present invention comprises (1) a means for detecting that at least one recycling pump stops, (2) a means for judging region for inserting the selected control rods based on the reactor power and the recycling flowrate of driving water, and (3) a means for calculating a logic product of output signals sent from both of the means described above and outputting a selected control rod insertion signal. With such a constitution, if at least one recycling pump stops, the means (1) detects it. Further, the means (2) judges the regions for inserting the selected control rods. Then, the means (3) outputs a signal for inserting the selected control rods. As a result, since a group of control rods selected previously are inserted into the reactor rapidly, the reactor power is suppressed, to avoid the automatic reactor shutdown. (I.N.)

  8. Tandem mirror reactors

    International Nuclear Information System (INIS)

    Logan, B.G.; Barr, W.L.; Bender, D.J.

    1978-01-01

    We have made preliminary designs of tandem mirror fusion reactors burning D-T fuel and of fusion-fission (hybrid) tandem mirrors producing both fissile fuel and electricity. For the hybrid reactor, we find that by using stream-stabilized, 2XIIB-like plugs and by injecting 200-keV deuterium beams into a tritium-plasma target confined electrostatically in the solenoid (two-component operation), we obtain a useful Q (fusion power/injection power) near unity. The D-T tandem reactor parameters are optimized to obtain the minimum capital cost per kW(e) net. For $200/kW(e) of 1200-keV neutral beam injection power in the plugs and a solenoid cost of about $3 million per metre length, the optimum Q is near 5. To allow for more expensive injector costs, a higher D-T reactor Q of 10 is obtainable with either increased power output or decreased neutron wall loading. Fokker--Planck calculations show steady-state Q approximately 5 for D-D tandem reactors burning only deuterium fuel and its reaction products, with most of the charged-particle fusion power recovered in a direct converter

  9. Reactor shutdown device

    International Nuclear Information System (INIS)

    Matsumiya, Hirohito; Endo, Hiroshi; Tsuboi, Yasushi.

    1993-01-01

    The present invention concerns a reactor shutdown device capable of suppressing change of a core insertion amount relative to temperature change during normal operation and having a great extension amount due to thermal expansion and high mechanical strength. A control rod main body is contained vertically movably in a guide tube disposed in a reactor core. An extension member extends upward from the upper end of a control rod main body and suspends the control rod main body. A shrinkable member intervenes at a midway of the extension member and is made shrinkable. A temperature sensitive member contains coolants at the inside and surrounds the shrinkable member. Thus, if the temperature of external coolants rises abruptly, the shrinkable member is extended by thermal expansion of the coolants in the temperature sensitive member. Upon usual reactor startup, the coolants in the temperature sensitive member cause no substantial thermal expansion by temperature elevation from a cold shutdown temperature to a rated power operation temperature, and the shrinkable member maintains its original state, so that the control rod main body is not inserted into the reactor core. However, upon abrupt temperature elevation, the control rod main body is inserted into the reactor core. (I.S.)

  10. FBR type reactors

    International Nuclear Information System (INIS)

    Maemoto, Junko.

    1985-01-01

    Purpose: To moderate abrupt temperature change near the inner walls of a suspended body thereby prevent thermal shocks and thermal deformations to structural materials. Constitution: High temperature coolants during ordinary operation of the nuclear reactor flow from the reactor core through the flow holes of the suspended body and from the upper plenum into an intermediate heat exchanger. The temperature of the coolants is lowered with heat exchanging effect with secondary coolants in the heat exchange and the coolants are then flow through the lower plenum into the reactor core and heated again. Upon generation of reactor scram, the temperature of the coolants at the exit of the reactor core is reduced abruptly and the flow rate is lowered due to the pump coast down. However, mixing of the coolants in the suspended body is accelerated by the coolants at high temperature flowing out of the flow holes and the coolants at the low temperature flowing from the flow hole group, to reduce the temperature difference and moderate the stratification flow forming an abrupt temperature slope. (Yoshihara, H.)

  11. RB research reactor Safety Report

    International Nuclear Information System (INIS)

    Sotic, O.; Pesic, M.; Vranic, S.

    1979-04-01

    This RB reactor safety report is a revised and improved version of the Safety report written in 1962. It contains descriptions of: reactor building, reactor hall, control room, laboratories, reactor components, reactor control system, heavy water loop, neutron source, safety system, dosimetry system, alarm system, neutron converter, experimental channels. Safety aspects of the reactor operation include analyses of accident causes, errors during operation, measures for preventing uncontrolled activity changes, analysis of the maximum possible accident in case of different core configurations with natural uranium, slightly and highly enriched fuel; influence of possible seismic events

  12. Mimic of OSU research reactor

    International Nuclear Information System (INIS)

    Lu, Hong; Miller, D.W.

    1991-01-01

    The Ohio State University research reactor (OSURR) is undergoing improvements in its research and educational capabilities. A computer-based digital data acquisition system, including a reactor system mimic, will be installed as part of these improvements. The system will monitor the reactor system parameters available to the reactor operator either in digital parameters available to the reactor operator either in digital or analog form. The system includes two computers. All the signals are sent to computer 1, which processes the data and sends the data through a serial port to computer 2 with a video graphics array VGA monitor, which is utilized to display the mimic system of the reactor

  13. Reactor Structural Materials: Reactor Pressure Vessel Steels

    Energy Technology Data Exchange (ETDEWEB)

    Chaouadi, R

    2000-07-01

    The objectives of SCK-CEN's R and D programme on Rector Pressure Vessel (RPV) Steels are:(1) to complete the fracture toughness data bank of various reactor pressure vessel steels by using precracked Charpy specimens that were tested statically as well as dynamically; (2) to implement the enhanced surveillance approach in a user-friendly software; (3) to improve the existing reconstitution technology by reducing the input energy (short cycle welding) and modifying the stud geometry. Progress and achievements in 1999 are reported.

  14. Reactor Structural Materials: Reactor Pressure Vessel Steels

    International Nuclear Information System (INIS)

    Chaouadi, R.

    2000-01-01

    The objectives of SCK-CEN's R and D programme on Rector Pressure Vessel (RPV) Steels are:(1) to complete the fracture toughness data bank of various reactor pressure vessel steels by using precracked Charpy specimens that were tested statically as well as dynamically; (2) to implement the enhanced surveillance approach in a user-friendly software; (3) to improve the existing reconstitution technology by reducing the input energy (short cycle welding) and modifying the stud geometry. Progress and achievements in 1999 are reported

  15. Bir Su Ürünleri İşleme Tesisinde İş Sağlığı ve Güvenliği Risk Analizi Uygulaması

    Directory of Open Access Journals (Sweden)

    Servet Atayeter

    2015-02-01

    Full Text Available Bu çalışmada, Bodrum’da bulunan bir su ürünleri işleme ve paketleme tesisinde TS 18001 İş Sağlığı ve Güvenliği Sistemi çerçevesinde pilot bir risk analizi uygulaması gerçekleştirilerek sonuçları değerlendirilmiştir. Çalışanların kendilerini güvende hissetme gereksinimi ile doğrudan ilgili olan iş sağlığı ve güvenliği konusu, günümüzde tüm sektörlerde olduğu gibi su ürünleri işletmeleri için de rekabet edilebilirlik, verimlilik, sosyal sorumluluk ve ülke ekonomisi açılarından üzerinde önemle durulması gereken bir konu haline gelmiştir. TS 18001 İş Sağlığı ve Güvenliği Sistemi bir işletmede insan sağlığı ve güvenliğini sağlamaya, can ve mal kayıplarını önlemeye, bu konudaki riskleri azaltmaya odaklı dinamik ve esnek bir sistemin kurulmasını amaçlar. Sistemin amaç ve hedeflerine ulaşılması ve etkinliğinin sürekli iyileştirilebilmesi ise gerçekçi bir risk analizinin yapılmasına bağlıdır. Risk analizinin sonuçları değerlendirilerek, işletmede can güvenliği ve maddi kayıpların önlenmesine yönelik önleyici tedbirlerin alınması yönünde önemli bir adım atılmış olmakta, böylelikle faaliyetlerle ilgili risklerin azaltılması ve ortadan kaldırılması olanaklı hale gelmektedir.

  16. İki Spor Kulübünün Hisse Senedi Getirileri Üzerine Bir İnceleme

    Directory of Open Access Journals (Sweden)

    Deniz PARLAK

    2014-12-01

    Full Text Available Futbol, günümüz dünyasında bir eğlence unsuru olmaktan çıkarak endüstri kolu haline gelmiştir. Bu sporun Türkiye’deki en önemli temsilcileri olan Fenerbahçe ve Galatasaray’ın arasındaki rekabet hem takım düzeyinde sahada hem de şirket düzeyinde borsada yaşanmaktadır. Çalışmanın amacı bu iki futbol takımının yaptıkları karşılaşmalarda aldıkları sonuçların borsada işlem gören hisselerine ait fiyatlara etkisini incelemektir. Takımların kendi sonuçlarının yanı sıra rakibinin aldığı sonuçların da şirketin hisse senedi getirisine etki edip etmediği araştırılmıştır. Kullanılan üç günlük olay etüdü analizi ile maç sonuçlarına ait beklentilerin maçtan bir gün önce, maç sonuçlarının ise maçtan bir gün sonra kümülatif anormal getiri yarattığını göstermiştir. Kümülatif anormal getirinin rakibin elde ettiği sonuçlara göre farklılık göstermediği saptanmıştır.

  17. Reactor safety analysis

    International Nuclear Information System (INIS)

    Arien, B.

    1998-01-01

    Risk assessments of nuclear installations require accurate safety and reliability analyses to estimate the consequences of accidental events and their probability of occurrence. The objective of the work performed in this field at the Belgian Nuclear Research Centre SCK-CEN is to develop expertise in probabilistic and deterministic reactor safety analysis. The four main activities of the research project on reactor safety analysis are: (1) the development of software for the reliable analysis of large systems; (2) the development of an expert system for the aid to diagnosis; (3) the development and the application of a probabilistic reactor-dynamics method, and (4) to participate in the international PHEBUS-FP programme for severe accidents. Progress in research during 1997 is described

  18. Reactor for exothermic reactions

    Science.gov (United States)

    Smith, L.A. Jr.; Hearn, D.; Jones, E.M. Jr.

    1993-03-02

    A liquid phase process is described for oligomerization of C[sub 4] and C[sub 5] isoolefins or the etherification thereof with C[sub 1] to C[sub 6] alcohols wherein the reactants are contacted in a reactor with a fixed bed acid cation exchange resin catalyst at an LHSV of 5 to 20, pressure of 0 to 400 psig and temperature of 120 to 300 F. Wherein the improvement is the operation of the reactor at a pressure to maintain the reaction mixture at its boiling point whereby at least a portion but less than all of the reaction mixture is vaporized. By operating at the boiling point and allowing a portion of the reaction mixture to vaporize, the exothermic heat of reaction is dissipated by the formation of more boil up and the temperature in the reactor is controlled.

  19. Refueling of nuclear reactors

    International Nuclear Information System (INIS)

    Meuschke, R.E.

    1987-01-01

    This patent describes the unrodded refueling of a nuclear reactor having fuel assemblies and upper internals with apparatus including a lifting rig and a lift plate. The upper internals of the reactor are secured to the lifting rig. A method is given of reinserting in the fuel assemblies of the reactor the rods which penetrate into the fuel assemblies, such as control rods and/or coolant-displacement rods. The penetrating rods are connected to drive rods, the drive rods and penetrating rods being suspended from the lift plate, the lift plate and the drive rods and penetrating rods suspended therefrom being supported on a removable support in an upper position on the lifting rig

  20. Nuclear reactor safety device

    Science.gov (United States)

    Hutter, Ernest

    1986-01-01

    A safety device is disclosed for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of an upward thermal excursion. Such safety device comprises a laminated helical ribbon configured as a tube-like helical coil having contiguous helical turns with slidably abutting edges. The helical coil is disclosed as a portion of a drive member connected axially to the control rod. The laminated ribbon is formed of outer and inner laminae. The material of the outer lamina has a greater thermal coefficient of expansion than the material of the inner lamina. In the event of an upward thermal excursion, the laminated helical coil curls inwardly to a smaller diameter. Such inward curling causes the total length of the helical coil to increase by a substantial increment, so that the control rod is axially repositioned by a corresponding amount to reduce the power output of the reactor.

  1. The nuclear reactor systems

    International Nuclear Information System (INIS)

    Bacher, P.

    2008-01-01

    This paper describes the various nuclear reactor systems, starting with the Generation II, then the present development of the Generation III and the stakes and challenges of the future Generation IV. Some have found appropriate to oppose reactor systems or generations one to another, especially by minimizing the enhancements of generation III compared to generation II or by expecting the earth from generation IV (meaning that generation III is already obsolete). In the first part of the document (chapter 2), some keys are given to the reader to develop its proper opinion. Chapter 3 describes more precisely the various reactor systems and generations. Chapter 4 discusses the large industrial manoeuvres around the generation III, and the last chapter gives some economical references, taking into account, for the various means of power generation, the impediments linked to climate protection

  2. Reactor control device

    International Nuclear Information System (INIS)

    Araki, Takao; Inoue, Toyokazu.

    1981-01-01

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

  3. Licensed operating reactors

    International Nuclear Information System (INIS)

    1989-08-01

    THE OPERATING UNITS STATUS REPORT - LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US

  4. Nuclear reactor risk assessment

    International Nuclear Information System (INIS)

    Higson, D.J.

    1982-01-01

    Experience has shown that reactors can be operated safely. Accidents have occurred, but the probability of physical health detriment to members of the public has been negligible. Methods for the quantitative evaluation of the probabilities of serious accidents are described, and some results are quoted which show that the estimated frequency of harmful effects is small when compared with other risks already accepted by society. Attempts have been made to justify the acceptance of nuclear reactor risks by relating them to the benefits which are derived from reactor operation and comparing them quantitatively with the risks from alternative methods of deriving the same benefits. This approach takes no account of the perceptions which people have of risk

  5. Breazeale Reactor Modernization Program

    International Nuclear Information System (INIS)

    Davison, C. C.

    2003-01-01

    The Penn State Breazeale Nuclear Reactor is the longest operating licensed research reactor in the nation. The facility has played a key role in educating scientists, engineers and in providing facilities and services to researchers in many different disciplines. In order to remain a viable and effective research and educational institution, a multi-phase modernization project was proposed. Phase I was the replacement of the 25-year old reactor control and safety system along with associated wiring and hardware. This phase was fully funded by non-federal funds. Tasks identified in Phases II-V expand upon and complement the work done in Phase I to strategically implement state-of-the-art technologies focusing on identified national needs and priorities of the future

  6. Fusion reactor materials

    International Nuclear Information System (INIS)

    Rowcliffe, A.F.; Burn, G.L.; Knee', S.S.; Dowker, C.L.

    1994-02-01

    This is the fifteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; Special purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the U.S. Department of Energy. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide

  7. MERCHANT MARINE SHIP REACTOR

    Science.gov (United States)

    Mumm, J.F.; North, D.C. Jr.; Rock, H.R.; Geston, D.K.

    1961-05-01

    A nuclear reactor is described for use in a merchant marine ship. The reactor is of pressurized light water cooled and moderated design in which three passes of the water through the core in successive regions of low, intermediate, and high heat generation and downflow in a fuel region are made. The foregoing design makes a compact reactor construction with extended core life. The core has an egg-crate lattice containing the fuel elements confined between a lower flow baffle and upper grid plate, with the latter serving also as part of a turn- around manifold from which the entire coolant is distributed into the outer fuel elements for the second pass through the core. The inner fuel elements are cooled in the third pass.

  8. Utilization of research reactors

    International Nuclear Information System (INIS)

    1962-01-01

    About 200 research reactors are now in operation in different parts of the world, and at least 70 such facilities, which are in advanced stages of planning and construction, should be critical within the next two or three years. In the process of this development a multitude of problems are being encountered in formulating and carrying out programs for the proper utilization of these facilities, especially in countries which have just begun or are starting their atomic energy work. An opportunity for scientific personnel from different Member States to discuss research reactor problems was given at an international symposium on the Programing and Utilization of Research Reactors organized by the Agency almost immediately after the General Conference session. Two hundred scientists from 35 countries, as well as from the European Nuclear Energy Agency and EURATOM, attended the meeting which was held in Vienna from 16 to 21 October 1961

  9. Compact stellarators as reactors

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  10. Reactor container facility

    International Nuclear Information System (INIS)

    Saito, Takashi; Nagasaka, Hideo.

    1990-01-01

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

  11. International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    Blevins, J.D.; Stasko, R.R.

    1989-09-01

    An international design team comprised of members from Canada, Europe, Japan, the Soviet Union, and the United States of America, are designing an experimental fusion test reactor. The engineering and testing objectives of this International Thermonuclear Experimental Reactor (ITER) are to validate the design and to demonstrate controlled ignition, extended burn of a deuterium and tritium plasma, and achieve steady state using technology expected to be available by 1990. The concept maximizes flexibility while allowing for a variety of plasma configurations and operating scenarios. During physics phase operation, the machine produces a 22 MA plasma current. In the technology phase, the machine can be reconfigured with a thicker shield and a breeding blanket to operate with an 18 MA plasma current at a major radius of 5.5 meters. Canada's involvement in the areas of safety, facility design, reactor configuration and maintenance builds on our internationally recognized design and operational expertise in developing tritium processes and CANDU related technologies

  12. BWR type reactor system

    International Nuclear Information System (INIS)

    Morooka, Shin-ichi.

    1980-01-01

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

  13. Licensed operating reactors

    International Nuclear Information System (INIS)

    1989-08-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  14. Licensed operating reactors

    International Nuclear Information System (INIS)

    1990-01-01

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  15. Licensed operating reactors

    International Nuclear Information System (INIS)

    Hartfield, R.A.

    1990-03-01

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  16. Nuclear reactor containment device

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu.

    1980-01-01

    Purpose: To reduce the volume of a containment shell and decrease the size of a containment equipment for BWR type reactors by connecting the containment shell and a suppression pool with slanted vent tubes to thereby shorten the vent tubes. Constitution: A pressure vessel containing a reactor core is installed at the center of a building and a containment vessel for the nuclear reactor that contains the pressure vessel forms a cabin. To a building situated below the containment shell, is provided a suppression chamber in which cooling water is charged to form a suppression pool. The suppression pool is communicated with vent tubes that pass through the partition wall of the containment vessel. The vent tubes are slanted and their lower openings are immersed in coolants. Therefore, if accident is resulted and fluid at high temperature and high pressure is jetted from the pressure vessel, the jetting fluid is injected and condensated in the cooling water. (Moriyama, K.)

  17. Nuclear Rocket Engine Reactor

    CERN Document Server

    Lanin, Anatoly

    2013-01-01

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

  18. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Hoizumi, Atsushi.

    1986-01-01

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

  19. AREVA's nuclear reactors portfolio

    International Nuclear Information System (INIS)

    Marincic, A.

    2009-01-01

    A reasonable assumption for the estimated new build market for the next 25 years is over 340 GWe net. The number of prospect countries is growing almost each day. To address this new build market, AREVA is developing a comprehensive portfolio of reactors intended to meet a wide range of power requirements and of technology choices. The EPR reactor is the flagship of the fleet. Intended for large power requirements, the four first EPRs are being built in Finland, France and China. Other countries and customers are in view, citing just two examples: the Usa where the U.S. EPR has been selected as the technology of choice by several U.S utilities; and the United Kingdom where the Generic Design Acceptance process of the EPR design submitted by AREVA and EDF is well under way, and where there is a strong will to have a plant on line in 2017. For medium power ranges, the AREVA portfolio includes a boiling water reactor and a pressurized water reactor which both offer all of the advantages of an advanced plant design, with excellent safety performance and competitive power generation cost: -) KERENA (1250+ MWe), developed in collaboration with several European utilities, and in particular with Eon; -) ATMEA 1 (1100+ MWe), a 3-loop evolutionary PWR which is being developed by AREVA and Mitsubishi. AREVA is also preparing the future and is deeply involved into Gen IV concepts. It has developed the ANTARES modular HTR reactor (pre-conceptual design completed) and is building upon its vast Sodium Fast Reactor experience to take part into the development of the next prototype. (author)

  20. Oscillatory flow chemical reactors

    Directory of Open Access Journals (Sweden)

    Slavnić Danijela S.

    2014-01-01

    Full Text Available Global market competition, increase in energy and other production costs, demands for high quality products and reduction of waste are forcing pharmaceutical, fine chemicals and biochemical industries, to search for radical solutions. One of the most effective ways to improve the overall production (cost reduction and better control of reactions is a transition from batch to continuous processes. However, the reactions of interests for the mentioned industry sectors are often slow, thus continuous tubular reactors would be impractically long for flow regimes which provide sufficient heat and mass transfer and narrow residence time distribution. The oscillatory flow reactors (OFR are newer type of tube reactors which can offer solution by providing continuous operation with approximately plug flow pattern, low shear stress rates and enhanced mass and heat transfer. These benefits are the result of very good mixing in OFR achieved by vortex generation. OFR consists of cylindrical tube containing equally spaced orifice baffles. Fluid oscillations are superimposed on a net (laminar flow. Eddies are generated when oscillating fluid collides with baffles and passes through orifices. Generation and propagation of vortices create uniform mixing in each reactor cavity (between baffles, providing an overall flow pattern which is close to plug flow. Oscillations can be created by direct action of a piston or a diaphragm on fluid (or alternatively on baffles. This article provides an overview of oscillatory flow reactor technology, its operating principles and basic design and scale - up characteristics. Further, the article reviews the key research findings in heat and mass transfer, shear stress, residence time distribution in OFR, presenting their advantages over the conventional reactors. Finally, relevant process intensification examples from pharmaceutical, polymer and biofuels industries are presented.

  1. Yüzde tabanlı String Eşleme Problemi için yeni bir donanım modülü tasarımı

    Directory of Open Access Journals (Sweden)

    İbrahim Şahin

    2016-12-01

    Full Text Available Bir verinin bir dizgi içerisinde veya bir gen yapısının bir DNA gen dizilimi içerisinde arama işleminin gerçekleştirilmesi için çeşitli algoritmalar kullanılmaktadır. Kullanılan bu algoritmalardan bazıları bize mutlak eşleşme olmadığı durumlarda olumsuz dönüt vermekte, bazıları ise “bunu mu arıyorsunuz” diye alternatifler sunmaktadır. Her iki algoritma da genel amaçlı PC’lerde saniyeler süren işlemler sonucunda bize dönüt verebilmektedir. Bu çalışmada bize hem mutlak eşleşmeyi hem de hedef dizgi içinde yüzdelik eşleşme oranlarının gerçekleştiği konumu veren FPGA çiplerine yönelik yüksek performanslı bir donanım modülü tasarlanmıştır. Geliştirilen modülün veri işleme hızı farklı PC’lerle karşılaştırılmış ve 2300 kata kadar daha hızlı arama gerçekleştirdiği karşılaştırma sonuçlarından elde edilen veriler ile doğrulanmıştır.

  2. The Staphylococcus aureus group II biotin protein ligase BirA is an effective regulator of biotin operon transcription and requires the DNA binding domain for full enzymatic activity.

    Science.gov (United States)

    Henke, Sarah K; Cronan, John E

    2016-11-01

    Group II biotin protein ligases (BPLs) are characterized by the presence of an N-terminal DNA binding domain that functions in transcriptional regulation of the genes of biotin biosynthesis and transport. The Staphylococcus aureus Group II BPL which is called BirA has been reported to bind an imperfect inverted repeat located upstream of the biotin synthesis operon. DNA binding by other Group II BPLs requires dimerization of the protein which is triggered by synthesis of biotinoyl-AMP (biotinoyl-adenylate), the intermediate in the ligation of biotin to its cognate target proteins. However, the S. aureus BirA was reported to dimerize and bind DNA in the absence of biotin or biotinoyl-AMP (Soares da Costa et al. (2014) Mol Microbiol 91: 110-120). These in vitro results argued that the protein would be unable to respond to the levels of biotin or acceptor proteins and thus would lack the regulatory properties of the other characterized BirA proteins. We tested the regulatory function of the protein using an in vivo model system and examined its DNA binding properties in vitro using electrophoretic mobility shift and fluorescence anisotropy analyses. We report that the S. aureus BirA is an effective regulator of biotin operon transcription and that the prior data can be attributed to artifacts of mobility shift analyses. We also report that deletion of the DNA binding domain of the S. aureus BirA results in loss of virtually all of its ligation activity. © 2016 John Wiley & Sons Ltd.

  3. Reactor Materials Research

    International Nuclear Information System (INIS)

    Van Walle, E.

    2002-01-01

    The activities of SCK-CEN's Reactor Materials Research Department for 2001 are summarised. The objectives of the department are: (1) to evaluate the integrity and behaviour of structural materials used in nuclear power industry; (2) to conduct research to unravel and understand the parameters that determine the material behaviour under or after irradiation; (3) to contribute to the interpretation, the modelling of the material behaviour and to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the department are focussed on studies concerning (1) Irradiation Assisted Stress Corrosion Cracking (IASCC); (2) nuclear fuel; and (3) Reactor Pressure Vessel Steel

  4. ARIES tokamak reactor study

    International Nuclear Information System (INIS)

    Steiner, D.; Embrechts, M.

    1990-07-01

    This is a status report on technical progress relative to the tasks identified for the fifth year of Grant No. FG02-85-ER52118. The ARIES tokamak reactor study is a multi-institutional effort to develop several visions of the tokamak as an attractive fusion reactor with enhanced economic, safety, and environmental features. The ARIES study is being coordinated by UCLA and involves a number of institutions, including RPI. The RPI group has been pursuing the following areas of research in the context of the ARIES-I design effort: MHD equilibrium and stability analyses; plasma-edge modeling and blanket materials issues. Progress in these areas is summarized herein

  5. Nuclear reactor core assembly

    International Nuclear Information System (INIS)

    Baxi, C.B.

    1978-01-01

    The object of the present invention is to provide a fast reactor core assembly design for use with a fluid coolant such as liquid sodium or carbon monoxide incorporating a method of increasing the percentage of coolant flow though the blanket elements relative to the total coolant flow through the blanket and fuel elements during shutdown conditions without using moving parts. It is claimed that deterioration due to reactor radiation or temperature conditions is avoided and ready modification or replacement is possible. (U.K.)

  6. Particle bed reactor modeling

    Science.gov (United States)

    Sapyta, Joe; Reid, Hank; Walton, Lew

    The topics are presented in viewgraph form and include the following: particle bed reactor (PBR) core cross section; PBR bleed cycle; fuel and moderator flow paths; PBR modeling requirements; characteristics of PBR and nuclear thermal propulsion (NTP) modeling; challenges for PBR and NTP modeling; thermal hydraulic computer codes; capabilities for PBR/reactor application; thermal/hydralic codes; limitations; physical correlations; comparison of predicted friction factor and experimental data; frit pressure drop testing; cold frit mask factor; decay heat flow rate; startup transient simulation; and philosophy of systems modeling.

  7. Advanced reactors: A retrospective

    International Nuclear Information System (INIS)

    Starr, C.

    1989-01-01

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

  8. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    Aspden, G.J.

    1980-01-01

    A nuclear reactor construction comprising a reactor core submerged in a pool of liquid metal coolant in a primary vessel which is suspended from the roof structure of a containment vault. Control rods supported from the roof structure are insertable in the core which is carried on a support structure from the wall of the primary vessel. To prevent excessive relaxation of the support structure whereby the control rods would be displaced relative to the core, the support structure incorporates a normally inactive secondary structure designed to become effective in bracing the primary structure against further relaxation beyond a predetermined limit. (author)

  9. Reactor pressure vessel materials

    International Nuclear Information System (INIS)

    Suzuki, K.

    1998-01-01

    As a result of the popularity of the Agencies report 'Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels' of 1975, it was decided that another report on this broad subject would be of use. In this report, background and contemporary views on specially identified areas of the subject are considered as self-contained chapters, written by experts. Chapter 3 offers a detailed treatment of the selection criteria and properties of reactor pressure vessel materials. The main attention is directed towards steel and ingot making and the subsequent material processing

  10. Australia's new nuclear reactor

    International Nuclear Information System (INIS)

    Kemeny, L.

    2007-01-01

    On 19 and 20 April 2007, the Australian Nuclear Science and Technology Organisation (ANSTO) celebrated the recent commissioning of its new, world-class, OPAL (Open Pool Australian Lightwater) research reactor at the Lucas Heights. On the 19th, scientists, business leaders and academics were introduced to the reactor and its technical capacity for the manufacture of radiopharmaceuticals, its material science applications, its environmental services and its neutron scattering facilities for business applications. The formal OPAL opening function took place that evening and, on the 20th, Prime Minister John Howard visited ANSTO to be briefed about OPAL and to be shown the work being carried out at Lucas Heights

  11. Netherlands Interuniversity Reactor Institut

    International Nuclear Information System (INIS)

    1978-01-01

    This is the annual report of the Interuniversity Reactor Institute in the Netherlands for the Academic Year 1977-78. Activities of the general committee, the daily committee and the scientific advice board are presented. Detailed reports of the scientific studies performed are given under five subjects - radiation physics, reactor physics, radiation chemistry, radiochemistry and radiation hygiene and dosimetry. Summarised reports of the various industrial groups are also presented. Training and education, publications and reports, courses, visits and cooperation with other institutes in the area of scientific research are mentioned. (C.F.)

  12. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2002-04-01

    The activities of SCK-CEN's Reactor Materials Research Department for 2001 are summarised. The objectives of the department are: (1) to evaluate the integrity and behaviour of structural materials used in nuclear power industry; (2) to conduct research to unravel and understand the parameters that determine the material behaviour under or after irradiation; (3) to contribute to the interpretation, the modelling of the material behaviour and to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the department are focussed on studies concerning (1) Irradiation Assisted Stress Corrosion Cracking (IASCC); (2) nuclear fuel; and (3) Reactor Pressure Vessel Steel.

  13. 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

  14. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2000-01-01

    SCK-CEN's research and development programme on fusion reactor materials includes: (1) the study of the mechanical behaviour of structural materials under neutron irradiation (including steels, inconel, molybdenum, chromium); (2) the determination and modelling of the characteristics of irradiated first wall materials such as beryllium; (3) the detection of abrupt electrical degradation of insulating ceramics under high temperature and neutron irradiation; (4) the study of the dismantling and waste disposal strategy for fusion reactors.; (5) a feasibility study for the testing of blanket modules under neutron radiation. Main achievements in these topical areas in the year 1999 are summarised

  15. Fusion Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2000-07-01

    SCK-CEN's research and development programme on fusion reactor materials includes: (1) the study of the mechanical behaviour of structural materials under neutron irradiation (including steels, inconel, molybdenum, chromium); (2) the determination and modelling of the characteristics of irradiated first wall materials such as beryllium; (3) the detection of abrupt electrical degradation of insulating ceramics under high temperature and neutron irradiation; (4) the study of the dismantling and waste disposal strategy for fusion reactors.; (5) a feasibility study for the testing of blanket modules under neutron radiation. Main achievements in these topical areas in the year 1999 are summarised.

  16. 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.

  17. Fast quench reactor method

    Science.gov (United States)

    Detering, B.A.; Donaldson, A.D.; Fincke, J.R.; Kong, P.C.; Berry, R.A.

    1999-08-10

    A fast quench reaction includes a reactor chamber having a high temperature heating means such as a plasma torch at its inlet and a means of rapidly expanding a reactant stream, such as a restrictive convergent-divergent nozzle at its outlet end. Metal halide reactants are injected into the reactor chamber. Reducing gas is added at different stages in the process to form a desired end product and prevent back reactions. The resulting heated gaseous stream is then rapidly cooled by expansion of the gaseous stream. 8 figs.

  18. Nuclear reactor pressure vessel

    International Nuclear Information System (INIS)

    McDonald, B.N.

    1976-01-01

    In nuclear power reactor systems which have a reactor core inside a pressure vessel, the feedwater inlet pipe and steam discharge nozzle usually require separate pressure vessel penetrations. This requirement involves a great deal of expensive high quality special machining, welding and weld joint testing. The invention overcomes most of these problems by nestling the feedwater inlet pipe inside the steam discharge nozzle. At the same time the individual heat exchanger modules are supported from the pressure vessel at the same location as the nested feedwater inlet pipe and steam discharge nozzle combination, thus eliminating the need to accomodate troublesome differential thermal expansion problems through special structures within the pressure vessel

  19. Computerized reactor monitor and control for research reactors

    International Nuclear Information System (INIS)

    Buerger, L.; Vegh, E.

    1981-09-01

    The computerized process control system developed in the Central Research Institute for Physics, Budapest, Hungary, is described together with its special applications at research reactors. The nuclear power of the Hungarian research reactor is controlled by this computerized system, too, while in Lybia many interesting reactor-hpysical calculations are built into the computerized monitor system. (author)

  20. Reactor operation environmental information document

    Energy Technology Data Exchange (ETDEWEB)

    Haselow, J.S.; Price, V.; Stephenson, D.E.; Bledsoe, H.W.; Looney, B.B.

    1989-12-01

    The Savannah River Site (SRS) produces nuclear materials, primarily plutonium and tritium, to meet the requirements of the Department of Defense. These products have been formed in nuclear reactors that were built during 1950--1955 at the SRS. K, L, and P reactors are three of five reactors that have been used in the past to produce the nuclear materials. All three of these reactors discontinued operation in 1988. Currently, intense efforts are being extended to prepare these three reactors for restart in a manner that protects human health and the environment. To document that restarting the reactors will have minimal impacts to human health and the environment, a three-volume Reactor Operations Environmental Impact Document has been prepared. The document focuses on the impacts of restarting the K, L, and P reactors on both the SRS and surrounding areas. This volume discusses the geology, seismology, and subsurface hydrology. 195 refs., 101 figs., 16 tabs.

  1. The market for research reactors

    International Nuclear Information System (INIS)

    Roegler, H.J.

    1986-01-01

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

  2. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Matsuura, S.; Nakahara, Y.; Takano, H.

    1983-09-01

    Research and development activities in the Department of Reactor Engineering in fiscal 1982 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Since fiscal 1982, Systematic research and development work on safeguards technology has been added to the activities of the Department. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

  3. High Flux Isotope Reactor (HFIR)

    Data.gov (United States)

    Federal Laboratory Consortium — The HFIR at Oak Ridge National Laboratory is a light-water cooled and moderated reactor that is the United States’ highest flux reactor-based neutron source. HFIR...

  4. Bir Koyun-Keçi Sürüsünde Gözlenen Dermatophilus congolensis İnfeksiyonu

    OpenAIRE

    GÖÇMEN, Hüban; ŞEN, Ayşin

    2014-01-01

    Bursa ili İznik ilçesinde 120 adet koyun ve keçinin birarada yetiştirildiği bir işletmede akut eksudatif dermatitis olgusu gözlendi. Sürüdeki 50 adet keçinin yaklaşık %70’i, 70 adet koyunun ise %25’inde semptomlar gözlendi. Lezyonların genellikle baş bölgesinde olduğu saptandı. Deri lezyonlarından alınan kabuk örnekleri bakteriyolojik ve mikolojik yönden incelendi. Bakteriyoskopide; örneklere Giemsa boyama uygulandı ve ardışık dizili koklar düzensiz, uzun ve büyük filamentler halinde gözlendi...

  5. Les Surfaces des corps ou la promesse de l'empreinte dans Pèlerinage d'un artiste amoureux, de Abdelkébir Khatibi

    OpenAIRE

    Gendre , Annick

    2010-01-01

    17 pages ; bibliographie incluse ; texte de travail, en date du 14 mars 2010, pour la conférence donnée à Kenitra le 16 mars 2010, en tant que document complémentaire ; en attente de publication; Stucs, images, apparences, mirages, pages et peau : à la fois malléables et évanescentes, pourtant ni malléables, ni évanescentes, ces surfaces explorées prennent en otage l'artiste amoureux de Abdelkébir Khatibi. En effet, elles semblent initier la khôra qui fonde une anatomie du désir singulière. D...

  6. Türkiye’de Denizcilik Eğitiminin Geleceğine Yönelik Nicel Bir Çalışma Örneği

    Directory of Open Access Journals (Sweden)

    Ünal ÖZDEMİR

    2017-07-01

    Full Text Available Bu çalışma ile ülkemizde yükseköğretim kurumuna (YÖK bağlı denizcilik eğitimi veren lisans düzeyindeki bölümlerde yer alan öğretim üyelerine yönelik kantitatif bir araştırma yapılması amaçlanmıştır. Lisans düzeyinde denizcilik eğitimi veren deniz ulaştırma işletme ve gemi makinaları işletme mühendisliği bölümleri kapsamında yer alan öğretim üyeleri çalışmanın ana kapsamını oluşturmaktadır. Bu bölümlerin eğitim-öğretim faaliyetlerini yerine getirebilmeleri için gerekliliklerini sağlama konusunda yaşanan sorunların, yeni kurulan fakülte ve yüksekokul sayılarının artması ile birlikte daha da çarpıcı boyuta geleceği tahmin edilmektedir. Çalışmada probleme neden olan etkenler kantitatif teknikler yardımı ile incelenmiş ve soruna yönelik çözüm önerileri sunulmaya çalışılmıştır. Probleme neden olan çeşitli etkenler bir araya getirilerek, bu etkenlerin birbirleri ile olan ilişkileri ve önem dereceleri bulanık AHP (Fuzzy Analytic Hierarchy Process ve soruna çözüm sunabilecek çözüm önerileri arasında da bir değerlendirme yapabilmesi adına bulanık TOPSIS (Fuzzy Technique for Order Performance by Similarity to Ideal Solution yönteminin ele alındığı bir model yaklaşımı kullanılmıştır. Çalışma sonuçlarına göre öğretim üyesi sayısının yeterli sayıda olmayışının temel nedenlerinden bazıları sırasıyla; “akademisyen ücretlerinin düşüklüğü”, “denizde çalışanlar için yüksek ücret imkânı”, “üniversiteler tarafından yeteri sayıda akademik kadronun açılmaması” olarak tespit edilmiştir. Bu soruna çözüm getirebilecek en önemli alternatiflerden bazıları ise; “akademisyenlik mesleğine olan ilginin arttırılması, özendirilmesi ve öğrencilerin bu alana yönlendirilmesi”, “YÖK’ün istemiş olduğu gerekliliklerin denizcilik eğitimi veren kurumlar için farklı kategoride d

  7. Lütfi Ömer Akad ve Yalnızlar Rıhtımı (1959): Biçemsel Bir Analiz

    OpenAIRE

    SERTER, S.Serhat

    2009-01-01

    Sinema sanatında biçemi olan bir yönetmen her filmde kendi sinema diline ait unsurları barındırır ve bu dili mutlaka izleyicisine hissettirir. Biçemi oluşturan unsurlar anlatı yapısı, sinematografi, mizansen, kurgu ve ses gibi sinemasal anlatımın temel öğeleridir. Lütfi Ömer Akad, Türk Sinema Tarihi'nde gerçek anlamda sinema dilini kurma ve uygulama açısından akla gelebilecek ilk isimdir. Çünkü ondan önceki dönem, Türk Sineması'nda, tiyatrodan yetişme yönetmenlerin egemenliği altınd...

  8. X ve Gama-Işını Dedektörlerinde Ölü Zaman Düzeltmesi İçin Bir Program

    OpenAIRE

    KARABIDAK, Salih Mustafa; KAYA, Selim; BİNGÖL, Özkan; KAYA, ALİ

    2016-01-01

    X ya da gama ışını detektörlerinin kullanıldığı spektrometrik kantitatif ve kalitatif analizlerinde, analizlerin doğruluğu için sayma kayıplarının belirlenmesi ve telafi edilmesi önemlidir. Spektrometrelerdeki bu sayma kayıpları uzatılan ve uzatılmayan sistem ölü zamanlarından meydana gelir. Bu çalışmada, bu kayıpları telafi etmek için bir bilgisayar program geliştirilmiştir. Programı test etmek için deneysel çalışmalar yapılmıştır. Program, DELPHI program derleyicisiyle kodlanmıştır. Program...

  9. Cumhuriyet Tarihi Üzerine Kısa Bir Dönemlendirme Denemesi / A Short Essay on Periodization of History of Republic

    Directory of Open Access Journals (Sweden)

    Cengiz SUNAY

    2016-01-01

    Full Text Available Türkiye Cumhuriyeti tarihi, bir asra yaklaşan geçmişiyle oldukça keskin dönüşümlerin gözlendiği bir süreci ifade ediyor. Bu dönüşümlerin içeride ve dışarıdaki hangi değişimler ekseninde meydana geldiği konusunda, nesnel araştırmaların yapıldığı bilinmekle birlikte; son tahlilde, cumhuriyet tarihinde olan bitenleri ileri-geri; devrimci-karşı devrimci şeklindeki öznel değerlendirmelerin belirlediği de söylenebilir. Geçmişte, nelerin olup bittiğine dair çoğu anlatımın, örtülü de olsa bu zaafla malul olduğu söylenebilir; bu çerçevede, tarihin bilimden ziyade, ideoloji olduğuna ilişkin tezler üzerinde düşünmek gerekiyor. Tarihin bilim olduğu kabul edilse bile, güçlünün kaleminden okunduğu, bu nedenle bilimlerin en Darwinist’i olduğu tezi, ihmal edilebilir gibi gözükmüyor. Bu çalışmada, Türkiye Cumhuriyeti tarihinin ana hatları üzerinden kuşbakışı bir gözlem deneniyor; ek okumalar öneriliyor. Son doksan beş yılda nelerin olup, nelerin bittiğine ilişkin kimi zaman alternatif bir perspektiften bakılmaya çalışılıyor. / History of the Turkish Republic expresses a period with considerably sharp transformations with its past which almost reaches one century. It is known that objective studies have been made on the axises on which these transformations took place at home and abroad; nevertheless, in the last analysis, it can be claimed that the occurrences in republican history are determined by subjective evaluations such as forward-backward, revolutionary-counter revolutionary etc. It can be said that most narrations as to what happened in the past suffer from this weakness albeit implicitly; within this framework, the thesis that history is more an ideology than a science should be contemplated. Even if it is accepted that history is science, it is hardly negligible that it is read from the pen of the mighty, for which reason it is the most Darwinist of all sciences

  10. SMS Reklamları ve Mobil Bilgi Servislerine Yönelik Tüketici Tutumunu Belirleyen Bir Araştırma

    OpenAIRE

    DURUCASU, R. Reha; AKSOY, N. Figen

    2018-01-01

    Akıllı telefonların gelişmesiyle MMS, Wap, Mobil Uygulamalar, IVR vb. mobil pazarlama mecralarının kullanımında artış meydana gelmiştir. Türkiye’de akıllı telefon kullanım oranı her geçen sene artmaktadır. Buna rağmen işletmeler yaygın bir tüketici kitlesine ulaşmak için halen en çok kullanılan mobil pazarlama mecralarından birisi olan SMS reklamlarını kullanmaya devam etmektedir. Mobil bilgi servisleri ise, kullanıcılar için fayda sağlayan bilgilerin; cep telefonu aracılığıyla kullanıcılara ...

  11. Reactor operation safety information document

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

  12. Nuclear reactors for the future

    International Nuclear Information System (INIS)

    Vijayan, P.K.; Kamble, M.T.; Dulera, I.V.

    2013-01-01

    For the sustainable development of nuclear power plants with enhanced safety features, economic competitiveness, proliferation resistance and physical protection, several advanced reactor developments have been initiated world-wide. The major advanced reactor initiatives and the proposed advanced reactor concepts have been briefly reviewed along with their advantages and challenges. Various advanced reactor designs being pursued in India have also been briefly described in the paper. (author)

  13. Fusion reactor development: A review

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

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

  14. Inertial confinement fusion reactor systems

    International Nuclear Information System (INIS)

    Frank, T.G.; Bohachevsky, I.O.; Pendergrass, J.H.

    1980-01-01

    A variety of reactor cavity concepts, drivers, and energy conversion mechanisms are being considered to realize commercial applications of ICF. Presented in this paper are: (1) a review of reactor concepts with estimates of practically achievable pulse repetition rates; (2) a survey of drivers with estimates of the requirements on reactor conditions imposed by beam propagation characteristics; and (3) an assessment of compatible driver-reactor combinations

  15. Çanakkale Bölgesinde Germeli Tuzaklar (Fyke-Net Üzerine Bir Ön Çalışma.

    Directory of Open Access Journals (Sweden)

    Adnan Ayaz

    2015-12-01

    Full Text Available Germeli tuzaklar göl, nehir, ırmak gibi iç sulara kurulabildiği gibi, deniz kıyısı, dalyan, lagün gibi sığ deniz kıyılarına ve akıntı sistemi bulunan denizlere de kurulabilen bir tür tuzaktır. Germe vasıtasıyla balıkların tuzağa yönelmelerini ve tuzak içine girerek yakalanmasını sağlarlar. Bu çalışmada 36 mm göz uzunluğuna sahip ağlardan yapılmış 6 m uzunluk ve 1x1.5 m ağız genişliğine sahip bir germeli tuzak Çanakkale Boğazı’nda denenmiştir. Germeli tuzak akıntıya dik yerleştirilerek takımın av verimine bakılmıştır. Yapılan denmelerde, tuzak içerisine karagöz (Diplodus vulgaris, iskorpit (Scorpaena sp., ısparoz (Diplodus annularis, çizgili hani (Serranus scriba, barbun (Mullus surmuletus ve mıgri (Conger conger balıkları girmiştir. Ayrıca germe ağı üzerinde de kupes (Boops boops, melanur (Oblada melanura ve çizgili hani (Serranus scriba balıkları galsamalarından yakalanmıştır

  16. Biyodizel ve Karışımlarının Kullanıldığı bir Dizel Motorda Performans ve Emisyon Analizi

    Directory of Open Access Journals (Sweden)

    Ahmet Necati ÖZSEZEN

    2009-02-01

    Full Text Available Bu çalışmada, atık palmiye yağı kökenli biyodizel ve petrol kökenli dizel yakıtı (PKDY ile karışımlarının, bir dizel motordaki performans ve emisyon karakteristikleri üç boyutlu haritalar üzerinden analiz edilmiştir. Biyodizel ve karışımlarının performans ve emisyon karakterlerini belirlemek amacıyla, motor tam yük ve değişik devir testlerine tabi tutulmuştur. Analiz sonucunda, karışımdaki biyodizel oranı arttıkça PKDY'a göre özgül yakıt tüketiminde artış olduğu, motorun döndürme momentinde ise azalma meydana geldiği tespit edilmiştir. Emisyon analizi sonucunda ise, karışımdaki biyodizel oranı ile ilişkili olarak PKDY'a kıyasla yanmamış hidrokarbon (HC, karbon monoksit (CO ve duman koyuluğu emisyonlarında iyileşmeler olduğu, bununla birlikte karbon dioksit (CO2 ve azot oksit (NOx emisyonlarının motor devrine göre kararlı bir yapı sergilemediği belirlenmiştir.

  17. ULUSLARARASI PORTFÖY YÖNETIMINDE REJIM GEÇIŞKEN KARAR DESTEK MODELLERI: GELIŞMEKTE OLAN MENKUL KIYMET PIYASALARI ÜZERINE BIR UYGULAMA

    Directory of Open Access Journals (Sweden)

    Kadir TUNA

    2014-04-01

    Full Text Available Bu makale, portföy yatırımlarında bir karar destek sistemi olarak rejim geçişken modellerin ne şekilde kullanılabileceğini gelişmekte olan hisse senedi piyasalarına ait zaman serilerini ve Gauss yazılım programını kullanarak incelemektedir. Yönetim bilişim sistemlerinde, model riskinin minimize edilmesi, karar destek siteminin uygulanacağı problemin net olarak tanımlanması ve bu problemin çözümünde kullanılacak modelin doğru seçilmesi ile mümkündür. Ekonometrik testlerin sonuçları, Ukrayna hariç, gelişmekte olan ekonomilerde hisse senetleri piyasalarında 09/01/2004-13/09/2007 tarihleri arasında, ABD hisse senedi piyasaları ile karşılaştırıldığında kalıcı bir volatilitenin gözlemlendiğini ortaya koymaktadır. Bu kapsamda, Türkiye, Rusya, Ukrayna, Brezilya, Lübnan, ABD (Dow Jones Industrial Average ve MSCI (Morgan Stanley Composite Index hisse senedi piyasalarında rejim geçişkenliği ekonometrik olarak karşılaştırmalı incelenmiştir.

  18. Maqâshid al-Qur’ân dalam Ayat Kebebasan Beragama Menurut Thahâ Jâbir al-‘Alwânî

    Directory of Open Access Journals (Sweden)

    Ah. Fawaid

    2017-12-01

    Full Text Available Maqâshid al-Qur’ân in the Verses of Religious Freedom in Interpretation of Thahâ Jâbir al-’Alwânî. This article is aimed at describing Thahâ Jâbir al-‘Alwânî’s interpretation on various verses dealing with the issues of religious freedom. Adapting an approach of maqâshid al-Qur’ân, the present paper comes to answer two main issues on the true of Alwânî’s maqâshid al-Qur’ân perception and the theoretical application of Alwânî’s maqâshid al-Qur’ân in interpreting verses of religious freedom. According to ‘Alwânî, it was concluded that there are three main segments that he called al-maqâshid al-Qur’âniyyah al-hâkimah: (1 al-tawhîd, (2 al-tazkiyah, and (3 al-‘umrân. ‘Alwânî stated that freedom of interfaith religion is important goal of sharia meaning. Freedom of interfaith religion, on the other hand, is one of the important embodiments in believing the God and tauhid. Seeing this pattern, the later purpose of the Quran is tazkiyah. This term is a value that enables people apply the message, fulfill the promise, and can perform the tasks of the caliphate. When such principles are implemented, something appears that Alwânî called ‘umrân as the next purpose of the Quran can be manifested well. ‘Umrân or ‘prosperity’ in which human being performs as a khalifah actually can create baldatun thayyibatun wa rabbun ghafûr as the real welfare.

  19. REACTOR FUEL ELEMENTS TESTING CONTAINER

    Science.gov (United States)

    Whitham, G.K.; Smith, R.R.

    1963-01-15

    This patent shows a method for detecting leaks in jacketed fuel elements. The element is placed in a sealed tank within a nuclear reactor, and, while the reactor operates, the element is sparged with gas. The gas is then led outside the reactor and monitored for radioactive Xe or Kr. (AEC)

  20. Engineering reactors for catalytic reactions

    Indian Academy of Sciences (India)

    ... improvements in reactor performance. In this article, application of recent (and not so recent) developments in engineering reactors for catalytic reactions is discussed. Some examples where performance enhancement was realized by catalyst design, appropriate choice of reactor, better injection and dispersion strategies ...

  1. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-04-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis

  2. Fast reactors: potential for power

    International Nuclear Information System (INIS)

    1983-02-01

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

  3. Digital control of research reactors

    International Nuclear Information System (INIS)

    Crump, J.C. III.; Richards, W.J.; Heidel, C.C.

    1991-01-01

    Research reactors provide an important service for the nuclear industry. Developments and innovations used for research reactors can be later applied to larger power reactors. Their relatively inexpensive cost allows research reactors to be an excellent testing ground for the reactors of tomorrow. One area of current interest is digital control of research reactor systems. Digital control systems offer the benefits of implementation and superior system response over their analog counterparts. At McClellan Air Force Base in Sacramento, California, the Stationary Neutron Radiography System (SNRS) uses a 1,000-kW TRIGA reactor for neutron radiography and other nuclear research missions. The neutron radiography beams generated by the reactor are used to detect corrosion in aircraft structures. While the use of the reactor to inspect intact F-111 wings is in itself noteworthy, there is another area in which the facility has applied new technology: the instrumentation and control system (ICS). The ICS developed by General Atomics (GA) contains several new and significant items: (a) the ability to servocontrol on three rods, (b) the ability to produce a square wave, and (c) the use of a software configurator to tune parameters affected by the actual reactor core dynamics. These items will probably be present in most, if not all, future research reactors. They were developed with increased control and overall usefulness of the reactor in mind

  4. Reactor component automatic grapple

    International Nuclear Information System (INIS)

    Greenaway, P.R.

    1982-01-01

    A grapple for handling nuclear reactor components in a medium such as liquid sodium which, upon proper seating and alignment of the grapple with the component as sensed by a mechanical logic integral to the grapple, automatically seizes the component. The mechanical logic system also precludes seizure in the absence of proper seating and alignment. (author)

  5. LMFBR type reactor

    International Nuclear Information System (INIS)

    Kumaoka, Yoshio; Kawamura, Yutaka.

    1990-01-01

    A main vessel support skirt is supported by a base mat of reactor buildings and the base mat is supported by means of an earthquake-proof device on concretes of a lower raft disposed on ground rocks. The earthquake-proof device is constituted by alternately stacking, laminating and press-bonding thin steel plates together with thin rubber layers between an upper flange and a lower raft. Thus, for the horizontal seismic vibrations, the period of the swinging in the horizontal direction of the buildings is made greater than the swinging period of earthquakes by the earthquake-proof device to reduce the impact shocks of earthquakes. Further, for the vertical seismic vibrations, the input seismic movements are not amplified during transmission from the base mat of the buildings to the reactor structure by way of the support skirt of the main vessel, due to the shortened load transmission path and the seismic power design to the reactor structure can be moderated sufficiently. A safety LMFBR type reactor with reduced construction cost and improved reliability can be attained. (N.H.)

  6. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    Baddley, A.H.

    1981-01-01

    A method of constructing a radiation shielding plug for use in the roof of the coolant containment vault of liquid metal cooled fast breeder reactors is described. The construction allows relative movement of that part of service cables and pipes which are carried by the fixed roof and that part which is carried by the rotatable plug. (U.K.)

  7. The reactor vessel steels

    International Nuclear Information System (INIS)

    Bilous, W.; Hajewska, E.; Szteke, W.; Przyborska, M.; Wasiak, J.; Wieczorkowski, M.

    2005-01-01

    In the paper the fundamental steels using in the construction of pressure vessel water reactor are discussed. The properties of these steels as well as the influence of neutron irradiation on its degradation in the time of exploitation are also done. (authors)

  8. Thermal Reactor Safety

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods.

  9. Thermal Reactor Safety

    International Nuclear Information System (INIS)

    1980-06-01

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods

  10. Hydrodynamic Cavitation Reactors contd…

    Indian Academy of Sciences (India)

    First page Back Continue Last page Overview Graphics. Hydrodynamic Cavitation Reactors contd… Reservoir: 10 L capacity. Centrifugal Pump :1.5kW). Orifice plate (different configurations in terms of number and diameter of the holes). Bypass line (for controlling the inlet pressure and the flow rate into the cavitation ...

  11. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Sekimizu, Koichi

    1980-01-01

    Purpose: To improve the performance and secure the safety of a nuclear reactor by rapidly computing and display the power density in the nuclear reactor by using a plurality of processors. Constitution: Plant data for a nuclear reactor containing the measured values from a local power monitor LPRM are sent and recorded in a magnetic disc. They are also sent to a core performance computer in which burn-up degree distribution and the like are computed, and the results are sent and recorded in the magnetic disc. A central processors loads programs to each of the processors and applies data recorded in the magnetic disc to each of the processors. Each of the processors computes the corresponding power distribution in four fuel assemblies surrounding the LPRM string by the above information. The central processor compiles the computation results and displays them on a display. In this way, power distribution in the fuel assemblies can rapidly be computed to thereby secure the improvement of the performance and safety of the reactor. (Seki, T.)

  12. Reactor instrumentation and control

    International Nuclear Information System (INIS)

    Wach, D.; Beraha, D.

    1980-01-01

    The methods for measuring radiation are shortly reviewed. The instrumentation for neutron flux measurement is classified into out-of-core and in-core instrumentation. The out-of-core instrumentation monitors the operational range from the subcritical reactor to full power. This large range is covered by several measurement channels which derive their signals from counter tubes and ionization chambers. The in-core instrumentation provides more detailed information on the power distribution in the core. The self-powered neutron detectors and the aeroball system in PWR reactors are discussed. Temperature and pressure measurement devices are briefly discussed. The different methods for leak detection are described. In concluding the plant instrumentation part some new monitoring systems and analysis methods are presented: early failure detection methods by noise analysis, acoustic monitoring and vibration monitoring. The presentation of the control starts from an qualitative assessment of the reactor dynamics. The chosen control strategy leads to the definition of the part-load diagram, which provides the set-points for the different control systems. The tasks and the functions of these control systems are described. In additiion to the control, a number of limiting systems is employed to keep the reactor in a safe operating region. Finally, an outlook is given on future developments in control, concerning mainly the increased application of process computers. (orig./RW)

  13. Nuclear Reactor Sharing Program

    International Nuclear Information System (INIS)

    1994-01-01

    The Ohio State University Research Reactor (OSURR) is licensed to operate at a maximum power level of 500 kW. A pool-type reactor using flat-plate, low enriched fuel elements, the OSURR provides several experimental facilities including two 6-inch i.d. beam ports, a graphite thermal column, several graphite-isotope-irradiation elements, a pneumatic transfer system (Rabbit), various dry tubes, and a Central Irradiation Facility (CIF). The core arrangement and accessibility facilitates research programs involving material activation or core parameter studies. The OSURR control room is large enough to accommodate laboratory groups which can use control instrumentation for monitoring of experiments. The control instrumentation is relatively simple, without a large amount of duplication. This facilitates opportunities for hands-on experience in reactor operation by nuclear engineering students making reactor parameter measurements. For neutron activation analysis and analyses of natural environmental radioactivity, the NRL maintains the gamma ray spectroscopy system (GRSS). It is comprised of two PC-based 8192-channel multichannel analyzers (MCAs) with all the required software for quantitative analysis. A 3 double-prime x 3 double-prime NaI(Tl), a 14 percent Ge(Li), and a High Purity Germanium detector are currently available for use with the spectroscopy system

  14. The Chernobyl reactor accident

    International Nuclear Information System (INIS)

    1986-01-01

    The documentation abstracted contains a complete survey of the broadcasts transmitted by the Russian wire service of the Deutsche Welle radio station between April 28 and Mai 15, 1986 on the occasion of the Chernobyl reactor accident. Access is given to extracts of the remarkable eastern and western echoes on the broadcasts of the Deutsche Welle. (HP) [de

  15. Nuclear power reactor physics

    International Nuclear Information System (INIS)

    Barjon, Robert

    1975-01-01

    The purpose of this book is to explain the physical working conditions of nuclear reactors for the benefit of non-specialized engineers and engineering students. One of the leading ideas of this course is to distinguish between two fundamentally different concepts: - a science which could be called neutrodynamics (as distinct from neutron physics which covers the knowledge of the neutron considered as an elementary particle and the study of its interactions with nuclei); the aim of this science is to study the interaction of the neutron gas with real material media; the introduction will however be restricted to its simplified expression, the theory and equation of diffusion; - a special application: reactor physics, which is introduced when the diffusing and absorbing material medium is also multiplying. For this reason the chapter on fission is used to introduce this section. In practice the section on reactor physics is much longer than that devoted to neutrodynamics and it is developed in what seemed to be the most relevant direction: nuclear power reactors. Every effort was made to meet the following three requirements: to define the physical bases of neutron interaction with different materials, to give a correct mathematical treatment within the limit of necessary simplifying hypotheses clearly explained; to propose, whenever possible, numerical applications in order to fix orders of magnitude [fr

  16. Reactor control system. PWR

    International Nuclear Information System (INIS)

    2009-01-01

    At present, 23 units of PWR type reactors have been operated in Japan since the start of Mihama Unit 1 operation in 1970 and various improvements have been made to upgrade operability of power stations as well as reliability and safety of power plants. As the share of nuclear power increases, further improvements of operating performance such as load following capability will be requested for power stations with more reliable and safer operation. This article outlined the reactor control system of PWR type reactors and described the control performance of power plants realized with those systems. The PWR control system is characterized that the turbine power is automatic or manually controlled with request of the electric power system and then the nuclear power is followingly controlled with the change of core reactivity. The system mainly consists of reactor automatic control system (control rod control system), pressurizer pressure control system, pressurizer water level control system, steam generator water level control system and turbine bypass control system. (T. Tanaka)

  17. Reactor vessel stud tensioner

    International Nuclear Information System (INIS)

    Malandra, L.J.; Beer, R.W.; Salton, R.B.; Spiegelman, S.R.; Cognevich, M.L.

    1982-01-01

    A quick-acting stud tensioner, for facilitating the loosening or tightening of a stud nut on a reactor vessel stud, has gripper jaws which when the tensioner is lowered into engagement with the upper end of the stud are moved inwards to grip the upper end and which when the tensioner is lifted move outward to release the upper end. (author)

  18. Fossil fuel furnace reactor

    Science.gov (United States)

    Parkinson, William J.

    1987-01-01

    A fossil fuel furnace reactor is provided for simulating a continuous processing plant with a batch reactor. An internal reaction vessel contains a batch of shale oil, with the vessel having a relatively thin wall thickness for a heat transfer rate effective to simulate a process temperature history in the selected continuous processing plant. A heater jacket is disposed about the reactor vessel and defines a number of independent controllable temperature zones axially spaced along the reaction vessel. Each temperature zone can be energized to simulate a time-temperature history of process material through the continuous plant. A pressure vessel contains both the heater jacket and the reaction vessel at an operating pressure functionally selected to simulate the continuous processing plant. The process yield from the oil shale may be used as feedback information to software simulating operation of the continuous plant to provide operating parameters, i.e., temperature profiles, ambient atmosphere, operating pressure, material feed rates, etc., for simulation in the batch reactor.

  19. Fast reactor programme

    International Nuclear Information System (INIS)

    Plakman, J.C.

    1982-01-01

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

  20. Reactor operational transient analysis

    International Nuclear Information System (INIS)

    Shin, W.K.; Chae, S.K.; Han, K.I.; Yang, K.S.; Chung, H. D.; Kim, H.G.; Moon, H.J.; Ryu, Y.H.

    1983-01-01

    To build up efficient capability of safety review and inspection for the nuclear power plants, four area of studies have performed as follows: 1) In order to search the most optimized operating method during load follow operating schemes, automatic control and normal control, are compared each other under the CAOC condition. The analysis performed by DDID code has shown that the reactor has to be controlled by the operator manually during load follow operation. 2) Through the sensitivity analysis by COBRA code, the operating parameters, such as coolant pressure, flow rate, inlet temperature, and power distribution are shown to be important to the determination of DNBR. Expecially, inlet temperature of primary coolant system is appeared as the most senstive parameter on DNBR. 3) FRAPCON code is adapted to study the sensitivity of several operational parameters on the mechanical properties of reactor fuel rod. 4) The calculations procedure which is required to be obtained the neutron fluence at the reactor vessel and the spectrum at the surveillance capsule is established. The results of computation are conpared with those of FSAR and SWRI report and proved its applicability to reactor surveillance program. (Author)

  1. Fusion reactor materials

    International Nuclear Information System (INIS)

    Sethi, V.K.; Scholz, R.; Nolfi, F.V. Jr.; Turner, A.P.L.

    1980-01-01

    Data are given for each of the following areas: (1) effects of irradiation on fusion reactor materials, (2) hydrogen permeation and materials behavior in alloys, (3) carbon coatings for fusion applications, (4) surface damage of TiB 2 coatings under energetic D + and 4 He + irradiations, and (5) neutron dosimetry

  2. Reactor physics of CANFLEX

    International Nuclear Information System (INIS)

    Sim, K. S.; Min, Byung Joo.

    1997-07-01

    Characteristic of reactor physics for CANFLEX-NU fuel core were calculated using final fuel design data. The results of analysis showed that there was no impact on reactor operations and safety. The above results of calculations and analysis were described in the physics design for CANFLEX-NU core. Various fuel models were evaluated for selecting high burnup fuel using recovered uranium. It is judged to be worse effects for reactor safety. Hence, the use of graphite within fuel was proposed and its results showed to be better. The analysis system of reactor physics for design and analysis of high burnup fuel was evaluated. Lattice codes and core code were reviewed. From the results, the probability of WIMS-AECL and HELIOS is known to be high for analysis of high burnup fuel. For the core code, RFSP, it was evaluated that the simplified 2 group equation should be replaced by explicit 2 group equation. This report also describes about the status of critical assemblies in other countries. (author). 58 refs., 41 tabs., 126 figs

  3. WATER BOILER REACTOR

    Science.gov (United States)

    King, L.D.P.

    1960-11-22

    As its name implies, this reactor utilizes an aqueous solution of a fissionable element salt, and is also conventional in that it contains a heat exchanger cooling coil immersed in the fuel. Its novelty lies in the utilization of a cylindrical reactor vessel to provide a critical region having a large and constant interface with a supernatant vapor region, and the use of a hollow sleeve coolant member suspended from the cover assembly in coaxial relation with the reactor vessel. Cool water is circulated inside this hollow coolant member, and a gap between its outer wall and the reactor vessel is used to carry off radiolytic gases for recombination in an external catalyst chamber. The central passage of the coolant member defines a reflux condenser passage into which the externally recombined gases are returned and condensed. The large and constant interface between fuel solution and vapor region prevents the formation of large bubbles and minimizes the amount of fuel salt carried off by water vapor, thus making possible higher flux densities, specific powers and power densities.

  4. Cermet fuel reactors

    International Nuclear Information System (INIS)

    Cowan, C.L.; Palmer, R.S.; Van Hoomissen, J.E.; Bhattacharyya, S.K.; Barner, J.O.

    1987-09-01

    Cermet fueled nuclear reactors are attractive candidates for high performance space power systems. The cermet fuel consists of tungsten-urania hexagonal fuel blocks characterized by high strength at elevated temperatures, a high thermal conductivity and resultant high thermal shock resistance. Key features of the cermet fueled reactor design are (1) the ability to achieve very high coolant exit temperatures, and (2) thermal shock resistance during rapid power changes, and (3) two barriers to fission product release - the cermet matrix and the fuel element cladding. Additionally, thre is a potential for achieving a long operating life because of (1) the neutronic insensitivity of the fast-spectrum core to the buildup of fission products and (2) the utilization of a high strength refractory metal matrix and structural materials. These materials also provide resistance against compression forces that potentially might compact and/or reconfigure the core. In addition, the neutronic properties of the refractory materials assure that the reactor remains substantially subcritical under conditions of water immersion. It is concluded that cermet fueled reactors can be utilized to meet the power requirements for a broad range of advanced space applications. 4 refs., 4 figs., 3 tabs

  5. Integral Fast Reactor Program

    International Nuclear Information System (INIS)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1993-06-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R ampersand D

  6. Nuclear reactor vessels

    International Nuclear Information System (INIS)

    Sato, Yoshimi; Fukuda, Yoshio.

    1987-01-01

    Purpose: To improve the strength and reliability by moderating thermal stresses produced to the furnace walls of a reactor vessel by the thermal shocks upon reactor shutdown and tripping and reducing the generation of developing thermal ratchet strains produced upon repeating thermal shocks. Constitution: Upon occurrence of reactor shutdown or tripping, the temperature is detected and the pressure of the cover gas is controlled such that the axial temperature slope is decreased to displace the liquid surface in an annular vessel. Then, for attaining the stress reducing temperature, control is so conducted that the temperature of the lower portion is not higher than the upper portion in the axial temperature distribution of the reactor vessel. By controlling the pressure of the cover gas in the annular vessel in this way, the liquid level can be raised to a cover gas portion remaining at a high temperature state. Further, the temperature of the furnace wall can always be decreased to a temperature of the high temperature plenum thereby enabling to moderate the thermal stresses. (Yoshihara, H.)

  7. Studies on reactor physics

    International Nuclear Information System (INIS)

    1960-01-01

    Most of the peaceful applications of atomic energy are inherently dependent on advances in the science and technology of nuclear reactors, and aspects of this development are part of a major programme of the International Atomic Energy Agency. The most useful role that the Agency can play is as a co-ordinating body or central forum where the trends can be reviewed and the results assessed. Some of the basic studies are carried out by members of the Agency's own scientific staff. The Agency also convenes groups of experts from different countries to examine a particular problem in detail and make any necessary recommendations. Some of the important subjects are discussed at international scientific meetings held by the Agency. One of the subjects covered by such studies is the physics of nuclear reactors and a specific topic recently discussed was Codes for Reactor Computations, on which a seminar was held in Vienna in April this year. Another The members of the Panel described the development of heavy water reactors, the equipment and methods of research currently used, and plans for further development in their respective countries meeting of Panel of Experts on Heavy Water Lattices was held in Vienna in August 1959

  8. 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

  9. Fusion reactor materials

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1989-01-01

    This paper discuses the following topics on fusion reactor materials: irradiation, facilities, test matrices, and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; fundamental mechanical behavior; radiation effects; development of structural alloys; solid breeding materials; and ceramics.

  10. Method of reactor operation

    International Nuclear Information System (INIS)

    Nakajima, Takeshi

    1988-01-01

    Purpose: To minimize the power change due to the increase in xenone and power distribution after reaching the rated power in the case of using fresh fuels no requiring conditioning operation thereby starting the nuclear reactor in a short period of time and stably. Method: When control rods are entirely inserted only with a purpose for the compensation of the reactivity in a xenon-unsaturated state such as upon starting of the nuclear reactor, peaking is generated in the lower portion of the reactor core. Therefore, it is necessary to insert control rods for additionally suppressing the peaking in the lower portion of the reactor core to a relatively shallow level. In view of the above, a plurality of control rods are divided into a first control rod group finally inserted in the rated power state and a second control rod group other than the above. Then, the power is once elevated to the rated power level by means of such an intermediate control rod pattern that the ratio of the total extraction amount between the first control rod group and the second control rod group is made constant. Then, the control rods are extracted stepwise while setting the ratio of the total extraction amount constant in accordance with the change of the accumulating amount of xenone, to thereby obtain the purpose. (kamimura, M.)

  11. Integral Fast Reactor concept

    Energy Technology Data Exchange (ETDEWEB)

    Till, C.E.; Chang, Y.I.

    1986-01-01

    The Integral Fast Reactor (IFR) is an innovative LMR concept, being developed at Argonne National Laboratory, that fully exploits the inherent properties of liquid metal cooling and metallic fuel to achieve breakthroughs in economics and inherent safety. This paper describes key features and potential advantages of the IFR concept, technology development status, fuel cycle economics potential, and future development path.

  12. Integral Fast Reactor concept

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.

    1986-01-01

    The Integral Fast Reactor (IFR) is an innovative LMR concept, being developed at Argonne National Laboratory, that fully exploits the inherent properties of liquid metal cooling and metallic fuel to achieve breakthroughs in economics and inherent safety. This paper describes key features and potential advantages of the IFR concept, technology development status, fuel cycle economics potential, and future development path

  13. Tandem mirror reactor

    International Nuclear Information System (INIS)

    Moir, R.W.; Barr, W.L.; Carlson, G.A.

    1977-01-01

    A parametric analysis and a preliminary conceptual design for a 1000 MWe Tandem Mirror Reactor (TMR) are described. The concept is sufficiently attractive to encourage further work, both for a pure fusion TMR and a low technology TMR Fusion-Fission Hybrid

  14. Nuclear Reactors and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Cason, D.L.; Hicks, S.C. [eds.

    1992-01-01

    This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

  15. Orphee reactor experimental equipment

    International Nuclear Information System (INIS)

    1987-01-01

    Experimental equipment around the ORPHEE reactor is presented. The neutron source; and the spectrometers and sample environment (inelastic and quasi-elastic scattering, elastic scattering, spread scattering, small angle scattering) are described. An experiment proposal and reports guide is supplied [fr

  16. NEUTRONIC REACTOR FUEL PUMP

    Science.gov (United States)

    Cobb, W.G.

    1959-06-01

    A reactor fuel pump is described which offers long life, low susceptibility to radiation damage, and gaseous fission product removal. An inert-gas lubricated bearing supports a journal on one end of the drive shsft. The other end has an impeller and expansion chamber which effect pumping and gas- liquid separation. (T.R.H.)

  17. Mirror reactor blankets

    International Nuclear Information System (INIS)

    Lee, J.D.; Barmore, W.L.; Bender, D.J.; Doggett, J.N.; Galloway, T.R.

    1976-01-01

    The general requirements of a breeding blanket for a mirror reactor are described. The following areas are discussed: (1) facility layout and blanket maintenance, (2) heat transfer and thermal conversion system, (3) materials, (4) tritium containment and removal, and (5) nuclear performance

  18. Low Power Reactor Comparisons

    Energy Technology Data Exchange (ETDEWEB)

    Homeyer, W. G. [General Atomics Site, San Diego, CA (United States)

    1969-02-21

    Studies were made of a number of low power (< 300 kWe) thermionic reactors containing flashlight or unit cell thermionic fuel elements. The objective of these studies was to determine the feasibility of producing a net power of 50 to 100 kWe with a power plant weighing 3000 to 4000 lb (1360 to 1820 kg).

  19. Hadoop ve Mapreduce Teknolojisi aracılığıyla Gıda-tabanlı Mobil Uygulamaları için bir Arama Hizmeti

    Directory of Open Access Journals (Sweden)

    Mehmet Akif ÇİFÇİ

    2017-02-01

    Full Text Available Özet. Son zamanlarda güvenli gıda tüketimi ve e-sağlık üzerine birçok mobil uygulama geliştirilmiştir. Sağlık bilinciyle hareket eden kullanıcılar, özellikle zararlı gıda ve katkı maddelerinden kaçınarak, güvenli gıda tüketimi için bu alana yönelik uygulamaları son derece önemsemektedir. Günümüzde bu tür uygulamaları destekleyen yapılandırılmış veya yapılandırılmamış verileri içeren kapsamlı bir veritabanı eksikliği bulunmaktadır. Bu makalede mobil uygulamalar için sağlıklı bir gıda tüketimi arama hizmeti sunan Hadoop ve Mapreduce (MR yaklaşımından yararlanan Mobile Apps Search Sevice (MSS önerilmektedir. MSS, gıda ve gıda katkı maddeleri alanına yönelik hizmet vermekte ve mobil kullanıcıların sorgularını ele alarak bilgi sunma hizmetini kapsamaktadır. MSS herhangi bir mobil uygulamanın arkasındaki işlem olarak çalışabilir. Çünkü MSS, bir arama motoru ile aynı mantıkla çalışır; mobil uygulamalarda tıklamalarla oluşan kullanıcı sorgularına yanıt aramak ve kullanıcıya bilgi sunmak için bağlantılı bilgileri kataloglar ve web kaynakları üzerinde tarama yapar. MSS’in tasarımı ve geliştirilmesi, sistem mimarisi, sorgu anlayışı, Hadoop-MR ortamında ve Action Script kullanımı ile vurgulanmaktadır. Makalenin içinde, bir örnek olay incelemesi ile MSS'in genel özellikleri, işleyişi ve mevcut faydaları ortaya konulmuştur.Anahtar Kelimeler: Mobil Sağlık Sistemleri, Gıda-Tabanlı Mobil Uygulamalar, Hadoop ve MR, Mobil Sistemler İçin Büyük Veri, Mobil Bilgi Servisi Abstract. Many mobile applications on safe food consumption and e-health have been developed recently. Health conscious users highly regard such applications for safe food consumption, especially avoiding offending foods and additives. However, there is the lack of a comprehensive database containing structured or unstructured data to support such applications. In this paper we

  20. Meşrutiyet Devri Tarih Eğitimine Dair Bir Kaynak: Fatihli Mehmet Tevfik Paşa Ve Eseri “Osmanlı Tarihi”

    Directory of Open Access Journals (Sweden)

    Galip Çağ

    2012-10-01

    Full Text Available Özet: Meşrutiyet devri tarih ders kitapları, gerek devrin yönetiminin tarihe olan bakış açısını yansıtması gerekse de bu devirde yetişen ve Türkiye Cumhuriyeti’ni kuran nesillerin zihnindeki tarih algısının şekillenmesindeki etkileriyle oldukça önemli, ilk elden kaynaklardır. Bu nedenle meşrutiyet devri ders kitaplarının incelenmesi ve muhtevalarının bilinmesi ciddi bir önem arz eder. Çalışmamız, bu bağlamda meşrutiyet devrinde uzun yıllar askeri idadilerde ders kitabı olarak okutulan bir “Osmanlı Tarihi”ni ve yazarı Fatihli Mehmet Tevfik Paşa’yı tanıtmak amacıyla hazırlanmıştır. Fatihli Mehmet Tevfik Paşa’nın eserini, askeri idadilerde okutulması nedeniyle dönemin diğer tarih ders kitaplarından ayrı tutmak gerekir. Çünkü başta Mustafa Kemal Atatürk olmak üzere askeri idadilerde yetişen, Türkiye Cumhuriyeti’ne yön veren birçok isim Fatihli Mehmet Tevfik Paşa’nın eseriyle tarihi öğrenmiştir. Fatihli Mehmet Tevfik Paşa ile Atatürk’ün yolu bir noktada daha kesişmektedir. Atatürk’ün Manastır Askeri İdadisi’ndeki tarih öğretmenin adı Mehmet Tevfik Bilge’dir. Atatürk’ün kendisinden övgüyle bahsettiği, Türk Tarih Kurumu’nun üyeliğine atadığı ve bir dönem mebusluk da yaptırdığı Mehmet Tevfik Bilge isim benzerliği nedeniyle Mehmet Tevfik Paşa ile karıştırılmıştır. Birçok araştırmada Mehmet Tevfik Bilge’ye atfedilen Osmanlı Tarihi adlı eserin aslında Mehmet Tevfik Paşa’ya ait olduğunun izahı çalışmamızın diğer ana temasıdır. Anahtar Kelimeler: Ders Kitabı, Tarih, Osmanlı, Fatihli Mehmet Tevfik, Tarih Öğretimi Abstract: Meşrutiyet era history textboks are importance reliable resources not only they reflect the understanding of the Meşrutiyet by the state but also of the effects of these boks on generations who later founded the republic. Therefore making research about these textbooks have great