WorldWideScience

Sample records for bir reactor

  1. Spondilokostal Dizostoz: Bir Olgu

    OpenAIRE

    UÇAR, ?it; KEPENEKL?, Eda; Zorlu, Pelin; Doksöz, Önder; Ç?FTÇ?, Atilla

    2007-01-01

    Spondilo-kostal dizostoz, boyun, toraks ve lomber bölgeyi içerebilen vertebra ve kosta anomalileri ile karakterize, 1938?de tanımlanmış, nadir görülen bir hastalıktır. Prevalansı 0.25/10.000 olarak bildirilmiştir. Solunum sık?ntısı nedeniyle ba?vuran üç aylık olgu, nadir görülmesi, prenatal tanı konabilmesi, bildirilen yeni destek ve tedavi yöntemleri nedeni ile sunulmuştur.

  2. BIR - The View of the Industry

    International Nuclear Information System (INIS)

    BIR is an international trade federation representing the world’s recycling industry, covering in particular ferrous and non-ferrous metals, paper and textiles. Plastics, rubber and tyres are also studied and traded by some BIR members. About 800 companies and national federations from over 70 countries are affiliated to BIR. Together they offer an international forum for industrial exchange and business contacts. They provide their expertise to other industrial sectors and political groups in order to promote recycling

  3. Plastinasyon bir bilim mi yoksa garip bir gösteri mi?

    OpenAIRE

    Üstün, Çağatay

    2002-01-01

    Plastinasyon, anatomik örneklerin yaşamsal koşullardaki özelliklerini koruyarak çok uzun süre saklanmasına yönelik benzersiz bir metottur. Plastize edilmiş örnekler yüksek ısılara dirençli, kokusuz, zehirsiz özelliklere sahiptir. Bunlar, öğretmenler ve öğrenciler tarafından eldiven gibi koruyucu malzemelere gereksinim duyulmadan elle kullanılabilirler. Plastinasyon, anatomik örneklerin yağ ve sudan arındırılarak polimer bir maddeyle kaplandığı bir yöntemdir. Bu yöntem 1978 yılında...

  4. BIR 2014 - Bibliometric-enhanced Information Retrieval

    DEFF Research Database (Denmark)

    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......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...

  5. Israel's Bir Zeit University: A Center for Palestinian Nationalism.

    Science.gov (United States)

    Clark, Staughton

    1981-01-01

    Located in Israel's West Bank area, BirZeit University has always been and remains the central incubator of West Bank intellectual radicalism in Israel. The majority of law-abiding, serious students are actually afraid, or intimidated, of speaking out against the PLO or its campus supporters. (MLW)

  6. Deri infeksiyonu sonrası staphylococcus aureus spondiliti: bir olgu sunumu

    OpenAIRE

    B.M, Suntur; O.R, Sipahi; Çallı, C.; Dalbastı, T; Büke, Ç

    2007-01-01

    Erişkinde spondilit nadir rastlanan fakat ciddi bir hastalıktır. Deri infeksiyonu Staphylococcus aureus'a bağlı spondilit için nadir bir predispozan faktördür. Bu bildiride deri infeksiyonu sonrası gelişen bir S. aureus spondiliti vakasının sunulması amaçlanmıştır.

  7. İntroventriküler Araknoid Kist ( Bir olgu nedeniyle )

    OpenAIRE

    İYİGÜN,, Ö.; ÇELİK, F.; KANDEMİR, B.; ŞENEL, A.

    2010-01-01

    Familial hypercholesterolemia is an infrequent systemic disease closely associated with coronary artery disease and atherosclerosis. In this report, we reported a case of familial hypercholesterolemia tip Ila with typical systemic symtoms as well as numerous extremital xantomas and the relevant literature reviewed. Ailesel hiperkolesterolemi koroner arter hastalığı ve arterosklerozis ile yakın ilişkisi bulunan sistemik bir hastalıktır. Bu makalede, tipik semptomlarla birlikte çeşitli büy...

  8. DAO Spectroscopic classification of SN 2016bir in SDSS J131405.16+335510.1

    Science.gov (United States)

    Balam, D. D.; Graham, M. L.

    2016-04-01

    A noisy spectrum was obtained of SN 2016bir (ATEL #8857) on Apr. 10.36 UT using the 1.82-m Plaskett telescope (National Research Council of Canada) covering the range 405-710 nm (resolution 0.32 nm). Cross-correlation with a template library using SNID (Blondin & Tonry 2007, ApJ, 666, 1024) shows 2016bir to most resemble the spectrum of a type-Ib supernova approximately 1 week pre-maximum light.

  9. 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.

  10. Bukkal bölgede pleomorfik adenoma: bir olgu sunumu

    Directory of Open Access Journals (Sweden)

    Defne Akpinar

    2011-10-01

    Full Text Available

    Introduction: Pleomorphic adenoma is most common tumor (%50 of the major and minor salivary glands. Seventy percent of the tumors of the minor salivary glands are pleomorphic adenomas, and the most common intraoral site is the palate, followed by the upper lip and buccal mucosa. The tumor is usually solitary and presents as a slow growing, painless, firm single nodular mass.

    Case report: A 56 -year-old female with a painless buccal mass that slowly increased in size was referred Department of Oral and Maxillofacial Surgery of Dentistry Faculty of Gazi University. Clinic examination and radiographic evaluation was determined painless, firm and extraoral expansive mass in the right buccal region. Lesion was enucleationed with its capsule. Histologic analysis confirmed the diagnosis of pleomorphic adenoma with no carcinomatous foci. The 24-month follow up showed good healing of the buccal mucosa. Conclusion: Through the present case report and review literatures, it is suggested that the minor salivary gland tumors are characterized by the higher incidence benign tumors, especially of pleomorphic adenoma.

    ÖZET

    Giriş: Pleomorfik adenoma majör ve minör tükürük bezlerinin en yaygın (%50 görülen tümörüdür. Minör tükürük bezi tümörlerinin %70’ini pleomorfik adenomalar oluşturur ve en sık görülen intraoral bölge palatinaldir, üst dudak ve bukkal mukoza bu sıralamayı takip eder. Bu tümör genellikle tek taraflı ve yavaş büyüme gösteren, ağrısız, katı kitle şeklindedir.

    Olgu: 56 yaşındaki bayan hasta bukkal bölgede büyüklüğü yavaşça artan ağrısız bir kitle ile Gazi Üniversitesi Diş Hekimliği Fakültesi Ağız, Diş, Çene Hastalıkları ve Cerrahisi Anabilim dalına başvurmuştur. Yapılan klinik ve radyolojik muayenede sağ bukkal b

  11. Functional definition of BirA suggests a biotin utilization pathway in the zoonotic pathogen Streptococcus suis.

    Science.gov (United States)

    Ye, Huiyan; Cai, Mingzhu; Zhang, Huimin; Li, Zhencui; Wen, Ronghui; Feng, Youjun

    2016-01-01

    Biotin protein ligase is universal in three domains of life. The paradigm version of BPL is the Escherichia coli BirA that is also a repressor for the biotin biosynthesis pathway. Streptococcus suis, a leading bacterial agent for swine diseases, seems to be an increasingly-important opportunistic human pathogen. Unlike the scenario in E. coli, S. suis lacks the de novo biotin biosynthesis pathway. In contrast, it retains a bioY, a biotin transporter-encoding gene, indicating an alternative survival strategy for S. suis to scavenge biotin from its inhabiting niche. Here we report functional definition of S. suis birA homologue. The in vivo functions of the birA paralogue with only 23.6% identity to the counterpart of E. coli, was judged by its ability to complement the conditional lethal mutants of E. coli birA. The recombinant BirA protein of S. suis was overexpressed in E. coli, purified to homogeneity and verified with MS. Both cellulose TLC and MALDI-TOFF-MS assays demonstrated that the S. suis BirA protein catalyzed the biotinylation reaction of its acceptor biotin carboxyl carrier protein. EMSA assays confirmed binding of the bioY gene to the S. suis BirA. The data defined the first example of the bifunctional BirA ligase/repressor in Streptococcus. PMID:27217336

  12. Bir Cumhuriyet kurumu olarak TRT ve tarih belgeselciliği (1978-2008)

    OpenAIRE

    ERBAŞ, Mehmet Akif

    2011-01-01

    asın, ana işlevleri itibariyle sadece haber veren, az çok eğiten, eğlendiren, kamuoyunun oluşmasını sağlayan bir kurum değil; aynı zamanda tarihe mal olan hadiselerin incelenip aydınlatılmasında kaynaklık oluşturabilecek ana unsurlardan biridir. Hatta bunun yanında, bir kısmının, oluştukları dönem itibariyle vuku bulan bir takım hadiselerin doğrudan kışkırtıcısı veya yönlendiricisi bile olabildikleri rahatlıkla ifade edilebilir. Keza, ülkenin ...

  13. 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

    X-linked Inhibitor of Apoptosis (XIAP) is an essential ubiquitin ligase for pro-inflammatory signalling downstream of the nucleotide-binding oligomerization domain containing (NOD)-1 and -2 pattern recognition receptors. Mutations in XIAP cause X-linked lymphoproliferative syndrome type-2 (XLP2......), an immunodeficiency associated with a potentially fatal deregulation of the immune system, whose aetiology is not well understood. Here, we identify the XIAP baculovirus IAP repeat (BIR)2 domain as a hotspot for missense mutations in XLP2. We demonstrate that XLP2-BIR2 mutations severely impair NOD1/2-dependent...... immune signalling in primary cells from XLP2 patients and in reconstituted XIAP-deficient cell lines. XLP2-BIR2 mutations abolish the XIAP-RIPK2 interaction resulting in impaired ubiquitylation of RIPK2 and recruitment of linear ubiquitin chain assembly complex (LUBAC) to the NOD2-complex. We show...

  14. Alvin Ward Gouldner'ın eleştirel sosyolojisi üzerine bir inceleme

    OpenAIRE

    Binay, Berivan

    2008-01-01

    İlk dönem çalışmalarını sanayi sosyolojisi alanında yapan Gouldner, 1960'lardan sonra sosyal teorilerin teorisine yönelerek Platon'dan Weber'e, Parsons'tan Marx'a kadar birçok sosyal teorisyenin eleştirel yeniden okumasını gerçekleştirmiştir. Bu anlamda Gouldner'ın eleştirel sosyolojisini temelde sosyal teorilerin teorisi karakterize eder. Ancak Gouldner'ın sosyal teorilerin teorisine yönelmesi esas itibariyle `sosyolojinin sosyolojisi'ne bağlılığının bir parçasıdır. Gouldner tek bir `sosyolo...

  15. An immobilized biotin ligase: surface display of Escherichia coli BirA on Saccharomyces cerevisiae.

    Science.gov (United States)

    Parthasarathy, Ranganath; Bajaj, Jitin; Boder, Eric T

    2005-01-01

    The Escherichia coli biotin ligase enzyme BirA has been extensively used in recent years to generate site-specifically biotinylated proteins via a biotin acceptor peptide tag. In the present study, BirA was displayed for the first time on the yeast Saccharomyces cerevisiae using the Aga1p-Aga2p platform and assayed using a peptide-tagged protein as the substrate. The enzyme is fully functional and resembles the soluble form in many of its properties, but the yeast-displayed enzyme demonstrates stability and reusability on the time scale of weeks. Thus, the yeast-displayed BirA system represents a facile and highly economical alternative for producing site-specifically biotinylated proteins.

  16. 重组BirA酶的原核表达及其活性鉴定%Expression of Recombinant BirA in Prokaryotic System and Identification of Its Activity

    Institute of Scientific and Technical Information of China (English)

    赵爽佳; 鲍如梦; 唐海科; 杨洪鸣; 唐金宝

    2015-01-01

    构建含有rTEV酶切位点的原核表达载体pUC18-His-BirA,利用E coli DH5α表达重组BirA酶,并通过酶切获得不含His标签肽的BirA酶.PCR方式扩增BirA基因片段重组至质粒pUC18,构建原核表达载体pUC18-His-BirA并转化E coli DH5α;采用冻融法释放菌体蛋白,SDS-PAGE分析目的蛋白的存在形式;冻融上清经金属离子亲和色谱纯化获得目的蛋白His-BirA酶,利用rTEV酶切除His标签肽,并采用HABA方法进行BirA酶活鉴定分析.经双酶切验证、基因测序结果表明重组载体构建正确,SDS-PAGE结果显示表达产物可溶部分比例约占50%;利用rTEV酶将标签切除,经HABA测定该酶相对酶活性可达4 365 U/μg.该研究通过构建pUC18-His-BirA质粒表达载体,实现了重组BirA酶较高比例的可溶性表达.表达产物经rTEV酶酶切后具有较高的酶活性,为实现BirA酶的经济、高效制备奠定了一定的实验基础.

  17. 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

  18. 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

  19. 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

  20. Bilişsel psikolojinin bir konusu olarak müzik algısı

    OpenAIRE

    Aslan, Aslı

    2007-01-01

    Müzik insanda zihinsel bir aktivite gerektirdiği için psikolojik araştırmaların bir konusu olarak uzun ve ayrıcalıklı bir tarihe sahiptir. Karmaşık bir insan aktivitesi olarak müzik algısı doğal olarak özellikle bilişsel psikoloji için bir ilgi alanı olmuştur. Bilişsel çalışmalar gösteriyor ki bir dinleyicide oluşan belli bir müzik parçasından edindiği deneyim duyusal mekanizmalar tarafından kaydedilen sesler tarafından yürütülür ve aynı zamanda o sesler tarafından da sınırlandırılır fakat ay...

  1. N Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The last of Hanfordqaodmasdkwaspemas7ajkqlsmdqpakldnzsdflss nine plutonium production reactors to be built was the N Reactor.This reactor was called a dual purpose...

  2. Otopsi ile tanısı konan bir psödo trizomi 13 olgusu

    OpenAIRE

    Kara, Mustafa; KIYAK ÇAĞLAYAN, Emel

    2012-01-01

    ÖZET Yaklaşık 10000 doğumda bir görülen Trizomi 13 (Patau Sendromu) spontan abortusların en sık nedenlerinden biridir. Doğum sonrasında otopsi ile Trizomi 13 tanısı konan bir olguyu sunmayı amaçladık. 36 yaşında, gravida 7, parite 6, yaşayan 5 olan hasta kliniğimizde normal spontan vaginal yol ile doğum yaptı. Ölü doğan yenidoğanın mak¬roskopik bulguları ve otopsisine göre tanı kondu. Hastalık 13. kromozomun ayrılmaması (nondisjunction) sonucu meydana gelir ve etkilenen bebeklerde yüz anom...

  3. Comparative study of factors controlling the groundwater occurrence in Bir Kiseiba and Bir El Shab areas, south western desert, Egypt using hydrogeological and geophysical techniques

    Science.gov (United States)

    Abu Risha, U. A.; Al Temamy, A. M. M.

    2016-05-01

    This research presents a clear example of the significant role of basement relief on the formation of aquifers and the impact of geologic structures on groundwater occurrence. A basement relief map was constructed using the depth to basement data acquired from 20 vertical electrical soundings (VESes), 3 land magnetic profiles, and 27 drilled wells tapping the basement rocks in addition to the elevations of the basement outcrops in the area of study. The map shows three basins underlying the area. The geoelectric survey shows that these basins were formed as a result of series of step faults. The largest basin underlies El-Shab area. The medium basin underlies the area of Bir Kiseiba whereas the smallest one underlies Bir Abu El-Hussein area. The Nubian Sandstone aquifer occurs only in El-Shab basin whereas the other basins are filled completely with the confining layer of Kiseiba Formation. The depth to basement in El-Shab basin ranges from 11 m. (ves-20) to 197 m. (ves-1) m.b.g.s. The depth to basement in Kiseiba basin ranges from 20 m. (Bir Kurayim magnetic profile) to 122 m. (ves-13) m.b.g.s. The depth to basement in Abu El-Husein basin ranges from 0 (basement outcrops) to 64 m. (Abu El-Husein magnetic profile) m.b.g.s. The aquifer thickness ranges from 0 m (where the aquitard rests directly on the basement) to 153 m. (El Shab well No. 79). The aquifer is uncoformably overlain by Kiseiba Formation which represents the aquitard layer at Bir El-Shab. The thickness of the aquitard ranges from 0 (in areas covered by the Nubian Sandstone) to 120 m (ves-13). Each of the aquifer and aquitard consist of three layers. Two of the aquitard layers are water-bearing. However, the estimated transmissivity of the aquitard is very low (11.9 m2/d). The groundwater moves vertically into the overlying aquitard at Bir El-Shab and subsequently flows in concentric pattern into the surrounding areas. Faulting controls groundwater occurrence and quality. Some springs lie on the

  4. 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.

  5. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    2013-01-01

    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

  6. 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

  7. Bir Kurumsal Kaynak Planlama Modülü Olarak İnsan Kaynakları Bilgi Sisteminin İky ve İşletme Performansı Üzerindeki Etkisi: Bir Uygulama

    OpenAIRE

    MENTEŞE, ASUMAN

    2012-01-01

    Kurumsal kaynak planlaması sistemleri 1990’lardan bu yana işletmelerin rekabete bağlı olarak farklı amaçlarla tercih ettikleri bilgi teknolojileri ürünleridir. Bütünleşik bilgi sistemleri olarak kurumsal kaynak planlaması sistemleri işletmelerin tüm departman ve fonksiyonları tek bir sistem içerinde birleştirilir. İnsan kaynakları bilgi sistemleri de kurumsal kaynak planlaması sistemlerinin bir alt modülüdür. İnsan kaynakları bilgi sistemlerinin insan kaynakları fonksiyonlarının etkin bir şek...

  8. Bir henoch-schönlein purpurası komplikasyonu : stoma

    OpenAIRE

    Yıldız, Tülin

    2011-01-01

    Henoch Schönlein Purpurası (HSP) deri, böbrek, eklem ve gastrointestinal sistemi etkileyen ve immun kompleks aracılıgı ile olusan bir lökositoklastik veya hipersensitivite vaskülitidir. Esas olarak çocukluk çagı hastalıgıdır. Prognoz genellikle iyidir; ancak siddetli gastrointestinal ve renal bulguları olan hastaların dikkatle tedavi edilmesi ve izlenmesi gerekir. Bazı durumlar ise, hastalık sonucu stoma açılmasını gerektirebilir. Olgumuz, HSP tanısı ile servise kabul edildikten k...

  9. Butterfly Species Diversity of Bir-Billing Area of Dhauladhar Range of Western Himalayas in Northern India

    Directory of Open Access Journals (Sweden)

    Sangeeta Chandel

    2013-10-01

    Full Text Available The present study of butterfly species diversity was carried out in the Bir-Biling area of Dhauladhar Range of the Western Himalayas in Northern India. The study was done since April 2012 to March 2013, throughout the year during the routine field visits to Bir-Billing. A total of 50 butterfly species were recorded from the study areas which belonge to five families i.e. Nymphalidae, Pieridae, Papilionidae, Lycaenidae and Hesperiidae and 39 genera. The Nymphalidae family was the most dominant family in the study area having 32 species and followed by Lycaenidae family with 7 species.

  10. Research reactors

    International Nuclear Information System (INIS)

    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)

  11. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    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

  12. KOBİ'lerin finansal risk algı düzeyine yönelik bir araştırma : Isparta ve Burdur illerine yönelik bir anket çalışması

    OpenAIRE

    Önem, Hüseyin Başar

    2010-01-01

    Bütün ekonomilerin vazgeçilmez temel bir bileşeni olan KOBİ 'ler, istihdam ettikleri işgücünden, gerçekleştirdikleri yatırımlara, yarattıkları katma değere ve ödedikleri vergilere kadar pek çok yönleri ile her ekonomide önemli bir yere sahiptir. Risk; iş hayatının ayrılmaz bir parçasıdır. KOBİ' lerin en yüksek karlılığa ulaşabilmeleri, faaliyet göstermiş oldukları tüm iş kollarında karşı karşıya kalınan risklerin doğru bir şekilde yönetilmesi ile mümkün olacaktır. KOBİ' lerin karşılaştıkları ...

  13. Ansip lõi läbirääkimistelaua tühjaks / Kadri Jakobson

    Index Scriptorium Estoniae

    Jakobson, Kadri, 1970-

    2007-01-01

    Koalitsiooniläbirääkimised katkestas tüli ministri kohtade jagamise pärast, mis võib anda võimaluse Keskerakonnale. Vt. samas intervjuud Keskerakonna juhatuse liikme Ain Seppikuga. Kommenteerivad: Urmas Sõõrumaa, Jüri Mõis, Rainer Nõlvak ja Olari Taal. Lisa: Kes mida tahtis? Mida pakuti?

  14. Tıbbi Tahminde Alternatif Bir Yaklaşım: Destek Vektör Makineleri

    OpenAIRE

    Özge YILMAZ AKŞEHİRLİ; Ankarali, Handan; Duygu AYDIN; Özge SARAÇLI

    2013-01-01

    Amaç: Bu çalışma, birçok alanda sıklıkla kullanılan destek vektör makinelerinin (DVM) tıbbi araştırmalarda kullanımına yönelik bir uygulama olarak düşünülmüş ve tıbbi bir çalışma verisi kullanılarak DVM yönteminin veriyi doğru sınıflama başarısını ortaya koymak amaçlanmıştır. Gereç ve Yöntemler: Çalışmamızda, verileri sınıflandırmak veya tahmin yapmak amacıyla kullanılan, eğiticili (supervised) bir makine öğrenmesi yöntemi olan DVM kullanılmıştır. Burada, doğrusal olmayan ilişkiler için iki s...

  15. 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

  16. Reactor building

    International Nuclear Information System (INIS)

    The whole reactor building is accommodated in a shaft and is sealed level with the earth's surface by a building ceiling, which provides protection against penetration due to external effects. The building ceiling is supported on walls of the reactor building, which line the shaft and transfer the vertical components of forces to the foundations. The thickness of the walls is designed to withstand horizontal pressure waves in the floor. The building ceiling has an opening above the reactor, which must be closed by cover plates. Operating equipment for the reactor can be situated above the building ceiling. (orig./HP)

  17. ULUSLARIN REKABET ÜSTÜNLÜĞÜ VE ELMAS MODELI ÜZERINE BIR DEĞERLENDIRME

    Directory of Open Access Journals (Sweden)

    Murat KOC

    2014-07-01

    Full Text Available Günümüzde, rekabet kavramı daha çok firma düzeyinde bir kavram olmakla beraber, artık ulusal düzeyde de ele alınmaya başlanmıştır. Rekabet şartlarının değişken bir yapı içerisinde olması ve yaşanan küreselleşme, bir ulusun rekabet üstünlüğünün analiz edilebilmesi açısından yeni yöntemlerin uygulanması gerekliliğini ortaya koymuştur. Bu kapsamda Michael E. Porter, kapsamlı bir araştırma niteliği taşımakta olan, Elmas Modeli (Diamond Model’ni ortaya koymuştur. “Bazı ulusların neden diğerlerine göre belirli sektörlerde daha rekabetçi olduğu” sorusuna yanıt vermeye çalışılan model, belirli bir sektörde ulusal rekabet gücünü belirleyen bazı unsurların birbirleriyle ilişkili olarak incelenmesini öngörmektedir. Bu çalışmanın amacı, ulusların rekabet üstünlüğü sağlamasında Porter’ın literatüre kazandırdığı “Elmas Modeli” yaklaşımının değerlendirilmesi ve modele yönelik eleştirilerin ortaya konulmasıdır.

  18. Evaluation of fine needle aspiration cytology of cervical lymphadenopathy in Bir Hospital

    Directory of Open Access Journals (Sweden)

    Subash Khadka

    2015-09-01

    Full Text Available Background & Objectives: To correlate FNAC of cervical lymphadenopathy with the histopathology.Materials and Methods: Prospective study on 67 patients with cervical lymphadenopathy at the ENT Department, Bir Hospital, from January 2013 to July 2014. Patients were subjected to both FNAC and histopathology.Results: Thirty cases (44.8% were females and 37 cases (55.2% were males. Tuberculosis was most common disease in 30(44.80% patients. Sensitivity, specificity, and diagnostic accuracy of FNAC to diagnose tubercular lymphadenopathies were 83.0%, 100.0%, and 92.54% respectively. Overall correlation of FNAC to histopathology was 86.57%.Conclusion: FNAC is very simple and accurate technique for diagnosis of cervical lymphadenopathy.JCMS Nepal. 2015;11(1: 22-25

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

    OpenAIRE

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

    2002-01-01

    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...

  20. Yıldırma (Mobbing): Kuramsal Bir Çerçeve

    OpenAIRE

    Güneş Ertuna , Derya; Ertuna, Erdem

    2015-01-01

    Mobbing; işletmelerde çalışanların çalışma arkadaşları, yöneticileri ve/veya astları tarafından rahatsız ve huzursuz edilmesi, fiziksel ve/veya psikolojik şiddete maruz bırakılması olarak değerlendirilebilmektedir. Bu yönüyle mobbingin ana amacı, mobbing mağduru konumundaki kişinin yıldırılması ve bir anlamda yenik düşmesinin sağlanması olarak ifade edilmektedir. “İsveç Ulusal İş Güvenliği ve Hijyeni Dairesi (Swedish National Board of Occupational Safety and Health)” tarafından mobbing kavram...

  1. 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›,...

  2. Kyzikos’lu bir kadın Euergetes : Kraliçe Apollonis

    OpenAIRE

    ÜRETEN, Hüseyin

    2004-01-01

    Klasik dönemlerden Hellenistik döneme kadar, kadın adaklarının sayıca artışı Grek polisinin değişen durumu ve artan zenginliği ile açıklanabilmiştir. Bu gelişimin en belirgin işareti Klasik dönemin leitourgia sisteminden doğan ve halk yönetimi açısından yeni bir nitelik ve önemkazanan zengin sınıfın euergetizm' i olmuştur. Aynı zamanda Hellenistik dönemin kraliçeleri hayırsever ve kurucu gibi sıfatlarla hareket ederek diğer kadınlara da örnek olmuşlardır....

  3. Liderlikte post-modern bir paradigma: dönüşümcü liderlik

    Directory of Open Access Journals (Sweden)

    Levent Eraslan

    2006-12-01

    Full Text Available Heraklitos’un “Her şey akıştadır ve hiçbir şey duruşta değildir.” deyişi  ile insanlığın değişimi anlama, algılama ve ona uyum sağlama sürecinin başladığı kabul edilir. Değişim denen bu karmaşık  olgu, günümüzde bütün sosyal sistemlerin yaşama ilişkin kültürlerini ve yönetim biçimlerini hızlı bilgi artışı, hızlı gelişme ve hızlı iletişim ile birlikte derinden etkilemektedir. Bu değişim sürecinin  yükümlülüğü oluşturmak ve bunu başarmak için “liderlik” olgusu önemli bir rol oynamaktadır. Dönüşümü sağlamada geleneksel liderlik anlayışının yeterli olmadığının bilinmesi de, değişimin etkisinin yoğun olarak hissedildiği günümüzde, değişim temelli bir liderlik anlayışının yapılandırılması gerekliliğini ortaya çıkarmıştır. Bu  liderlik anlayışının da "Dönüşümcü Liderlik" olduğu ileri sürülmektedir. Aralıksız devam eden değişim sürecinde, dönüşümcü liderliğin tüm sektörlerde önemi gittikçe artmaktadır. Dönüşümcü liderler, vizyon yaratarak ve bu vizyonu paylaşarak izleyenleri ile sürekli iletişim kuran, güvenilir, saygı duyulan sosyal mimarlardır. Yeni zorlukların yaşanacağı  yeni çağda; "dönüşümcü liderlik"  bu zorlukların aşılmasında en iyi çözüm yolu olarak kabul edilmektedir. Tarihsel sürece baktığımızda ise Dönüşümcü liderliğe verilecek en büyük örneğin Türkiye Cumhuriyetinin Kurucusu M.Kemal Atatürk olduğunu görmekteyiz. Büyük Lider Atatürk dönüşümcü liderliğin  bütün karakteristik özelliklerini taşımaktadır. Yıkılmış bir imparatorluktan, her şeyi ile yeni bir devlet kurarak, yönetsel,sosyal,ekonomik ve kültürel yaşamda köklü bir dönüşüm süreci gerçekleştirmiştir. Atatürk’te Dönüşümcü liderliğin başat özelliklerinden;  Ortak Vizyon Oluşturma ve Paylaşma, Zihinsel Uyarım ve Yaratıcı olma, Karizmatik Etkiye Sahip

  4. Çok merkezli kapalı bir eğri: Cassini Ovali, özellikleri ve uygulamaları

    OpenAIRE

    KARATAŞ, Mümtaz

    2013-01-01

    Cassini ovali, düzlem üzerindeki sabit iki noktaya olan mesafelerinin çarpımı yine bir sabit olan noktalar kümesinin oluşturduğu kuadratik bir eğri olarak tanımlanabilir. Benzersiz özellikleri ve geometrik profili, bu ovalleri pek çok askeri ve ticari alanda kullanılmasına imkan tanıyan üstün bir araç haline getirmiş, ayrıca analitik geometriye ve genel elips konseptinin ötesindeki matematik teorisiyle ilişkili diğer konulara yeni bir boyut kazandırmıştır. Bu çalışma kapsamında, Cassini ovall...

  5. Üslûpbilime Kültürel Bir Yaklaşıma Doğru

    Directory of Open Access Journals (Sweden)

    Adem Çalışkan

    2014-10-01

    Full Text Available Bu tebliğ, burada edebî-dilbilim incelemesinde en ileri nokta olarak ele alınan üslûpbilime farklı yaklaşımları tartışıyor ve bağlamsallaştırılmış bir üslûpbilimin edebiyat öğretimine olası yararlarını sunuyor. Üslûpbilimin çok can sıkıcı ve kaypak bir kavram olduğu varsayımından başlayarak, tümellerden ve mikro-dilbilimsel gözlemlerden bağlam çalışması ve onun insanın davranış, konuşma ve iletişim davranış tarzındaki etkisine nasıl taşındığını belirtiyor. Bu tebliğin temel amacı, üslûpbilimin çok rahat bir biçimde dil ve edebiyat arasına yerleştirilebileceğini, kültürel uygulama olarak metnin anlaşılmasına katkısını ve böylece kültürel, edebî ve dilbilimsel araştırmalar arasında bir köprü olarak çalışabileceğini tartışmaktır. Bu argümanı desteklemek için, üslûpbilimin görüldüğü farklı ışıklardan bazısı tartışılıyor. Tebliğ, bağlamsallaştırılmış bir pedagojik üslûpbilimi tanımlamaya yardım eden bir teorik model teklif ederek sona eriyor.

  6. Compact Reactor

    International Nuclear Information System (INIS)

    Weyl's Gauge Principle of 1929 has been used to establish Weyl's Quantum Principle (WQP) that requires that the Weyl scale factor should be unity. It has been shown that the WQP requires the following: quantum mechanics must be used to determine system states; the electrostatic potential must be non-singular and quantified; interactions between particles with different electric charges (i.e. electron and proton) do not obey Newton's Third Law at sub-nuclear separations, and nuclear particles may be much different than expected using the standard model. The above WQP requirements lead to a potential fusion reactor wherein deuterium nuclei are preferentially fused into helium nuclei. Because the deuterium nuclei are preferentially fused into helium nuclei at temperatures and energies lower than specified by the standard model there is no harmful radiation as a byproduct of this fusion process. Therefore, a reactor using this reaction does not need any shielding to contain such radiation. The energy released from each reaction and the absence of shielding makes the deuterium-plus-deuterium-to-helium (DDH) reactor very compact when compared to other reactors, both fission and fusion types. Moreover, the potential energy output per reactor weight and the absence of harmful radiation makes the DDH reactor an ideal candidate for space power. The logic is summarized by which the WQP requires the above conditions that make the prediction of DDH possible. The details of the DDH reaction will be presented along with the specifics of why the DDH reactor may be made to cause two deuterium nuclei to preferentially fuse to a helium nucleus. The presentation will also indicate the calculations needed to predict the reactor temperature as a function of fuel loading, reactor size, and desired output and will include the progress achieved to date

  7. 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.

  8. NUCLEAR REACTOR

    Science.gov (United States)

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

    1958-01-21

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

  9. 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)

  10. NUCLEAR REACTOR

    Science.gov (United States)

    Anderson, C.R.

    1962-07-24

    A fluidized bed nuclear reactor and a method of operating such a reactor are described. In the design means are provided for flowing a liquid moderator upwardly through the center of a bed of pellets of a nentron-fissionable material at such a rate as to obtain particulate fluidization while constraining the lower pontion of the bed into a conical shape. A smooth circulation of particles rising in the center and falling at the outside of the bed is thereby established. (AEC)

  11. Nuclear reactor

    International Nuclear Information System (INIS)

    In order to reduce neutron embrittlement of the pressue vessel of an LWR, blanked off elements are fitted at the edge of the reactor core, with the same dimensions as the fuel elements. They are parallel to each other, and to the edge of the reactor taking the place of fuel rods, and are plates of neutron-absorbing material (stainless steel, boron steel, borated Al). (HP)

  12. Çok Boyutlu Performans Değerleme Modelleri ve Bir Balanced Scorecard Uygulaması

    OpenAIRE

    Tunçer, Ender

    2006-01-01

    Günümüzde karmaşık ortamlarda rekabet eden işletmelerin başarılı olmalarında etkin bir performans değerleme sisteminin önemi büyüktür. Başarıyla uygulanan bir performans değerleme sistemi, firma başarısının sürekli izlenmesini sağlamaktadır. İşletmenin başarısını tüm yönleriyle değerlendirmeyi amaçlayan performans değerleme sistemlerinin finansal boyutla birlikte finansal olmayan boyutu da dikkate almaları gerekmektedir. Bugüne kadar kullanılan finansal göstergelere dayalı performans değerlem...

  13. Hepatit A'ya Bağlı Guillain-Barre Sendromu: Nadir Bir Birliktelik

    OpenAIRE

    Canpolat, Mehmet; Ceylan, Özgür; Çelik, İlknur; Bayram, Ayşe Kaçar; Per, Hüseyin; Doğanay, Selim; Gümüş, Hakan; ASLAN, Duran; Kumandaş, Sefer

    2015-01-01

    Guillain Barre Sendromu (GBS), çocukluktan ileri yaşlara kadar her yaş grubunda rastlanabilen, akut başlangıçlı, simetrik ve jeneralize kas güçsüzlüğü, arefleksi ve periferik sinirlerin inflamatuvar demyelinizasyonu ile karakterize bir hastalıktır. GBS 'un patogenezi net olarak bilinmemekle birlikte otoimmun bir hastalık olduğu düşünülmektedir. Guillian-Barre Sendromu(GBS) ile enfeksiyon hastalıkları arasındaki ilişki iyi bilinmektedir. Hepatit A enfeksiyonu sırasında GBS gelişimi nadir görül...

  14. 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

  15. Selbstreinigung urbaner Flusslandschaften bei Basel : Inwertsetzung revitalisierter und naturnaher Auen- und Feuchtgebiete in den Flussebenen von Wiese, Birs und Rhein

    OpenAIRE

    Geissbühler, Urs

    2007-01-01

    Capacity of self-purification processes of urban river areas near Basel (CH). Improvement of rehabilitated and natural-like wetlands in the ancient river basins of the river Wiese, Birs and Rhine. Introduction and objectives: Urban areas are characterized by an enormous human use density. Passing rivers and their landscapes were subjected and adapted to the human activities. Straightened and obstructed running waters have today become self-evident nationwide. Since the end...

  16. Prevalence of parasitic infection in captive wild animals in Bir Moti Bagh mini zoo (Deer Park), Patiala, Punjab

    OpenAIRE

    A. Q. Mir; Dua, K; Singla, L. D.; Sharma, S.; Singh, M.P.

    2016-01-01

    Aim: The study was conducted to know the prevalence of gastrointestinal parasites of captive wild animals at Bir Moti Bagh Mini Zoo (Deer Park), Patiala, Punjab. Materials and Methods: A total of 31 fecal samples from eight species of captive animals including Civet cat (Viverra zibetha), Porcupine (Hystrix indica), Nilgai (Boselaphus tragocamelus), Spotted deer (Axis axis), Black buck (Antelope cervicapra), Sambar deer (Cervus unicolor), Hog deer (Axis porcinus), and Barking deer (Muntiac...

  17. Theoretical studies on the interactions of XIAP-BIR3 domain with bicyclic and tricyclic core monovalent Smac mimetics.

    Science.gov (United States)

    Ling, Baoping; Dong, Lihua; Zhang, Rui; Wang, Zhiguo; Liu, Yongjun; Liu, Chengbu

    2010-11-01

    X-linked IAP can bind caspase-9 and inhibit its activity. Mitochondrial protein Smac/DIABLO can also interact with XIAP and relieve the inhibition on caspase-9 to induce apoptosis. A series of artificial Smac mimetics have been used to mimic the Smac N-terminal tetrapeptide AVPI to bind to XIAP-BIR3, but these structural diverse mimetics exhibited distinct binding affinities. To get an insight into the binding nature and optimize the structures, molecular docking and dynamics simulations were used to study the binding of XIAP-BIR3 with three groups of Smac mimetics. The docking results reveal that these Smac mimetics anchored on the surface groove of XIAP-BIR3 and superimposed well with AVPI. The modifications on the seven-membered ring of bicyclic core segment do not strengthen the binding affinity, while a benzyl introduced to the five-membered ring is favorable to the binding. Molecular dynamics simulations on three typical systems show that these complexes are very stable. Hydrogen bonds between the bicyclic core segment and Thr308 play critical roles in maintaining the stability of complex. The binding free energies calculated by MM_PBSA method are consistent with the experimental results. PMID:20980180

  18. 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

  19. Müzakere yönetimi ve bir model denemesi

    OpenAIRE

    UÇAN, Murat Yusuf

    2008-01-01

    Bu çalışma öncelikle iki konunun teorik boyutunun incelenmesini amaçlamıştır. Birincisi, kişisel ve kurumsal ilişkilerde tarafların, kaynakları optimum kullanarak, amaçlarına ulaşmasında temel müzakere ilke ve boyutlarının anlaşılmasını, ayrıntılı ön hazırlık ve sistematik planlamanın yapılmasını, uygun strateji ve taktiklerin seçilerek uygulanmasını içeren müzakere yönetim sürecinin incelenmesi; ikincisi 21. yüzyılda küreselleşmenin hızlı bir şekilde arttığı değişimler ve karmaşıklaşan müzak...

  20. Sonochemical Reactors.

    Science.gov (United States)

    Gogate, Parag R; Patil, Pankaj N

    2016-10-01

    Sonochemical reactors are based on the generation of cavitational events using ultrasound and offer immense potential for the intensification of physical and chemical processing applications. The present work presents a critical analysis of the underlying mechanisms for intensification, available reactor configurations and overview of the different applications exploited successfully, though mostly at laboratory scales. Guidelines have also been presented for optimum selection of the important operating parameters (frequency and intensity of irradiation, temperature and liquid physicochemical properties) as well as the geometric parameters (type of reactor configuration and the number/position of the transducers) so as to maximize the process intensification benefits. The key areas for future work so as to transform the successful technique at laboratory/pilot scale into commercial technology have also been discussed. Overall, it has been established that there is immense potential for sonochemical reactors for process intensification leading to greener processing and economic benefits. Combined efforts from a wide range of disciplines such as material science, physics, chemistry and chemical engineers are required to harness the benefits at commercial scale operation.

  1. Etnik Gruplar Arası Sorunların Yeniden İfadesine Yönelik Bir Girişim

    OpenAIRE

    Çev. Tuncel Öncel, Broghos Levon Zekiyan,

    2015-01-01

    Küreselleşme süreciyle yüz yüze gelinmesi, neden ve nasıl etnik bilinç ve mücadelelerin kalıcı oldukları sorusunu gündeme getiriyorsa, bu konuda sıklıkla dile getirilen bir başka soru da bunların kökeniyle ilgilidir. Bir süredir söz konusu olduğu üzere etnik gruplar arası çatışmaları ve hatta etnik öz- farkındalığın kalıcılığını, ekonomik etkenlerin bir fonksiyonu olarak yorumlayan epey baskın bir eğilim bulunmaktadır. Marksizm, bu argümana bilimsel bir çerçeve ve sağlamlık kazandırmakta...

  2. Random Forests Yöntemi ve Sağlık Alanında Bir Uygulama

    Directory of Open Access Journals (Sweden)

    Muhammet AKMAN

    2011-01-01

    Full Text Available Amaç: Veri madenciliği, genel olarak tanımlayıcı ve tahmin edici olmak üzere iki ana başlıkta incelenmektedir. Özellikle tıp alanında veri madenciliği daha çok tahmin edici yönüyle kullanılmaktadır. Bu çalışmada, ağaç tabanlı veri madenciliği yöntemlerinden birisi olan Random Forests (RF yönteminin incelenmesi ve sağlık alanından elde edilen bir veri seti üzerine uygulaması yapılarak sonuçlarının tartışılması amaçlanmıştır. Gereç ve Yöntemler: RF yönteminde, karar ormanını oluşturan karar ağaçları orijinal veri setinden bootstrap yöntemiyle seçilen farklı örneklerden oluşturulmaktadır. Her karar ağacında veri setindeki tüm değişkenlerden rastgele seçilen az sayıda değişken kullanılmaktadır. Her ağaç bir sınıf için oy vermektedir ve orman sınıflayıcısı bütün ağaçların verdiği oyları toplayarak bir sınıf için son tahminini yapmaktadır. Yöntemin uygulanması amacıyla Diş hekimliği alanından elde edilen bir veri seti kullanılmıştır. Bulgular: Toplam 43 tane demografik, dental ve serolojik özelliklere ait veriler kullanılarak RF yöntemi ile %95.4 oranında başarılı bir sınıflandırma yapılmıştır. Bu karar ormanının hata oranı ise %3.33 olarak bulunmuştur. Aynı veri seti için Bagging ve CART yöntemi ile de sınıflama yapılmış ve Bagging yöntemi ile hata oranı %5.4, CART yöntemi ile %8.75 olarak bulunmuştur. Sonuç: RF yöntemi ile veri setindeki değişken sayısı ve örnek sayısı ne kadar çok olursa olsun genellikle hata oranı düşük sınıflamalar yapılmaktadır. Hata oranının düşüklüğü ise bir topluluk yöntemi olmasından kaynaklanmaktadır. Özelikle çok sayıda değişkenin olduğu DNA veri seti gibi binlerce gen arasından önemli olanları tespit etmek için kullanılabilir.

  3. 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.

  4. Reactor container

    International Nuclear Information System (INIS)

    A reactor container has a suppression chamber partitioned by concrete side walls, a reactor pedestal and a diaphragm floor. A plurality of partitioning walls are disposed in circumferential direction each at an interval inside the suppression chamber, so that independent chambers in a state being divided into plurality are formed inside the suppression chamber. The partition walls are formed from the bottom portion of the suppression chamber up to the diaphragm floor to isolate pool water in a divided state. Operation platforms are formed above the suppression chamber and connected to an access port. Upon conducting maintenance, inspection or repairing, a pump is disposed in the independent chamber to transfer pool water therein to one or a plurality of other independent chambers to make it vacant. (I.N.)

  5. Incorporating the social dimension into hydrogeochemical investigations for rural development: the Bir Al-Nas approach for socio-hydrogeology

    Science.gov (United States)

    Re, Viviana

    2015-11-01

    A replicable multidisciplinary approach is presented for science-based groundwater management practices: Bir Al-Nas (Bottom-up IntegRated Approach for sustainabLe grouNdwater mAnagement in rural areaS). This approach provides a practical example of the concept of "socio-hydrogeology", a way of incorporating the social dimension into hydrogeological investigations, as reinforced by the translation of the Arabic bir al-nas: "the people's well". To achieve this, hydrogeologists act as "social hydrologists" during their monitoring activities, which often bring them into contact with local communities and end users (and polluters) of water. Not only can they retrieve reliable information about traditional know-how and local issues, but they can also change the public perception of science/scientists to create the basis for mutual collaboration and understanding in view of implementing improved integrated groundwater management. The final outcomes are expected to be an increased awareness of communities at the local level and a clear understanding of their water issues and needs from the very early stages of the investigation. Although the importance of using such methods in groundwater analysis and management is widely recognized, hydrogeological investigations are currently dominated by sectorial approaches that are easier to implement but less sustainable. The pressure of population growth, the shift towards more water-dependent economies, climate change and its impact on water availability will require scientists to use a more integrated approach, such as Bir Al-Nas, when dealing with increasing water pollution and water-scarcity issues.

  6. NEUTRONIC REACTORS

    Science.gov (United States)

    Anderson, J.B.

    1960-01-01

    A reactor is described which comprises a tank, a plurality of coaxial steel sleeves in the tank, a mass of water in the tank, and wire grids in abutting relationship within a plurality of elongated parallel channels within the steel sleeves, the wire being provided with a plurality of bends in the same plane forming adjacent parallel sections between bends, and the sections of adjacent grids being normally disposed relative to each other.

  7. Normokalsemi ile seyreden ve metastatik kemik hastalığını taklit eden bir brown tümörü olgusu

    OpenAIRE

    Meydan, Nezih; Ayhan, Mediha; Barutca, Sabri; Güney, Engin; Boylu, Şükrü

    2005-01-01

    Kemik sintigrafisi oldukça yaygın kullanılan bir tarama yöntemidir. Brown tümör ilerlemis hiperparatiroidinin oldukça nadir görülen bir bulgusudur. Primer hipertroidi, hiperkalsemi ve hipofosfatemi ile seyreden bir hastalıktır ve sintigrafik görüntülemede metastatik kemik hastalıgını taklit edebilir. Biz bu yazımızda yaygın kemik agrısı yakınması ile basvuran ve çekilen tüm vücut kemik sintigrafisinde kostalarda ve sol femur proksimalinde metastatik olarak degerlendirilen aktivite...

  8. İntiharın kısa tarihçesinden sebep ve yöntemlerine genel bir bakış

    OpenAIRE

    Bulut, Erkut Ragıp; KÜÇÜKER, Hüdaverdi; Bulut, Necati Serkut

    2012-01-01

    Özet Dünyada her yıl bir milyonun üstünde kişi, tüm ölüm sebepleri içerisinde onuncu sırada yer alan intihar nedeniyle hayatlarını kaybetmektedir. Buna ek olarak her yıl 20 milyona yakın intihar girişimi meydana gelmektedir. İntihar, insanın öz benliğine yönelmiş bir saldırganlık ve yok etme eylemi olup bireyin yaşamına istemli olarak son vermesidir. Başka bir deyişle, hayatına son vermeye karar veren kişinin en etkili yöntemi seçip, kimsenin müdahalesine izin vermeyecek şekilde kendini öldür...

  9. Nuclear research reactors

    International Nuclear Information System (INIS)

    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.)

  10. Nuclear reactor

    International Nuclear Information System (INIS)

    A nuclear reactor is described in which the core components, including fuel-rod assemblies, control-rod assemblies, fertile rod-assemblies, and removable shielding assemblies, are supported by a plurality of separate inlet modular units. These units are referred to as inlet module units to distinguish them from the modules of the upper internals of the reactor. The modular units are supported, each removable independently of the others, in liners in the supporting structure for the lower internals of the reactor. The core assemblies are removably supported in integral receptacles or sockets of the modular units. The liners, units, sockets and assemblies have inlet openings for entry of the fluid. The modular units are each removably mounted in the liners with fluid seals interposed between the opening in the liner and inlet module into which the fluid enters in the upper and lower portion of the liner. Each assembly is similarly mounted in a corresponding receptacle with fluid seals interposed between the openings where the fluid enters in the lower portion of the receptacle or fitting closely in these regions. As fluid flows along each core assembly a pressure drop is produced along the fluid so that the fluid which emerges from each core assembly is at a lower pressure than the fluid which enters the core assembly. However because of the seals interposed in the mountings of the units and assemblies the pressures above and below the units and assemblies are balanced and the units are held in the liners and the assemblies are held in the receptacles by their weights as they have a higher specific gravity than the fluid. The low-pressure spaces between each module and its liner and between each core assembly and its module is vented to the low-pressure regions of the vessel to assure that fluid which leaks through the seals does not accumulate and destroy the hydraulic balance

  11. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    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

  12. 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

  13. Tıbbi Tahminde Alternatif Bir Yaklaşım: Destek Vektör Makineleri

    Directory of Open Access Journals (Sweden)

    Özge YILMAZ AKŞEHİRLİ

    2013-01-01

    Full Text Available Amaç: Bu çalışma, birçok alanda sıklıkla kullanılan destek vektör makinelerinin (DVM tıbbi araştırmalarda kullanımına yönelik bir uygulama olarak düşünülmüş ve tıbbi bir çalışma verisi kullanılarak DVM yönteminin veriyi doğru sınıflama başarısını ortaya koymak amaçlanmıştır. Gereç ve Yöntemler: Çalışmamızda, verileri sınıflandırmak veya tahmin yapmak amacıyla kullanılan, eğiticili (supervised bir makine öğrenmesi yöntemi olan DVM kullanılmıştır. Burada, doğrusal olmayan ilişkiler için iki sınıflı DVM yönteminin bir uygulaması yapılmıştır. DVM’nin temelini, verilerin bir düzlem veya hiper düzlem ile ayrılarak sınıflandırılması işlemi oluşturmakta ve DVM bu işlemi, iki sınıf arasındaki marjini maksimum yaparak gerçekleştirmektedir. Bu şekilde veri eğitildikten sonra, DVM yeni gelen veriyi doğru sınıflamayı amaçlamaktadır. Tıpta DVM özellikle, kanser morfolojisinde, tedavi başarısının ve ilgili genin belirlenmesinde, çeşitli hastalıkların teşhisinde kullanılmaktadır. Araştırmanın uygulama bölümünde, Zonguldak Karaelmas Üniversitesi Tıp Fakültesi psikiyatri polikliniğine 1-31 Ocak 2011 tarihleri arasında gece yeme sendromu şikâyetiyle başvuran 433 hastaya ilişkin bilgiler kullanılmıştır. Bulgular: Kullanılan 17 değişken için tanımlayıcı istatistikler elde edilmiş ve univariate analizlerden elde edilen sonuçlara göre, GYA, BSQ ve SCL puanları, medeni durum, sigara kullanımı ve psikolojik tanı değişkenlerinin gece yeme sendromu tanısı koymada tek başına etkileri olduğu sonucuna varılmıştır. Doğrusal olmayan destek vektör makineleri kullanılarak elde edilen sonuçlar incelendiğinde, eğitim ve test verileri için doğruluk ve ROC eğrisi altında kalan alanlara bakılarak, modelin tanı koyma başarısının oldukça iyi derecede olduğu görülmüştür. Sonuç: DVM yöntemi, istatistiksel

  14. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T.; Sahimi, Muhammad; Fayyaz-Najafi, Babak; Harale, Aadesh; Park, Byoung-Gi; Liu, Paul K. T.

    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.

  15. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T. (Inventor); Sahimi, Muhammad (Inventor); Fayyaz-Najafi, Babak (Inventor); Harale, Aadesh (Inventor); Park, Byoung-Gi (Inventor); Liu, Paul K. T. (Inventor)

    2011-01-01

    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.

  16. 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

  17. Bir İlkokul 4. Sınıf Öğrencisinin Okuma Bozukluğu ve Anlama Güçlüğü: Bir Durum Çalışması

    Directory of Open Access Journals (Sweden)

    Nergiz KARDAŞ İŞLER

    2016-03-01

    Full Text Available Bu araştırmanın amacı, okuma güçlüğü çeken bir ilkokul dördüncü sınıf öğrencisinin okuma alanındaki sorunlarının ortaya konulması ve bu sorunların giderilmesine yönelik uygulamalar gerçekleştirilmesidir. Bu amaç doğrultusunda öğrencinin okuma alanındaki sorunlarını çözmeye yönelik “Paragrafın önceden dinlenmesi stratejisi” ve “Eşli okuma stratejisi” kullanılmıştır. Nitel araştırma yaklaşımının kullanıldığı bu araştırma, 2013–2014 eğitim öğretim yılının toplam 13 saatlik sürecini kapsamaktadır. Araştırma, bütüncül tek durum desenli bir durum araştırmasında nitel bir araştırmadır. Gözlemler ve doküman incelemesi veri toplama araçları olarak kullanılmaktadır. Uygulama öncesinde, öğrencinin tekrar ederek, heceleyerek, heceleri ve sözcükleri atlayarak okuduğu, okurken eklemeler yaptığı, yanlış okuduğu ve noktalama işaretlerine dikkat etmeden okuduğu tespit edilmiştir. Elde edilen bu veriler doğrultusunda Türkçe ders ve hikâye kitaplarından öğrencinin düzeyine uygun metinler seçilmiştir. Tüm bu çalışmalar ses kaydına alınmıştır. Bu çalışmalar sonucunda okuma ve okuduğunu anlama sorunlarında kullanılan stratejilerle öğrencinin problemleri azalmıştır.

  18. Reactor container

    International Nuclear Information System (INIS)

    Purpose: To prevent shocks exerted on a vent head due to pool-swell caused within a pressure suppression chamber (disposed in a torus configuration around the dry well) upon loss of coolant accident in BWR type reactors. Constitution: The following relationship is established between the volume V (m3) of a dry well and the ruptured opening area A (m2) at the boundary expected upon loss of coolant accident: V >= 30340 (m) x A Then, the volume of the dry well is made larger than the ruptured open area, that is, the steam flow rate of leaking coolants upon loss of coolant accident to decrease the pressure rise in the dry well at the initial state where loss of coolant accident is resulted. Accordingly, the pressure of non-compressive gases jetted out from the lower end of the downcomer to the pool water is decreased to suppress the pool-swell. (Ikeda, J.)

  19. Yağ dokusu İçeren Nadir Bir Stafne Kemik Kavitesi Olgusu

    Directory of Open Access Journals (Sweden)

    Erman Şenel

    2012-07-01

    nerilmektedir. Manyetik rezonans görüntüleme (MR, bu kavitelerin içeriği hakkında cerrahlara ayrıntılı bilgi vermektedir. Bu makalede, yağlı içeriğe sahip nadir bir Stafne Kemik Kavitesi olgusu sunulmaktadır. Ayırıcı tanısı, DBT ve MR ile gerçekleştirilmiştir.

  20. 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.

  1. Bir Tekstil Sanayi Sevkiyat Bölümünde R’WOT Analizi Uygulaması

    OpenAIRE

    Gürbüz, Feyza; Öztürk, Emrah

    2013-01-01

    Kurumsal yapının bir takım kriterlere tabi tutularak incelenmesi teknikleri, modern iş yönetiminin elinden düşmeyen araçlardır. Bu sayede o kurumun şu anki durumu, doğru işleyip işlemediği kolaylıkla belirlenmiş olur. Bu tekniklerden biri olan "SWOT Analizi", firmanızın kurumsal işlerliği, rekabet gücü, sektördeki konumu, piyasadaki dış tehditlerin varlığı vs. gibi iç ve dış değerlendirmelerin yapılabildiği en etkili değerlendirme yöntemlerinden biridir. Ancak swot analizi ...

  2. Šiaulių darbo biržos profesinio mokymo paslaugų kokybės vertinimas

    OpenAIRE

    Bielianaitė, Asta

    2009-01-01

    Magistro darbe yra analizuojamos Šiaulių darbo biržos organizuojamų profesinio mokymo kursų švietimo paslaugos, išanalizuota ir susisteminta informacija apie švietimo įstaigos administracijos darbą, dėstytojus, paskaitų dėstymo metodus, mokymo įstaigos tinkamumą paskaitoms, pažymių rašymo ir vertinimo politiką, namų darbų užduočių atlikimą, konsultavimą, bei kursų pasekmes. Tyrimui atlikti buvo pasirinktas T.R. Guskey ir D. Sparkso profesinio mokymosi ir tobulinimosi, bei mokinių mokymosi paž...

  3. Mikrodenetleyicili Asansör Denetiminde Seri Haberleşme Kullanan Bir Modelin Gerçekleştirilmesi

    OpenAIRE

    ERDEM, O. Ayhan; ORMAN, Abdullah

    2010-01-01

    Bu çalısmada, seri iletim hatlı mikrodenetleyici denetimli asansör tasarımı ve prototipi gerçeklestirildi. Mevcutasansör haberlesme sistemlerinde kullanılan kablolama sekillerine alternatif olarak seri iletisim protokolününkullanılmasını saglayan bir tasarım gerçeklestirildi. Tüm asansör sistemlerinde kullanılabilmesi amacıyla farklıstandartlarda olan asansörler için de farklı programlar yazıldı. Bu programlar PIC C de yazılmıstır. Tasarımıgerçeklestirilen devre, laboratuvar ve gerçek ortamda...

  4. 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

  5. Research Nuclear Reactors

    International Nuclear Information System (INIS)

    Published in English and in French, this large report first proposes an overview of the use and history of research nuclear reactors. It discusses their definition, and presents the various types of research reactors which can be either related to nuclear power (critical mock-ups, material test reactors, safety test reactors, training reactors, prototypes), or to research (basic research, industry, health), or to specific particle physics phenomena (neutron diffraction, isotope production, neutron activation, neutron radiography, semiconductor doping). It reports the history of the French research reactors by distinguishing the first atomic pile (ZOE), and the activities and achievements during the fifties, the sixties and the seventies. It also addresses the development of instrumentation for research reactors (neutron, thermal, mechanical and fission gas release measurements). The other parts of the report concern the validation of neutronics calculations for different reactors (the EOLE water critical mock-up, the MASURCA air critical mock-up dedicated to fast neutron reactor study, the MINERVE water critical mock-up, the CALIBAN pulsed research reactor), the testing of materials under irradiation (OSIRIS reactor, laboratories associated with research reactors, the Jules Horowitz reactor and its experimental programs and related devices, irradiation of materials with ion beams), the investigation of accident situations (on the CABRI, Phebus, Silene and Jules Horowitz reactors). The last part proposes a worldwide overview of research reactors

  6. Reactor Physics Training

    International Nuclear Information System (INIS)

    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

  7. 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

  8. Safeguarding research reactors

    International Nuclear Information System (INIS)

    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

  9. Cumhuriyet'in kurucular kuşağından bir aydın: Sabri Esat Siyavuşgil

    OpenAIRE

    ÇALMAZ, Fatih

    2013-01-01

    İmparatorluktan ulus devlete geçişte, milli kimliğin oluşumu ve rejimin inşasında kurucular kuşağı aydınlarının Cumhuriyetin erken döneminden başlayarak 1960’lı yıllara kadar etkin oldukları bilinmektedir. Cumhuriyetin kurucular kuşağı aydınları içinde bir bilim adamı olarak faaliyet gösteren Sabri Esat Siyavuşgil, daha çok bir kültür adamı kimliği ile tanınmaktadır. Daru-l Fünün’un lağv edilip yerine kurulan İstanbul Üniversitesinin pedag...

  10. Dental florozisin beyazlatılmasında kullanılan bir Office Bleaching metaryalinin pulpa ve periapikal dokular üzerindeki yan etkilerinin incelenmesi

    OpenAIRE

    Keçeci, Ayşe Diljin; Özdemir, Feyza

    2009-01-01

    Süleyman Demirel Üniversitesi TIP FAKÜLTESİ DERGİSİ: 2008 Mart; 15 (2) Dental florozisin beyazlatılmasında kullanılan bir Office Bleaching metaryalinin pulpa ve periapikal dokular üzerindeki yan etkilerinin incelenmesi Ayşe Diljin Keçeci Feyza Özdemir Özet Amaç: Önemli düzeyde estetik, hatta psikolojik problemlere yol açan dental florozise bağlı renklenmelerin tedavisinde estetiği kazandırırken dişe en az zarar verecek bir tedavi yönteminin seçilmesi amaçlanmalıdır. Gü...

  11. Mesane içine Bacillus Calmette-Guerin uygulanması sonrası gelişen reaktif artrit: Bir olgu sunumu

    OpenAIRE

    Tunç, Ş.Ercan; Arslan, Çağatay; Şahin, Mehmet; Adiloğlu, Ali Kudret

    2009-01-01

    SüleymanDemirel Üniversitesi TIP FAKÜLTESİ DERGİSİ: 2004 Eylül; 11(3) Mesane içine Bacillus Calmette-Guerin uygulanması sonrası gelişen reaktif artrit: Bir olgu sunumu Ş.Ercan Tunç, Çağatay Arslan, Mehmet Şahin, Ali Kudret Adiloğlu Özet Bacillus Calmette-Guerin (BCG) uygulaması süperfisiyal mesane karsinomlarında kullanılan etkin bir tedavi metodudur. Bu tedavi sırasında nadiren reaktif olarak artrit ve artraljiler gelişebilmektedir. Burada, mesaneye dördü...

  12. Ispanak (Spinacia oleracea L.) tohumlarının ekim mekanizasyonunun iyileştirilmesi üzerine bir araştırma

    OpenAIRE

    Özgüven, Fikret

    2008-01-01

    Ülkemizin sebze üretimi içersinde önemli bir yeri bulunan ıspanak üretimi tamamen kaplanmamıs tohumlarla yapılmaktadır. Ispanak tohumlarının küçük olusu, üzerinde dikenler tasıması nedeniyle birkaç tanesinin bir araya gelerek yumaklar yapması gibi nedenlerle makinalı ekimde büyük sorunlar olusturmaktadır. Serpme ekim yapıldıgında, fazla tohum sarfiyatı nedeniyle maliyet artmaktadır. Ayrıca kültürel islemler ve makinalı hasat için serpme ekim uygun olmamaktadır. Son yıllarda ...

  13. 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.

  14. SIP Tabanlı Telefon Servislerinin IPTV Sistemine Bütünleştirilebilmesi İçin Yeni Bir Protokol Önerisi

    Directory of Open Access Journals (Sweden)

    Hasan Yükselten

    2011-06-01

    Full Text Available Bu çalışmada, oturum başlatma protokolü (SIP tabanlı çağrı sunucusuyla sağlanan telefon servislerinin IPTV sistemiyle bütünleşmesini sağlayacak yeni bir mimari yapı önerilmiş ve bu amaca yönelik yeni bir protokol (Bağımsız Bildirim Protokolü tasarlanarak geliştirilen mimari yapının avantajları incelenmiştir. Önerilen mimari yapı ve bunu destekleyen protokoller, bildirim mimarisinde arabirim katmanına (middleware olan gereksinimi ortadan kaldırmaktadır. Böylece, bildirim mimari yapısı bir katman azaltılmakta, arabirim katmanına olan bağımlılık sona ermekte, her türlü arabirim katmanı ile bildirim mimarisi kurulabilmektedir. Geliştirilen mimari yapı ve protokolün testleri sonucunda, bildirim bant genişliğinin, mevcut bildirim mimari yapılarındakinin %10’una kadar düştüğü ve önerilen mimari yapının başarılı bir şekilde çalıştığı görülmüştür.

  15. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    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.)

  16. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    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

  17. Reactor System Design

    International Nuclear Information System (INIS)

    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

  18. [School Choice: A Mechanism Desing Approach], Okul Seçimi: Bir Mekanizma Tasarımı Yaklaşımı

    Directory of Open Access Journals (Sweden)

    Atila ABDULKADİROĞLU

    2014-12-01

    Full Text Available Okul seçimi konusundaki temel meselelerden bir tanesi öğrenci yerleştirilmeleriyle ilgili bir mekanizma tasarlamaktır. Eğitim yazını, böyle mekanizmaların tasarlanmasıyla ilgili yol göstermesine rağmen belirli tasarılar sunmamaktadır. Halen var olan okul seçimi planlarındaki kusurlar, memnun olmayan velilerin itirazlarına sebebiyet vermektedir. Biz, okul seçimi problemini bir mekanizma tasarımı problemi gibi formüle edip Boston, Columbus, Minneapolis ve Seattle’dakilerin de aralarında olduğu mevcut okul seçimi planlarından bazılarını analiz ediyoruz. Bu planların ciddi yetersizlikler barındırdıklarını gösterip her biri önemli bazı okul seçimi meselelerine pratik çözümler getiren iki alternatif mekanizma öneriyoruz.

  19. Türk Mimarisinde Cami İmajı Algısı : (Biçim-Form Üzerinden Bir Yaklaşım)

    OpenAIRE

    Sarıhan, Fatma Zehra

    2015-01-01

    "Türk Mimarisinde Cami İmajı Algısı Biçim- Form Üzerinden Bir Yaklaşım" İsimli bu çalışma geleneksel dini yapılar ve mimari mekân algısının birbiri ile etkileşimi sonucu bir arada incelenmesi ile oluşmuştur. Çalışma algıya yöneliktir. Toplumun kültür ve dini değerleri ile oluşan cami yapılarının, aynı toplumdan gelen bir başka nesli üzerinde algısı ve etkisini ölçmektedir. Başlangıçta cami mimarisinin oluşumu ve tarihçesi ile nasıl gelişim gösterdiği incelenmiştir. Türklerin cami yapıların...

  20. 18. yüzyılın ikinci yarışında Trabzon'da etkin bir ayan ailesi: Şatırzadeler

    OpenAIRE

    Yürük, Emre

    2016-01-01

    Osmanlı Devleti, 17. yüzyılın başından itibaren askeri, idari ve ekonomik birtakım değişimler yaşayarak klasik sisteminde yeni düzenlemelere gitmiştir. Bu yeni düzenlemeler Osmanlı tarihinin en dikkat çekici dönemlerinden biri olan ve mahalli güçlerin taşradaki yükselişini temsil eden “Ayanlar Çağı” adı verilen yeni bir dönemi beraberinde getirmiştir. Devletin ihtiyaçlarım her anlamda karşılayan yeni bir sınıfın oluşmasıyla taşrada güç dengeleri de değişmeye başlamıştır. Osmanlı ülkesinin bir...

  1. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kawakami, Hiroto

    1995-02-07

    A reactor container of the present invention has a structure that the reactor container is entirely at the same temperature as that at the inlet of the reactor and, a hot pool is incorporated therein, and the reactor container has is entirely at the same temperature and has substantially uniform temperature follow-up property transiently. Namely, if the temperature at the inlet of the reactor core changes, the temperature of the entire reactor container changes following this change, but no great temperature gradient is caused in the axial direction and no great heat stresses due to axial temperature distribution is caused. Occurrence of thermal stresses caused by the axial temperature distribution can be suppressed to improve the reliability of the reactor container. In addition, since the laying of the reactor inlet pipelines over the inside of the reactor is eliminated, the reactor container is made compact and the heat shielding structures above the reactor and a protection structure of container walls are simplified. Further, secondary coolants are filled to the outside of the reactor container to simplify the shieldings. The combined effects described above can improve economical property and reliability. (N.H.).

  2. Fossil nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Maurette, M.

    1976-01-01

    The discussion of fossil nuclear reactors (the Oklo phenomenon) covers the earth science background, neutron-induced isotopes and reactor operating conditions, radiation-damage studies, and reactor modeling. In conclusion possible future studies are suggested and the significance of the data obtained in past studies is summarized. (JSR)

  3. Ortodonti ve periodontoloji işbirliği. Modern biyolojik ortodontide periodontal konular

    Directory of Open Access Journals (Sweden)

    Tancan Uysal

    2011-01-01

    ;">    Ortodontistlerin ve periodontologların yaptıkları klinik tedavilerde periodontoloji ile ortodonti arasındaki ilişkinin biyolojik temellerinin farkında olması gerekmektedir. İki uzmanlık dalı arasındaki uyum, tedavi sonuçlarının olumlu olmasını sağlamaktadır. Bölümler arasında gerçekleştirilen işbirliği ile ortodontik tedavi periodontal sağlığı geliştirdiği gibi periodontal tedavi de ortodontik tedavi sonuçlarını daha da başarılı hale getirebilmektedir. Teknoloji, uzmanlık dalları arasında etkileşimi sağlarken, tedavinin temelini biyoloji oluşturmaktadır. Yeni yüzyılın ortodontisti; bilgili, deneyimli ve sorumluluk sahibi periodontolog ile beraber çalışmalıdır. Ortodontik tedavi görecek hastalar, periodontal riskler, dişeti büyümeleri ve olası alveolar kemik kaybından haberdar edilmelidir. Bu derlemede, aselüler dermal matriks, mine matriks proteinleri, periodontal plastik cerrahi ve yeni bir ortognatik cerrahi alternatifi olan “periodontal olarak hızlandırılmış osteojenik ortodonti” gibi güncel tedaviler ile geleneksel tedaviler tartışılacaktır. Ayrıca aşağıdaki sorulara cevaplar bulunmaya çalışılacaktır; “Ortodontik tedavi periodontal hastalığa sebep olur mu?”, “Periodontal olarak enfekte olan hastalar ortodontik diş hareketleri ile tedavi edilebilir mi?”, “Hastalara ne zaman ve hangi cerrahi yaklaşımlar yapılmaktadır?”, “Hangi tedavi seçenekleri en iyi sonuçları verir ve periodontal dokulara daha az zarar verir?”, “Ne sıklıkla ortodonti hastaları periodontolog tarafından takip edilmelidir?”. Ayrıca periodontal açıdan ortodontik tedavinin endikasyonları, kontrendikasyonları, sınırlamaları, avantaj ve dezavantajları tartışılacaktır.

    Nuclear reactor repairing device

    International Nuclear Information System (INIS)

    Purpose: To enable free repairing of an arbitrary position in an LMFBR reactor. Constitution: A laser light emitted from a laser oscillator installed out of a nuclear reactor is guided into a portion to be repaired in the reactor by using a reflecting mirror, thereby welding or cutting it. The guidance of the laser out of the reactor into the reactor is performed by an extension tube depending into a through hole of a rotary plug, and the guidance of the laser light into a portion to be repaired is performed by the transmitting and condensing action of the reflecting mirror. (Kamimura, M.)

  4. 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

  5. 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

  6. 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. 

  7. 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

  8. 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

  9. Prevalence of parasitic infection in captive wild animals in Bir Moti Bagh mini zoo (Deer Park, Patiala, Punjab

    Directory of Open Access Journals (Sweden)

    A. Q. Mir

    2016-06-01

    Full Text Available Aim: The study was conducted to know the prevalence of gastrointestinal parasites of captive wild animals at Bir Moti Bagh Mini Zoo (Deer Park, Patiala, Punjab. Materials and Methods: A total of 31 fecal samples from eight species of captive animals including Civet cat (Viverra zibetha, Porcupine (Hystrix indica, Nilgai (Boselaphus tragocamelus, Spotted deer (Axis axis, Black buck (Antelope cervicapra, Sambar deer (Cervus unicolor, Hog deer (Axis porcinus, and Barking deer (Muntiacus muntjak were screened using classical parasitological techniques including sedimentation and floatation technique. Results: Out of 31 fecal samples examined, 20 were positive for parasitic ova/oocysts of different species indicating an overall prevalence of 68.0%. The six different types of parasites observed in the study included strongyle (67%, Strongyloides spp. (14%, coccidia (38%, Trichuris spp. (19%, ascarid (10%, and Capillaria spp. (10%. Strongyles were the most common parasites observed (67% followed by coccidia (38%. Mixed helminth and protozoan infection were observed in 48% of animals. No cestode or trematodes were detected during the study. Conclusion: The high prevalence of gastrointestinal parasites without overt clinical signs of disease or mortality as observed in this study is suggestive of subclinical infection. The findings will help in formulating the appropriate deworming protocol for parasitic control in these captive animals.

  10. 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.

  11. Reactor Vessel Surveillance Program for Advanced Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyeong-Hoon; Kim, Tae-Wan; Lee, Gyu-Mahn; Kim, Jong-Wook; Park, Keun-Bae; Kim, Keung-Koo

    2008-10-15

    This report provides the design requirements of an integral type reactor vessel surveillance program for an integral type reactor in accordance with the requirements of Korean MEST (Ministry of Education, Science and Technology Development) Notice 2008-18. This report covers the requirements for the design of surveillance capsule assemblies including their test specimens, test block materials, handling tools, and monitors of the surveillance capsule neutron fluence and temperature. In addition, this report provides design requirements for the program for irradiation surveillance of reactor vessel materials, a layout of specimens and monitors in the surveillance capsule, procedures of installation and retrieval of the surveillance capsule assemblies, and the layout of the surveillance capsule assemblies in the reactor.

  12. Cronbach’ın Alfası, Tek Boyutluluğun veya Benzeşikliğin (Homojenliğin) Bir Ölçüsü Değildir

    OpenAIRE

    BADEMCİ, Vahit

    2014-01-01

    Güvenirlik, testler veya ölçme araçlarının değil, ölçümlerin bir özelliğidir. Cronbach’ın alfası katsayısı yöntemi, bir test ya da ölçme aracından elde edilen ölçümlerin güvenirliğini kestirme yöntemlerinden biridir. Başka bir ifadeyle, Cronbach’ın alfası, [madde] ölçümler[i] arasındaki iç tutarlılık üzerine temellenmiş bir ölçüm güvenirliğinin kestirilmesidir. Bunun yanı sıra, Cronbach’ın alfası katsayısı, ölçme aracının benzeşikliğinin (homojenliğinin) bir göstergesi olarak alınmamalı veya ...

  13. 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...

  14. Multipurpose research reactors

    International Nuclear Information System (INIS)

    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

  15. 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.

  16. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    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. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    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)

  18. Preterm yenidoğanlarda nekrotizan enterokolitin öncü bir göstergesi ve tedaviye yanıtın bir belirteci olarak fekal 'calprotectın' düzeyinin araştırılması

    OpenAIRE

    Menteş, Didem Ayşe

    2007-01-01

    Dışkı ?calprotectin? düzeylerinin nekrotizan enterokoliti öngören bir parametre ve tedaviye yanıtın bir belirteci olarak kullanılıp kullanılamayacağını ve dışkı ?caprotectin? düzeyini etkileyebilecek faktörlerin dışkı ?caprotectin? düzeyi ile ilişkisini araştırdığımız çalışmamıza 36 gebelik haftası ve öncesinde doğan 101 olgu prospektif olarak alındı. Nekrotizan enterokolit geliştirenler Grup 1 (n=33) ve geliştirmeyenler Grup 2 (n=68) olarak ayrıldı. Prenatal, natal ve postnatal özellikleri k...

  19. Pazarlama Yeniliği ile Pazarlama Performansı İlişkisini Açıklamaya Yönelik Bir Vaka Çalışması : Süleyman Demirel Üniversitesi Olimpik Yüzme Havuzu Örneği ve Bir Model Önerisi

    OpenAIRE

    Tüfekci, Ömer Kürşad; Tüfekci, Nezihe

    2014-01-01

    Pazarlama yeniliği girişimciliğin bir aracı olarak ele alınabilmektedir. Pazarlama yeniliği yeni süreçler ve farklılık meydana getirmektedir. Bu araştırmada pazarlama yeniliği ile pazarlama performansı ilişkisi açıklanmaya çalışılacaktır. Bu kapsamda Süleyman Demirel Üniversitesi Olimpik Yüzme Havuzunun pazarlama stratejisi ele alınarak bir vaka çalışması yapılmıştır. Araştırmada pazarlama yeniliği değişkenleri olarak ürün, fiyat ve tutundurma faaliyetleri; pazarlama perf...

  1. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kanbe, Mitsuru

    1997-04-04

    An LMFBR type reactor comprises a plurality of reactor cores in a reactor container. Namely, a plurality of pot containing vessels are disposed in the reactor vessel and a plurality of reactor cores are formed in a state where an integrated-type fuel assembly is each inserted to a pot, and a coolant pipeline is connected to each of the pot containing-vessel to cool the reactor core respectively. When fuels are exchanged, the integrated-type fuel assembly is taken out together with the pot from the reactor vessel in a state where the integrated-type fuel assembly is immersed in the coolants in the pot as it is. Accordingly, coolants are supplied to each of the pot containing-vessel connected with the coolant pipeline and circulate while cooling the integrated-type fuel assembly for every pot. Then, when the fuels are exchanged, the integrated type fuel assembly is taken out to the outside of the reactor together with the pot by taking up the pot from the pot-containing vessel. Then, neutron economy is improved to thereby improve reactor power and the breeding ratio. (N.H.)

  2. The International Framework of Information Policies Enformasyon Politikalarına Küresel Bir Bakış

    Directory of Open Access Journals (Sweden)

    Nick Moore

    2000-03-01

    Full Text Available The emergence of information societies is one of the defining characteristics of the last decade of the twentieth century. Countries all over the world are repositioning themselves to take advantage of the opportunities offered by the information age. They share common objectives although there are significant differences in the motivations underlying the re-positioning and in the mechanisms chosen to implement information society developments. Formal frameworks of policy are being established to steer the development of information societies. There can be few other examples of technological change stimulating formal policy creation in order to bring about social change. This paper surveys the approaches to information policy in various countries all over the world and forecasts future progress with views as to how to ensure that the information society will work for the good of every one. 20. yüzyılın son on yılının belirleyici karakteristiklerinden biri enformasyon toplumlarının ortaya çıkması olmuştur. Dünyanın dört bir yanında ülkeler, enformasyon çağının yarattığı olanaklardan yararlanabilmek için konumlarını gözden geçirmektedirler. Bu ülkelerin hedefleri aynı olmakla birlikte, yönelimlerinin ardındaki motivasyonlar her zaman aynı değildir ve enformasyon toplumu gelişmelerini uygulamaya sokmak için seçtikleri mekanizmalar önemli farklılıklar göstermektedir. Enformasyon toplumuna geçişi harekete geçirmek için resmi politikalar saptanmaktadır. Bunun dışında, teknolojik değişimin, bağlantılı bir toplumsal değişimi sağlamak için resmi politikalar belirlenmesini zorladığı çok ender görülmüştür. Bu bildiride dünyanın çeşitli ülkelerinde enformasyon politikalarına yaklaşımların neler olduğu gözden geçirilmekte, geleceğe yönelik görüşler sunulmakta ve enformasyon toplumunun herkesin yararına gelişmesi için neler yapılması gerektiği konusu işlenmektedir.

  3. 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

  4. Biržoje prekiaujamų fondų (ETF bendrojo išlaidų rodiklio tyrimas

    Directory of Open Access Journals (Sweden)

    Lukas Macijauskas

    2011-07-01

    Full Text Available Diskusijai, kuris – pasyvus ar aktyvus – investicijų valdymas yra efektyvesnis, ryškėjant, biržoje prekiaujami fondai (Exchange Traded Funds – ETF sulaukia vis didesnio investuotojų dėmesio, o tai skatina detalesnius šių priemonių tyrinėjimus. Pagrindinis šio straipsnio tikslas – įvairiais aspektais analizuoti šių finansinių priemonių bendrąjį išlaidų rodiklį (Total Expense Ratio (TER. Naudodami duomenų bazę, kurią sudaro 1020 ETF, apskaičiavome, kad paprastųjų, t. y. nenaudojančių sverto ir ne atvirkštinių ETF, svertinis bendrojo išlaidų rodiklio vidurkis (įvertinant kapitalizaciją yra lygus 0,32 proc. Analizė rodo, kad atvirkštiniai ir svertiniai ETF vidutiniškai apie 3 kartus brangesni nei paprastieji ETF. Atlikę skaičiavimus nustatėme, kad bendrasis išlaidų rodiklis yra gerokai mažesnis nei vidutinių investicinių fondų. Tai leidžia daryti išvadą, kad vertinant per išlaidų koeficiento prizmę, ETF yra daug efektyvesnė investavimo priemonė nei įprasti investiciniai fondai.Straipsnis lietuvių kalba

  5. 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

  6. 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

  7. 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

  8. Böbrek Yaralanmasını Taklit Eden Nadir Bir Renal Kolik Olgusu : Koç Toslaması Sonrası Gelişen Renal Kolik

    OpenAIRE

    Sancak, Eyüp Burak; Reşorlu, Mustafa; Akbaş, Alpaslan; Gülpınar, Murat Tolga

    2014-01-01

    Hayvanlarla ilişkili travmalar, ciddi morbidite ve mortalite potansiyelinden dolayı, önemli bir tıbbi problemdir. Türkiyede hayvancılığın halen önemli bir geçim kaynağı oluşu, bu problemin riskini artırmaktadır. Koç saldırısı sonucu oluşan travma ile ilgili literatürde çok az veri vardır. Ancak hayvanla ilişkili travma sonrası renal kolik vakasına literatürde rastlanmamıştır. Biz burada genç erişkin bir hastada, koç saldırısı sonrası gelişen akut renal kolik olgusunu sunmayı planl...

  9. An experiment on the factors affecting simple reaction timeBasit reaksiyon zamanını etkileyen faktörler üzerine bir deney

    Directory of Open Access Journals (Sweden)

    Ufuk Türen

    2013-10-01

    Full Text Available Reaction time is considered as an important measure that affects performance of an individual both in business and private life. Especially, reaction time, which can be defined as a period of time being required for giving appropriate responses to the perceived stimuli, is an important factor in terms of efficiency of organization and also health and safety at work. Moreover, reaction time is regarded as an important factor in product design. In this study, an experiment is designed to reveal the factors that affect simple reaction time and the effects of (discrete / continuous variables such as age, height, weight, gender, sight defects, smoking and alcohol use, regular habits of sports and academic achievement on reaction time of individuals are investigated, and the findings are interpreted. Özet İnsanlarda reaksiyon zamanı hem özel yaşamda hem de iş yaşamında performansı etkileyen önemli bir faktör olarak kabul edilmektedir. Özellikle çalışanların algıladıkları etkilere uygun tepkiler verebilmeleri için ihtiyaç duydukları zaman olarak tanımlanan reaksiyon zamanı, örgütün verimliliği açısından olduğu kadar işçi sağlığı ve iş güvenliği açısından da önemli bir özelliktir. Ayrıca, reaksiyon zamanının ürün tasarımı için de önemli bir faktör olduğu bilinmektedir. Bu çalışmada; insanların basit reaksiyon zamanlarını etkileyen faktörleri ortaya koymak için bir deney tasarlanmış ve yaş, boy, kilo, cinsiyet, görme kusurları, sigara ve alkol kullanma, düzenli spor yapma ve akademik başarı gibi (kesikli/sürekli değişkenlerin bireylerin reaksiyon zamanı üzerindeki etkileri araştırılmış, bulgular yorumlanmıştır.

  10. 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

  11. ‘Play Time’ Filmi ve Modern Mimarlık Kuramlarına İlişkin Eleştirel Bir Deneme

    Directory of Open Access Journals (Sweden)

    Mehmet Şener

    2016-01-01

    Full Text Available ÖzJacques Tati sineması, gerek dünya sinema tarihinde, gerek de mimarlık (tarihi sinema ilişkisi bağlamında çok önemli bir yere sahiptir. Tati’nin 1967 yılında çektiği ‘Play Time’ filmi de, mimari ve kentsel unsurlar üzerine şekillenir ve dönemine bu çerçevelerden ışık tutan bir filmdir. Bu makalede, Tati’nin ‘Play Time’ filmi üzerinden yapılacak mekânsal analizler doğrultusunda modern mimarlık ve şehircilik kuramları üzerine eleştirel bir bakış getirilmesi amaçlanmaktadır. Bu çerçevede, ilk bölümde Jacques Tati filmlerinin sinema dünyası ve tarihindeki yeri ile ‘Play Time’ filminin sinematografik yapısı incelenecektir. Bundan sonraki kısımlarda filme dair mekansal analiz ve bulgular üzerine değerlendirmeler yapılacak olup; öncelikle modern mimarinin başat unsurlarından olan “prizmatik” kamusal yapılar ve “kutu mekanlar”, sonrasında da filmde yer alan sergi mekânı, mobilya tasarımı bağlamında yabancılaşma metaforu üzerinden ele alınacaktır. Bunu müteakip, filmdeki sembolik mimari ifade araçlarından biri olan “cam”, modern yaşamda ifade ettiği anlam çerçevesinde; konut yaşantısının resmedildiği sahneler de, modern yaşamın konut ve yapı mahremiyetine etkileri üzerinden analiz edilecektir. Son kısımda da, restoran sahnelerinin incelenmesi üzerinden modern tasarım anlayışına dair eleştirel bir inceleme yapılacak ve sonuç kısmıyla makale tamamlanacaktır.     

  12. 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.

  13. Ürünlerde Son Kullanma Tarihinin Tüketicilerce Algılanmasına Yönelik Bir Araştırma

    OpenAIRE

    Açıkgözoğlu, Semih

    2006-01-01

    Bu çalışma ürünlerde son kullanma tarihinin tüketicilerce algılanmasına yönelik bir araştırmadır. Anket yoluyla elde edilen bilgilerin istatiksel anlamda ilişkileri incelenmiştir. Sonuç olarak tüketicilerin son kullanma tarihine dikkat ettikleri ve tüketicilik bilincinin ülkemizde de oluşmaya başladığı anlaşılmıştır.

  14. One piece reactor removal

    International Nuclear Information System (INIS)

    Japan Research Reactor No.3 (JRR-3) was the first reactor consisting of 'Japanese-made' components alone except for fuel and heavy water. After reaching its initial critical state in September 1962, JRR-3 had been in operation for 21 years until March 1983. It was decided that the reactor be removed en-bloc in view of the work schedule, cost and management of the reactor following the removal. In the special method developed jointly by the Japanese Atomic Energy Research Institute and Shimizu Construction Co., Ltd., the reactor main unit was cut off from the building by continuous core boring, with its major components bound in the block with biological shield material (heavy concrete), and then conveyed and stored in a large waste store building constructed near the reactor building. Major work processes described in this report include the cutting off, lifting, horizontal conveyance and lowering of the reactor main unit. The removal of the JRR-3 reactor main unit was successfully carried out safely and quickly by the en-block removal method with radiation exposure dose of the workers being kept at a minimum. Thus the high performance of the en-bloc removal method was demonstrated and, in addition, valuable knowhow and other data were obtained from the work. (Nogami, K.)

  15. 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)

  16. Light water reactor program

    Energy Technology Data Exchange (ETDEWEB)

    Franks, S.M.

    1994-12-31

    The US Department of Energy`s Light Water Reactor Program is outlined. The scope of the program consists of: design certification of evolutionary plants; design, development, and design certification of simplified passive plants; first-of-a-kind engineering to achieve commercial standardization; plant lifetime improvement; and advanced reactor severe accident program. These program activities of the Office of Nuclear Energy are discussed.

  17. Research reactor DHRUVA

    International Nuclear Information System (INIS)

    DHRUVA, a 100 MWt research reactor located at the Bhabha Atomic Research Centre, Bombay, attained first criticality during August, 1985. The reactor is fuelled with natural uranium and is cooled, moderated and reflected by heavy water. Maximum thermal neutron flux obtained in the reactor is 1.8 X 1014 n/cm2/sec. Some of the salient design features of the reactor are discussed in this paper. Some important features of the reactor coolant system, regulation and protection systems and experimental facilities are presented. A short account of the engineered safety features is provided. Some of the problems that were faced during commissioning and the initial phase of power operation are also dealt upon

  18. TRIGA research reactors

    International Nuclear Information System (INIS)

    TRIGA (Training, Research, Isotope production, General-Atomic) has become the most used research reactor in the world with 65 units operating in 24 countries. The original patent for TRIGA reactors was registered in 1958. The success of this reactor is due to its inherent level of safety that results from a prompt negative temperature coefficient. Most of the neutron moderation occurs in the nuclear fuel (UZrH) because of the presence of hydrogen atoms, so in case of an increase of fuel temperature, the neutron spectrum becomes harder and neutrons are less likely to fission uranium nuclei and as a consequence the power released decreases. This inherent level of safety has made this reactor fit for training tool in university laboratories. Some recent versions of TRIGA reactors have been designed for medicine and industrial isotope production, for neutron therapy of cancers and for providing a neutron source. (A.C.)

  19. Mirror reactor surface study

    International Nuclear Information System (INIS)

    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

  20. 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)

  1. Status of French reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ballagny, A. [Commissariat a l`Energie Atomique, Saclay (France)

    1997-08-01

    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{sup 3}. The OSIRIS reactor has already been converted to LEU. It will use U{sub 3}Si{sub 2} as soon as its present stock of UO{sub 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.

  2. Compact torsatron reactors

    International Nuclear Information System (INIS)

    Low-aspect-ratio torsatron configurations could lead to compact stellarator reactors with R0 = 8--11m, roughly one-half to one-third the size of more conventional stellarator reactor designs. Minimum-size torsatron reactors are found using various assumptions. Their size is relatively insensitive to the choice of the conductor parameters and depends mostly on geometrical constraints. The smallest size is obtained by eliminating the tritium breeding blanket under the helical winding on the inboard side and by reducing the radial depth of the superconducting coil. Engineering design issues and reactor performance are examined for three examples to illustrate the feasibility of this approach for compact reactors and for a medium-size (R0 ≅ 4 m,/bar a/ /approx lt/ 1 m) copper-coil ignition experiment. 26 refs., 11 figs., 7 tabs

  3. 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.

  4. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities in the Division of Reactor Engineering in fiscal 1977 are described. Works of the Division are development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and development of Liquid Metal Fast Breeder Reactor for 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 Committee on Reactor Physics. (Author)

  5. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    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)

  6. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    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.)

  7. Tasavvufun ve Epistemolojik Bir Araç Olarak İlhamın İbn Teymiyye Düşüncesindeki Yeri

    Directory of Open Access Journals (Sweden)

    Emrah Kaya

    2016-06-01

    Full Text Available ÖZ: Bu makalenin amacı Selef anlayışına dayalı bir geleneğin savunucusu olarak tanınan İbn Teymiyye’nin tasavvufa ve tasavvufî bilginin temel aracı olan ilhama yaklaşımını çalışmaktır. Tasavvufî ıstılahları genel sûfî anlayıştan farklı bir şekilde yorumlayan İbn Teymiyye birçok kimse tarafından katı bir tasavvuf karşıtı olarak görülmüştür. Ayrıca İbn Teymiyye’nin sürekli olarak Kur’an, hadis ve Selefin düşüncelerini dinî bilginin temeli olarak sunması onun ilham ve rasyonel metotlar ile elde edilen bilgiye sıcak bakmadığı, bunlara epistemolojisinde yer vermediği düşüncesinin ortaya çıkmasına ve zaman içinde gelişmesine neden olmuştur. Hâlbuki araştırmamızın sonucunda İbn Teymiyye’nin tasavvufu belli şartlar ile kabul etmesinin yanı sıra ilhamın epistemolojik değerini de onayladığı sonucuna ulaşılmıştır. O, tasavvufu erken dönem ve sonraki dönem tasavvuf olarak incelerken, ilhamı doğaüstü olayların bir alt kategorisi olarak gördüğü ilim bâbında ele almaktadır. Tasavvufun ve ilham ile gelen bilginin Kur’an, sünnet ve Selefin düşünceleri ışığında test edilmesi gerektiğine inanan İbn Teymiyye’nin yaptığı reddetmek değil, kendi kriterleri doğrultusunda meseleyi detaylı olarak incelemektir. Bu nedenle, konuyu eleştirel ve betimsel olarak ele alan makalemiz İbn Teymiyye’nin tasavvufa ve tasavvufî bilginin temel dayanağı olan ilhama yönelik tutumuna odaklanmaktadır.ÖZET: İslam tarihinde en etkili, üretken ve tartışmalı âlimlerden biri olan İbn Teymiyye dinî bilgi edinmede en iyi ve en güvenilir yolu bulmak için samimiyetle çaba sarf etmiştir. Bu çaba sonucunda onun Kur’an, hadis, Kelâm, İslam felsefesi ve Yunan felsefesi hakkındaki muazzam bilgisi verimli eserleri vasıtasıyla müşâdehe edilebilir. Epistemolojik, teolojik ve felsefî ifadelerinin dağınık bir şekilde bulunduğu eserlerinde vahiy

  8. Reactor performance calculations for water reactors

    International Nuclear Information System (INIS)

    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.

  9. Safety of research reactors

    International Nuclear Information System (INIS)

    The number of research reactors that have been constructed worldwide for civilian applications is about 651. Of the reactors constructed, 284 are currently in operation, 258 are shut down and 109 have been decommissioned. More than half of all operating research reactors worldwide are over thirty years old. During this long period of time national priorities have changed. Facility ageing, if not properly managed, has a natural degrading effect. Many research reactors face concerns with the obsolescence of equipment, lack of experimental programmes, lack of funding for operation and maintenance and loss of expertise through ageing and retirement of the staff. Other reactors of the same vintage maintain effective ageing management programmes, conduct active research programmes, develop and retain high calibre personnel and make important contributions to society. Many countries that operate research reactors neither operate nor plan to operate power reactors. In most of these countries there is a tendency not to create a formal regulatory body. A safety committee, not always independent of the operating organization, may be responsible for regulatory oversight. Even in countries with nuclear power plants, a regulatory regime differing from the one used for the power plants may exist. Concern is therefore focused on one tail of a continuous spectrum of operational performance. The IAEA has been sending missions to review the safety of research reactors in Member States since 1972. Some of the reviews have been conducted pursuant to the IAEA' functions and responsibilities regarding research reactors that are operated within the framework of Project and Supply Agreements between Member States and the IAEA. Other reviews have been conducted upon request. All these reviews are conducted following procedures for Integrated Safety Assessment of Research Reactors (INSARR) missions. The prime objective of these missions has been to conduct a comprehensive operational safety

  10. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    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)

  11. Reactor engineering department annual report

    International Nuclear Information System (INIS)

    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)

  12. Disiplinler Arası Bir Disiplin Olarak Türkçe Eğitimi Turkish Education as an Interdisciplinary Discipline

    Directory of Open Access Journals (Sweden)

    Namık Kemal ŞAHBAZ

    2012-09-01

    , grammarteaching, first reading and writing teaching, children’s literature,training Turkish teachers and historical development of Turkisheducation. Disiplinler arasılık, günümüz sosyal bilimleri için bir gerekliliktir. Çoğu kez, herhangi bir soruna bir tek disiplinin çerçevesinden bakmak yetersiz olabilir. Disiplinler arası araştırmalar, bilgiye farklı bakış açıları sunar. Bu çalışmada görece yeni bir bilimsel disiplin olan Türkçe eğitiminin disiplinler arası niteliği gerek kuramsal gerek de uygulama boyutuyla betimlenmeye çalışılmıştır. Bu amaçla öncelikle Türkçe eğitiminin araştırma alanları (Okuma eğitimi, konuşma eğitimi, yazma eğitimi, dinleme eğitimi, dil bilgisi öğretimi, ilk okuma ve yazma öğretimi, çocuk edebiyatı, Türkçe öğretmeni yetiştirme, Türkçe eğitimi tarihi açıklanmış, daha sonra Türkçe eğitiminin disiplinler arası araştırmalara neden gereksinim duyduğu tartışılmıştır. Çalışmada, araştırılması amaçlanan olgu ve olgular hakkında bilgi içeren yazılı materyallerin analizini kapsayan doküman inceleme yöntemi kullanılmıştır. Türkçe eğitimi ile eğitim bilimleri, dilbilim, yazınbilim, sosyoloji, psikoloji, tarih ve tıp disiplinleri arasındaki disiplinler arası ilişkiler irdelenmiştir. Bilimsel bir disiplin olarak ele alınmasa da kişisel gelişim konularıyla (ikna, etkili iletişim, yapay zekâ, duygusal zekâ, NLP Türkçe eğitimi arasındaki etkileşim, bu çalışmada açıklanmaya çalışılmıştır. Bu çalışma, Türkçe eğitimi alanında yapılacak yeni araştırmalara farklı bir boyut ve bir bakış açısı kazandıracak olması nedeniyle önemlidir. Araştırmanın sonuçları itibariyle hâlihazırda Türkçe eğitimine yönelik disiplinler arası çalışmalar yapılmaktadır. Ancak okuma eğitimi, konuşma eğitimi, yazma eğitimi, dinleme eğitimi, dil bilgisi öğretimi, ilkokuma ve yazma öğretimi, çocuk edebiyatı, Türkçe

  13. Bir Arka Plan Olarak Servet-i Fünun’da Pozitivizm As To A Background The Positivism In The Servet-i Fünun

    Directory of Open Access Journals (Sweden)

    Mehmet ÖZGER

    2013-03-01

    Full Text Available The Tanzimat in the Turkish literature is a breaking point periodand also can be said this emerging era is a "breaking literature". Someinnovations began during this period, and so in the period of the ServetiFünun artists’ reaches maturity level. Innovation, not just new speciesinto Turkish literature or looking at the issue is to underestimate thechange of existing species.With Innovation, the point of view of Ottomanintellectuals and artists change regarding existence. From the time ofwhen we met new types and concepts. Existing perception ofmetaphysical leaves its place to mind and senses. But the mind andsenses are the basic elements of positivism. The positivistunderstanding has been substituted its art theory and practical worksof art without metaphysics.The Servet-i Fünun literature, mainly are evaluated aroundthemes of to escape from reality and take shelter in dream. This is,apparently, place their position in a somewhere except positivism.However, in this period the basic structure of the poetry will be seeingthat are shaped by the mind and senses. This is, suggests that theServet-i Fünun poetry point of occurrence is positivism.The Servet-i Fünun artists had a positivist approach in the fieldof novel, fiction as a chess game, and they seen as an experiment thebasic structure of giving direction to people. Individuals in novels, actsin accordance with a certain genetic code. Place in novels, is reducedfrom the large places to the narrow places. This is like chessboardstructure, in the plotline the action is reduced but the reason whichgiving individual’s directions had been focus.In this article, will be discussed the positivism in the Servet-iFünun literature. In a sense, this artistic production style is likened to agame of chess, the Servet-i Fünun literature is very closely linked withthe perception of being existence. Türk edebiyatında Tanzimat, bir kırılma dönemidir bu dönemde ortaya çıkan edebiyata

  14. 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.

  15. Mobbingin Örgütsel Sinizme Etkisi: Beş Yıldızlı Otel İşletmelerinde Bir Uygulama

    OpenAIRE

    Ayduğan, Nil

    2012-01-01

    Önemli örgütsel sorun türlerinden olan mobbing ve örgütsel sinizmin emek-yoğun bir özellik gösteren sektör-işletmelerde daha fazla oranda ortaya çıkma ihtimali, bu işletmeleri-işletme türlerini, konuyla ilgili daha fazla bilinçli olmaya, önlem almaya zorlamaktadır. Bu doğrultuda gerçekleştirilen bu araştırmada, önemli bir hizmet işletme türü olan beş yıldızlı otel işletmeleri işgörenlerinin mobbing algılarının örgütsel sinizme etkisinin belirlenmesi amaçlanmış olup, bu doğrultuda mobbing ve ...

  16. 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.

  17. Test reactor technology

    International Nuclear Information System (INIS)

    The Reactor Development Program created a need for engineering testing of fuels and materials. The Engineering Test Reactors were developed around the world in response to this demand. The design of the test reactors proved to be different from that of power reactors, carrying the fuel elements closer to the threshold of failure, requiring more responsive instrumentation, more rapid control element action, and inherent self-limiting behavior under accident conditions. The design of the experimental facilities to exploit these reactors evolved a new, specialized, branch of engineering, requiring a very high-lvel scientific and engineering team, established a meticulous concern with reliability, the provision for recovery from their own failures, and detailed attention to possible interactions with the test reactors. This paper presents this technology commencing with the Materials Testing Reactor (MTR) through the Fast Flux Test Facility, some of the unique experimental facilities developed to exploit them, but discusses only cursorily the experiments performed, since sample preparation and sample analyses were, and to some extent still are, either classified or proprietary. The Nuclear Engineering literature is filled with this information

  18. Kitle İletişiminde Çağdaş Söylen Üretimi: Kuramsal Bir Değerlendirme

    Directory of Open Access Journals (Sweden)

    Birol Demircan

    2015-08-01

    Full Text Available Söylenler, iktidarın uygulamalarının rasyonelleştirilmesi ve meşrulaştırılması ile toplumsal bir iletişim gerçekleşmesine hala kaynaklık etmektedir. Bu amaçla çalışmada, kitle iletişimi ile dolayımlanan söylenler aracılığıyla yaratılan karizmatik otoriter öznelerin oluşturulma süreci üzerinde durulmuştur. Kitle iletişimin sahte doğallığı ile toplumun gerçekliğini çarpıttığı iddiası bu çalışmanın incelemek istediği temel sorundur. Bu doğrultuda, kitle iletişim ve mitoloji arasında kavramsal ilişki kurarak mitolojinin meşrulaştırma işlevinin izlerini kitle iletişim süreçlerinde aranmıştır. Kitle iletişim araçları ile dolayımlanan iletişim biçimleri ile söylenlerin oluşturulduğunu ve bu söylenlerin iktidar ilişkileri içerisinde bir meşrulaştırma işlevini yerine getirdiği savunulmuştur. Bu savunu doğrultusunda, kullanılan propaganda teknikleri ile özellikle politik liderlerin kahramanlaştırılmasında etkin bir söylen kullanımının varlığı amaçlı örneklem yöntemi ile seçilen örnekler üzerinden tartışılmıştır. Böylelikle, medya ve söylen üretimi arasındaki bağ kurulmak istenmiştir.  Özellikle, kahramanlık mitinin haber dilinde ideolojik belirlenimle üretilmesi sürecinde örtük bir çabanın varlığı tespit edilmiştir. Sonuç olarak, kitle iletişimi ile dolayımlanan söylenler aracılığıyla yaratılan karizmatik otoritenin dönemsel iktidar ilişkileri içersinde en çok rıza gösterilen sistemik bir efsane insan haline geldiği açıklanmıştır.

  19. Fast Breeder Reactor studies

    International Nuclear Information System (INIS)

    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

  20. 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.

  1. Licensed operating reactors

    International Nuclear Information System (INIS)

    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

  2. nuclear reactor design calculations

    International Nuclear Information System (INIS)

    In this work , the sensitivity of different reactor calculation methods, and the effect of different assumptions and/or approximation are evaluated . A new concept named error map is developed to determine the relative importance of different factors affecting the accuracy of calculations. To achieve this goal a generalized, multigroup, multi dimension code UAR-DEPLETION is developed to calculate the spatial distribution of neutron flux, effective multiplication factor and the spatial composition of a reactor core for a period of time and for specified reactor operating conditions. The code also investigates the fuel management strategies and policies for the entire fuel cycle to meet the constraints of material and operating limitations

  3. Course on reactor physics

    International Nuclear Information System (INIS)

    In Germany only few students graduate in nuclear technology, therefore the NPP operating companies are forced to develop their own education and training concepts. AREVA NP has started together with the Technical University of Dresden a one-week course ''reactor physics'' that includes the know-how of the nuclear power plant construction company. The Technical University of Dresden has the training reactor AKR-2 that is retrofitted by modern digital instrumentation and control technology that allows the practical training of reactor control.

  4. PWR type reactor

    International Nuclear Information System (INIS)

    From a PWR with a primary circuit, consisting of a reactor pressure vessel, a steam generator and a reactor coolant pump, hot coolant is removed by means of an auxiliary system containing h.p. pumps for feeding water into the primary circuit and being connected with a pipe, originating at the upper part, which has got at least one isolating value. This is done by opening an outlet in a part of the auxiliary system that has got a lower pressure than the reactor vessel. Preferably a water jet pump is used for mixing with the water of the auxiliary system. (orig.)

  5. Microfluidic electrochemical reactors

    Science.gov (United States)

    Nuzzo, Ralph G.; Mitrovski, Svetlana M.

    2011-03-22

    A microfluidic electrochemical reactor includes an electrode and one or more microfluidic channels on the electrode, where the microfluidic channels are covered with a membrane containing a gas permeable polymer. The distance between the electrode and the membrane is less than 500 micrometers. The microfluidic electrochemical reactor can provide for increased reaction rates in electrochemical reactions using a gaseous reactant, as compared to conventional electrochemical cells. Microfluidic electrochemical reactors can be incorporated into devices for applications such as fuel cells, electrochemical analysis, microfluidic actuation, pH gradient formation.

  6. Gurbet Türkülerine Arketipsel Bir Yaklaşım An Archetypal Approach To Homesick Songs

    Directory of Open Access Journals (Sweden)

    Meriç HARMANCI

    2013-07-01

    bilinmeyen bir parçası olan ve Jung’un tanımıyla ortak bilinçaltında yatıp bize çok derinlerden seslenen ruhsal davranış biçimleri olan arketipler edebi eserlerin pek çoğunun temelinde yer aldığı gibi türkülerde de derin olarak hissedilir. Gurbet türküleri; sevdiklerinden, daha önce yaşadığı mekânlardan, alışkınlıklarından uzakta kalan gurbetçinin ve onun arkasında bıraktıklarının ruh halini yansıtması bakımından bilinçaltının dışavurumu olarak değerlendirebilir. Gurbetin yarattığı ayrılık ve özlemin yanı sıra sosyolojik, ekonomik ve diğer çeşitli zorluklarla baskı altında alınıp bilinçaltına gönderilen türlü duyguların söze dökülmesiyle oluşan gurbet türküleri aynı zamanda bireyin kahramanlaşma sürecini anlatan yol hikâyelerini de bünyesinde barındırır.Campell tarafından “Ayrılma-Erginlenme-Dönüş” şeklinde basamaklandırılan bireyselleşme yolculuğu ekseninde türkü metinleri değerlendirildiğinde mitten masala, destandan halk hikâyesine kadar pek çok anlatı türünde görülen bu yolcuğun bir benzerine rastlanır. Bu benzerlik, uzun soluklu zaman veya mekân değişimine rağmen destan ya da masal zamanlarında ya da modern zamanlarda bireyin karşılaştığı duygu ve durumların aslında arketipsel olarak aynı olduğunu göstermektedir. Türküler taşıdığı sosyal ve estetik değerin yanında geçirdiği uzun yolculuk dolayısıyla bireyin ve toplumun mitik arka planına ışık tutar.Bu makale kapsamında insanoğlunun mitik yolculuğunda ona eşlik eden sosyal donanımlardan biri olarak türküler psikanalitik çözümleme yöntemiyle anlamlandırılmaya çalışılacaktır. Makalede, türkü metinlerinin kılavuzluğunda kahramanlık mitosuna uygun düşen psikanalitik ögeler üzerinde durulacak ve kahramanın ayrılık evresi ile başlayan ve karşılaştığı güçlüklerle mücadelesiyle devam eden mitik yolculuğun türkü formu üzerindeki izd

  7. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    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

  8. NEUTRONIC REACTOR FUEL COMPOSITION

    Science.gov (United States)

    Thurber, W.C.

    1961-01-10

    Uranium-aluminum alloys in which boron is homogeneously dispersed by adding it as a nickel boride are described. These compositions have particular utility as fuels for neutronic reactors, boron being present as a burnable poison.

  9. Pulsed fusion reactors

    International Nuclear Information System (INIS)

    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

  10. 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.

  11. 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.

  12. Reactor Neutrino Spectra

    CERN Document Server

    Hayes, A C

    2016-01-01

    We present a review of the antineutrino spectra emitted from reactors. Knowledge of these and their associated uncertainties are crucial for neutrino oscillation studies. The spectra used to-date have been determined by either conversion of measured electron spectra to antineutrino spectra or by summing over all of the thousands of transitions that makeup the spectra using modern databases as input. The uncertainties in the subdominant corrections to beta-decay plague both methods, and we provide estimates of these uncertainties. Improving on current knowledge of the antineutrino spectra from reactors will require new experiments. Such experiments would also address the so-called reactor neutrino anomaly and the possible origin of the shoulder observed in the antineutrino spectra measured in recent high-statistics reactor neutrino experiments.

  13. Experience with Kamini reactor

    International Nuclear Information System (INIS)

    Kamini is a 233U fuelled, 30 kW(th) research reactor. It is one of the best neutron source facility with a core average flux of 1012 n/cm2/s in IGCAR used for neutron radiography of active and nonradioactive objects, activation analysis and radiation physics research. The core consists of nine plate type fuel elements with a total fuel inventory of 590 g of 233U. Two safety control plates made of cadmium are used for start up and shutdown of the reactor. Three beam tubes, two-thimble irradiation site outside reflector and one irradiation site nearer to the core constitute the testing facilities of Kamini. Kamini attained first criticality on 29th October 96 and nominal power of 30 kW in September 1997. This paper covers the design features of the reactor, irradiation facilities and their utilities and operating experience of the reactor. (author)

  14. Reactor pressure boundary materials

    International Nuclear Information System (INIS)

    With a long-term operation of nuclear power plants, the component materials are degraded under severe reactor conditions such as neutron irradiation, high temperature, high pressure and corrosive environment. It is necessary to establish the reliable and practical technologies for improving and developing the component materials and for evaluating the mechanical properties. Especially, it is very important to investigate the technologies for reactor pressure boundary materials such as reactor vessel and pipings in accordance with their critical roles. Therefore, this study was focused on developing and advancing the microstructural/micro-mechanical evaluation technologies, and on evaluating the neutron irradiation characteristics and radiation effects analysis technology of the reactor pressure boundary materials, and also on establishing a basis of nuclear material property database

  15. 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.

  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. Special lecture on nuclear reactor

    International Nuclear Information System (INIS)

    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.

  18. Kâh Kahvehane Kâh Café: Küreselleşen Eskişehir’de Kahve Tüketimi Üzerine Kuramsal Bir Giriş

    OpenAIRE

    Akarçay, Erhan

    2014-01-01

    Bu çalışmada kahve, kahvehaneler ve caféler tüketim, tüketim sosyolojisive küreselleşme/küreyerelleşme tartışmaları ekseninde, orta ölçekli bir kent olanEskişehir özelinde Starbucks örneğinde kuramsal olarak tartışılmaktadır. Kahveüretim, tüketim ve bölüşüm ilişkilerine sahip önemli bir tüketim maddesidir.Kahve ve kahvehane Doğu kültürü ile özdeşleştirilmiş, kahvehaneler Osmanlı’dangünümüze insanları bir araya getiren sohbet ile bezenmiş bir toplumsallaşmapratiği ve mekânı olarak işlev görmüş...

  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. Kuran'ın Dili ve Anlatım Üslûbu Üzerine Bir Deneme / An Essay on Language and Speech Style of the Koran

    OpenAIRE

    GÜVEN, Dr. Mustafa

    2011-01-01

    Kur'an, son ilahî bir kitap olarak, hem akla hitap ediyor, hem de ortaya koyduğu akıl formatına uygun bir dil ve üslûp kullanıyor. Böylece okuyucu, Kur'an okurken, hem kendi doğru akıl ve mantığına göre bir metin ile tanışıyor hem de doğru ve evrensel bir akıl formatı ile karşılaşıyor. Zaten Kuran'ın hedefi de, insanları doğ-ru düşünmek, doğru akıl ve mantık yürütmek ve böylece iki dünya saadeti elde etmelerini sağlamaktır. Bu makalede, Kuran'ın beyan ve üslûbunda ortaya koyduğu aklîlik üzeri...

  1. Jet-Stirred Reactors

    OpenAIRE

    Herbinet, Olivier; Guillaume, Dayma

    2013-01-01

    The jet-stirred reactor is a type of ideal continuously stirred-tank reactor which is well suited for gas phase kinetic studies. It is mainly used to study the oxidation and the pyrolysis of hydrocarbon and oxygenated fuels. These studies consist in recording the evolution of the conversion of the reactants and of the mole fractions of reaction products as a function of different parameters such as reaction temperature, residence time, pressure and composition of the inlet gas. Gas chromatogr...

  2. Generation IV reactors: economics

    International Nuclear Information System (INIS)

    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.)

  3. OECD Halden reactor project

    International Nuclear Information System (INIS)

    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

  4. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    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)

  5. 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....

  6. Moon base reactor system

    Science.gov (United States)

    Chavez, H.; Flores, J.; Nguyen, M.; Carsen, K.

    1989-01-01

    The objective of our reactor design is to supply a lunar-based research facility with 20 MW(e). The fundamental layout of this lunar-based system includes the reactor, power conversion devices, and a radiator. The additional aim of this reactor is a longevity of 12 to 15 years. The reactor is a liquid metal fast breeder that has a breeding ratio very close to 1.0. The geometry of the core is cylindrical. The metallic fuel rods are of beryllium oxide enriched with varying degrees of uranium, with a beryllium core reflector. The liquid metal coolant chosen was natural lithium. After the liquid metal coolant leaves the reactor, it goes directly into the power conversion devices. The power conversion devices are Stirling engines. The heated coolant acts as a hot reservoir to the device. It then enters the radiator to be cooled and reenters the Stirling engine acting as a cold reservoir. The engines' operating fluid is helium, a highly conductive gas. These Stirling engines are hermetically sealed. Although natural lithium produces a lower breeding ratio, it does have a larger temperature range than sodium. It is also corrosive to steel. This is why the container material must be carefully chosen. One option is to use an expensive alloy of cerbium and zirconium. The radiator must be made of a highly conductive material whose melting point temperature is not exceeded in the reactor and whose structural strength can withstand meteor showers.

  7. BWR type nuclear reactor

    International Nuclear Information System (INIS)

    Purpose: To simplify the structure of an emergency core cooling system while suppressing the flow out of coolants upon rapture accidents in a coolant recycling device of BWR type reactors. Constitution: Recirculation pumps are located at a position higher than the reactor core in a pressure vessel, and the lower plenum is bisected vertically by a partition plate. Further, a gas-liquid separator is surrounded with a wall and the water level at the outer side of the wall is made higher than the water level in the inside of the wall. In this structure, coolants are introduced from the upper chamber in the lower plenum into the reactor core, and the steams generated in the reactor core are separated in the gas-liquid separator, whereby the separated liquid is introduced as coolants by way of the inner chamber into the lower chamber of the lower plenum and further sent by way of the outer chamber into the reactor core. Consequently, idle rotation of the recycling pumps due to the flow-in of saturated water is prevented and loss of coolants in the reactor core can also be prevented upon raptures in the pipeway and the driving section of the pump connected to the pressure vessel and in the bottom of the pressure vessel. (Horiuchi, T.)

  8. OECD Halden reactor project

    International Nuclear Information System (INIS)

    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

  9. 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

  10. 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.

  11. Reactor physics and economic aspects of the CANDU reactor system

    International Nuclear Information System (INIS)

    A history of the development of the CANDU system is given along with a fairly detailed description of the 600 MW(e) CANDU reactor. Reactor physics calculation methods are described, as well as comparisons between calculated reactor physics parameters and those measured in research and power reactors. An examination of the economics of CANDU in the Ontario Hydro system and a comparison between fossil fuelled and light water reactors is presented. Some physics, economics and resources aspects are given for both low enriched uranium and thorium-fuelled CANDU reactors. Finally the RβD program in Advanced Fuel Cycles is briefly described

  12. Reactor Safety Planning for Prometheus Project, for Naval Reactors Information

    Energy Technology Data Exchange (ETDEWEB)

    P. Delmolino

    2005-05-06

    The purpose of this letter is to submit to Naval Reactors the initial plan for the Prometheus project Reactor Safety work. The Prometheus project is currently developing plans for cold physics experiments and reactor prototype tests. These tests and facilities may require safety analysis and siting support. In addition to the ground facilities, the flight reactor units will require unique analyses to evaluate the risk to the public from normal operations and credible accident conditions. This letter outlines major safety documents that will be submitted with estimated deliverable dates. Included in this planning is the reactor servicing documentation and shipping analysis that will be submitted to Naval Reactors.

  13. Fast breeder reactor research

    International Nuclear Information System (INIS)

    Full text: The meeting was attended by 15 participants from seven countries and two international organizations. The Eighth Annual Meeting of the International Working Group on Fast Reactors (IWGFR) was attended by representatives from France, Fed. Rep. Germany, Italy, Japan, United Kingdom, Union of Soviet Socialist Republics and the United States of America - countries that have made significant progress in developing the technology and physics of sodium cooled fast reactors and have extensive national programmes in this field - as well as by representatives of the Commission of the European Communities and the IAEA. The design of fast-reactor power plants is a more difficult task than developing facilities with thermal reactors. Different reactor kinetics and dynamics, a hard neutron spectrum, larger integral doses of fuel and structural material irradiation, higher core temperatures, the use of an essentially novel coolant, and, as a result of all these factors, the additional reliability and safety requirements that are imposed on the planning and operation of sodium cooled fast reactors - all these factors pose problems that can be solved comprehensively only by countries with a high level of scientific and technical development. The exchange of experience between these countries and their combined efforts in solving the fundamental problems that arise in planning, constructing and operating fast reactors are promoting technical progress and reducing the relative expenditure required for various studies on developing and introducing commercial fast reactors. For this reason, the meeting concentrated on reviewing and discussing national fast reactor programmes. The situation with regard to planning, constructing and operating fast experimental and demonstration reactors in the countries concerned, the experience accumulated in operating them, the difficulties arising during operation and ways of over-coming them, the search for optimal designs for the power

  14. The Analytic Hierarchy Process (AHP and an Application: The Selection of a Library Director as a Leader Analitik Hiyerarşi Süreci (AHS ve Bir Uygulama: Lider bir Kütüphane Müdürü Seçimi

    Directory of Open Access Journals (Sweden)

    Murat Yılmaz

    2010-06-01

    Full Text Available The librarians have to take various decisions to deal with the problems met in library and information centers. Before having made the decisions, the librarians should firstly define the problem with all details. If the librarians have clear information about the relevant problem, they can easily define and solve it. But the problems met by librarians in library and information centers sometimes may have a complex and an unclear structure. The librarians need a powerful method to deal with such a problem having a complex and an unclear structure. This method may be Analytic Hierarchy Process (AHP. The main purpose of this study is to explain how to use the AHP. Furthermore, in this study it is also explained how to select a library director as a leader. Kütüphane ve bilgi merkezlerinde karşılaşılan problemlerin üstesinden gelmek için kütüphaneciler, çeşitli kararlar almak zorundadır. Karar vermek için kütüphanecilerin öncelikle problemi tanımlaması gerekir. Kütüphanecilerin problemle ilgili net verilere sahip olmaları söz konusu problemin tanımlanmasını ve çözümünü kolaylaştırır. Fakat kütüphanecilerin kütüphane ve bilgi merkezlerinde karşılaştıkları sorunlara ilişkin veriler bazen karmaşık ve belirsiz bir yapıda olabilir. Kütüphanecilerin karmaşık ve belirsiz bir yapıya sahip bu tür problemlerin üstesinden gelmeleri için güçlü bir yöntemden yararlanması gerekir. Bu yöntem, Analitik Hiyerarşi Süreci (AHS olabilir. Bu araştırmanın temel amacı, AHS yönteminden nasıl yararlanılacağını açıklamaktır. Araştırmamızda ayrıca AHS yöntemiyle lider bir kütüphane müdürünün nasıl seçileceği de açıklanmıştır.

  15. BR2 Reactor: Introduction

    International Nuclear Information System (INIS)

    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 3He, 6Li 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

  16. Scaleable, High Efficiency Microchannel Sabatier Reactor Project

    Data.gov (United States)

    National Aeronautics and Space Administration — A Microchannel Sabatier Reactor System (MSRS) consisting of cross connected arrays of isothermal or graded temperature reactors is proposed. The reactor array...

  17. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Shimizu, Takeshi; Iida, Masaaki; Moriki, Yasuyuki

    1994-10-18

    A reactor core is divided into a plurality of coolants flowrate regions, and electromagnetic pumps exclusively used for each of the flowrate regions are disposed to distribute coolants flowrates in the reactor core. Further, the flowrate of each of the electromagnetic pumps is automatically controlled depending on signals from a temperature detector disposed at the exit of the reactor core, so that the flowrate of the region can be controlled optimally depending on the burning of reactor core fuels. Then, the electromagnetic pumps disposed for every divided region are controlled respectively, so that the coolants flowrate distribution suitable to each of the regions can be attained. Margin for fuel design is decreased, fuels are used effectively, as well as an operation efficiency can be improved. Moreover, since the electromagnetic pump has less flow resistance compared with a mechanical type pump, and flow resistance of the reactor core flowrate control mechanism is eliminated, greater circulating flowrate can be ensured after occurrence of accident in a natural convection using a buoyancy of coolants utilizable for after-heat removal as a driving force. (N.H.).

  18. Reactor coolant cleanup facility

    International Nuclear Information System (INIS)

    A depressurization device is disposed in pipelines upstream of recycling pumps of a reactor coolant cleanup facility to reduce a pressure between the pressurization device and the recycling pump at the downstream, thereby enabling high pressure coolant injection from other systems by way of the recycling pumps. Upon emergency, the recycling pumps of the coolant cleanup facility can be used in common to an emergency reactor core cooling facility and a reactor shutdown facility. Since existent pumps of the emergency reactor core cooling facility and the reactor shutdown facility which are usually in a stand-by state can be removed, operation confirmation test and maintenance for equipments in both of facilities can be saved, so that maintenance and reliability of the plant are improved and burdens on operators can also be mitigated. Moreover, low pressure design can be adopted for a non-regenerative heat exchanger and recycling coolant pumps, which enables to improve the reliability and economical property due to reduction of possibility of leakage. (N.H.)

  19. EBT reactor analysis

    International Nuclear Information System (INIS)

    This report summarizes the results of a recent ELMO Bumpy Torus (EBT) reactor study that includes ring and core plasma properties with consistent treatment of coupled ring-core stability criteria and power balance requirements. The principal finding is that constraints imposed by these coupling and other physics and technology considerations permit a broad operating window for reactor design optimization. Within this operating window, physics and engineering systems analysis and cost sensitivity studies indicate that reactors with approx. 6 to 10%, P approx. 1200 to 1700 MW(e), wall loading approx. 1.0 to 2.5 MW/m2, and recirculating power fraction (including ring-sustaining power and all other reactors auxiliaries) approx. 10 to 15% are possible. A number of concept improvements are also proposed that are found to offer the potential for further improvement of the reactor size and parameters. These include, but are not limited to, the use of: (1) supplementary coils or noncircular mirror coils to improve magnetic geometry and reduce size, (2) energetic ion rings to improve ring power requirements, (3) positive potential to enhance confinement and reduce size, and (4) profile control to improve stability and overall fusion power density

  20. Generalities about nuclear reactors

    International Nuclear Information System (INIS)

    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)

  1. 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.

  2. GAA Triplet Tekrar Artışı İle Tanısı Doğrulanan Bir Friedreich Ataksisi Olgusu

    OpenAIRE

    Alper, Gülay

    1999-01-01

    Friedreich ataksisi otozomal resesif geçişli nörodejeneratif bir hastalıktır ve herediter ataksiler arasında en sık görülenidir Hastalığın başlangıç yaşı ve klinik bulgular değişkenlik gösterebilir Anormal genin kromozom 9 a lokalize edilmesinden sonra atipik olguların tanısının olanaklı hale gelmesiyle Friedreich ataksisinin klinik spektrumu genişlemiştir Bu yazıda 7 yaşından itibaren ilerleyici yürüme güçlüğü olan klinik bulguları ile Friedreich ataksisi tanısı konan ve GAA tekrar sayısı 10...

  3. A review on entrepreneurship education in TurkeyTürkiye’de girişimcilik eğitimi üzerine bir inceleme

    Directory of Open Access Journals (Sweden)

    Şefik Özdemir

    2016-01-01

    Full Text Available Entrepreneurship education is one of the fastest growing areas in the world. One of the main reasons is the assumption that entrepreneurship education plays an important role in solving the chronic challenges such as employment, economic growth, poverty via developing entrepreneurship. Entrepreneurship education is given to develop entrepreneurship in many countries which are trying to eliminate these problems. It is one of the most curious subject whether entrepreneurial education contributes to entrepreneurial activities. Therefore, in many studies it has been tried to explain the connection between entrepreneurship education and entrepreneurial activity. In our study, we conducted a literature review on the relationship between entrepreneurship education and entrepreneurial activities. Following the literature review, some proposals have been developed by comparison the studies abroad with the studies in Turkey.   Özet Girişimcilik eğitimi dünya genelinde en hızlı büyüyen alanlardan bir tanesidir. Bunun temel nedenleri arasında girişimcilik eğitiminin girişimciliği geliştirerek istihdam, ekonomik büyüme, yoksulluk gibi kronikleşen önemli sorunların çözümünde önemli rol oynadığı düşüncesidir. Bu problemleri bertaraf etmeye çalışan birçok ülkede girişimciliği geliştirmek için girişimcilik eğitimi verilmektedir. Verilen girişimcilik eğitimlerinin girişimcilik faaliyetlerine katkı verip vermediği en çok merak edilen konulardan birisidir. Bu nedenle yapılan birçok çalışmada, girişimcilik eğitimi ve girişimcilik faaliyetlerinin arasındaki bağlantıyı anlamaya çalışmıştır. Çalışmamızda girişimcilik eğitimi ve girişimcilik faaliyetleri arasındaki bağlantı ile ilgili bir literatür taraması yapılmıştır. Literatür taraması sonucunda, yurt dışında yapılan çalışmalar ile Türkiye’de yapılan çalışmalar kıyaslanarak öneriler geliştirilmiştir.

  4. Yeni bir insansız hava aracının (SUAVi) mekanik ve aerodinamik tasarımı

    OpenAIRE

    Çetinsoy, Ertuğrul; Cetinsoy, Ertugrul; ÖNER, Kaan Taha; Oner, Kaan Taha; Kandemir, İlyas; Kandemir, Ilyas; Akşit, Mahmut Faruk; Aksit, Mahmut Faruk; Ünel, Mustafa; Unel, Mustafa; GÜLEZ, Kayhan; Gulez, Kayhan

    2008-01-01

    Bu çalısmada, dört-döner rotoru ile helikopter gibi dikine kalkıs ve inis yapabilen aynı zamanda da uçak gibi uzun menzil yatay uçus yeteneğine sahip yeni bir insansız otonom hava aracının mekanik ve aerodinamik tasarımı anlatılmıstır. Ayrıca, donanım seçimi sırasında yapılan deneyler ve sonuçları, aerodinamik ve mekanik tasarım tasarım süreci içinde yapılan sonlu elemanlar analizlerinin sonuçları da sunulmustur. Yapılan hesaplar öngörüldüğü üzere tasarlanan insansız h...

  5. Yeni bir insansız hava aracının (SUAVİ) prototip üretimi ve algılayıcı-eyleyici entegrasyonu

    OpenAIRE

    Çetinsoy, Ertuğrul; Cetinsoy, Ertugrul; Sırımoğlu, Efe; Sirimoglu, Efe; ÖNER, Kaan Taha; Oner, Kaan Taha; Ayken, Taylan; Hançer, Cevdet; Hancer, Cevdet; Ünel, Mustafa; Unel, Mustafa; Akşit, Mahmut Faruk; Aksit, Mahmut Faruk; Kandemir, İ.; Kandemir, I.

    2009-01-01

    Bu çalısmada, dört-döner rotoru ile helikopter gibi dikine kalkıs ve inis yapabilen aynı zamanda da uçak gibi uzun menzil yatay uçus yeteneğine sahip yeni bir insansız otonom hava aracının mekanik ve aerodinamik tasarımı, karbon kompozit imalatı, algılayıcı eyleyici sistem entegrasyonu ve uçus deneyleri anlatılmıstır. Gelistirilen sistem ve içinde kullanılan algılayıcı eyleyici entegrasyonunun basarımı benzetim ve deneylerle doğrulanmıstır.

  6. Yükseköğretimde Psikolojik Taciz Olgusuna İlişkin Bir Örnek Olay İncelemesi

    OpenAIRE

    GÖK, Sibel; KARATUNA, Işıl

    2012-01-01

    Mobbing veya duygusal taciz gibi terimlerle de adlandırılan işyerinde psikolojik taciz olgusu, uzun süreli ve tekrar eden rahatsız edici tutum ve davranışların, hedef alınan kişi ya da kişilere karşı sergilendiği bir süreci ifade etmektedir. Bireysel ve/veya örgütsel çeşitli faktörlere bağlı olarak ortaya çıkan psikolojik taciz, gizli, anlaşılması zor ve anlamsız birtakım olumsuz davranışların sergilenmesi ile başlamaktadır. Taciz sürecinin ilerleyen dönemlerinde, bu olumsuz davranışlar gitti...

  7. İşletmelerin Kurumsal Sosyal Sorumluluk Faaliyetleri: Kayseri İli’nde Bir Uygulama / Corporate Social Responsibility Applications of Businesses: An Empirical Study in Kayseri

    OpenAIRE

    Cingöz, Ayşe; Akdoğan, A. Asuman

    2013-01-01

    Öz: Kurumsal sosyal sorumluluk, bir işletmenin paydaşlarına karşı olan ekonomik, yasal,ahlaki ve gönüllü sorumluluklarını yerine getirmesidir. Finansal performansı olumlu yöndeetkilemesi ve paydaş tatminini artırması, konuyu işletmeler açısından önemli kılmıştır. Bukapsamda, yapılan çalışmanın temel amacı, işletmeler açısından oldukça kritik olan bu konuyuteorik açıdan inceleyerek, konunun Kayseri İli Organize Sanayi Bölges...

  8. Étude par biréfringence d'écoulement de solutions semi-diluées de polymères.

    OpenAIRE

    COSTEUX, Stéphane

    1999-01-01

    Les solutions semidiluées de polymères sont aujourd'hui utilisées dans nombre d'applications industrielles qui nécessitent des fluides relativement visqueux qui fluidifient sous cisaillement, comme dans l'industrie alimentaire ou pour la récupération assistée du pétrole. Afin d'obtenir les propriétés rhéologiques désirées, il est primordial de comprendre quels mécanismes microscopiques en sont à l’origine. La biréfringence d'écoulement est de ce point de vue une technique intéressante, puisqu...

  9. Mimic of OSU research reactor

    International Nuclear Information System (INIS)

    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

  10. Methanation assembly using multiple reactors

    Science.gov (United States)

    Jahnke, Fred C.; Parab, Sanjay C.

    2007-07-24

    A methanation assembly for use with a water supply and a gas supply containing gas to be methanated in which a reactor assembly has a plurality of methanation reactors each for methanating gas input to the assembly and a gas delivery and cooling assembly adapted to deliver gas from the gas supply to each of said methanation reactors and to combine water from the water supply with the output of each methanation reactor being conveyed to a next methanation reactor and carry the mixture to such next methanation reactor.

  11. MINT research reactor safety program

    Energy Technology Data Exchange (ETDEWEB)

    Mohamad Idris bin Taib [Division of Special Project, Malaysian Institute for Nuclear Technology Research (MINT), Bangi (Malaysia)

    2000-11-01

    Malaysian Institute for Nuclear Technology Research (MINT) Research Reactor Safety Program has been done along with Reactor Power Upgrading Project, Reactor Safety Upgrading Project and Development of Expert System for On-Line Nuclear Process Control Project. From 1993 up to date, Neutronic and Thermal-hydraulics analysis, Probabilistic Safety Assessment as well as installation of New 2 MW Secondary Cooling System were done. Installations of New Reactor Building Ventilation System, Reactor Monitoring System, Updating of Safety Analysis Report and Upgrading Primary Cooling System are in progress. For future activities, Reactor Modeling will be included to add present activities. (author)

  12. 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.

  13. Thermionic Reactor Design Studies

    Energy Technology Data Exchange (ETDEWEB)

    Schock, Alfred

    1994-08-01

    Paper presented at the 29th IECEC in Monterey, CA in August 1994. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their (thermionic reactor) performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling.

  14. International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    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

  15. Licensed operating reactors

    International Nuclear Information System (INIS)

    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. Licensed operating reactors

    International Nuclear Information System (INIS)

    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

  17. Licensed operating reactors

    International Nuclear Information System (INIS)

    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

  18. Reactor safety equipments

    International Nuclear Information System (INIS)

    Purpose: To positively recover radioactive substances discharged in a dry well at the time of failure of a reactor. Constitution: In addition to the emergency gas treating system fitted to a reactor building, a purification system connected through a pipeline to the dry well is arranged in the reactor building. This purification system is connected through pipes fitted to the dry well to forced circulation device, heat exchanger, and purification device. The atmosphere of high pressure steam gases in the dry well is derived to the heat exchanger for cooling, and then radioactive substances which are contained in the gases are removed by filter sets charged with the HEPA filters and the HECA filters. At last, there gases are returned to dry well by circulation pump, repeat this process. (Kamimura, M.)

  19. Licensed operating reactors

    International Nuclear Information System (INIS)

    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

  20. Welding and reactor safety

    International Nuclear Information System (INIS)

    The high safety requirements which must be demanded of the quality of the welded joints in reactor technique have so far not been fulfilled in all cases. The errors occuring have caused considerable loss of availability and high material costs. They were not, however, so serious that one need have feared any immediate danger to the personnel or to the environment. The safety devices of reactor plants were only called upon in a few cases and to these they responded perfectly. The intensive efforts to complete and improve the specifications are to contribute to that in future, the reactor plants can be counted even more so as one of the safest technical plants ever. (orig./LH)

  1. Backfitting swimming pool reactors

    International Nuclear Information System (INIS)

    Calculations based on measurements in a critical assembly, and experiments to disclose fuel element surface temperatures in case of accidents like stopping of primary coolant flow during full power operation, have shown that the power of the swimming pool type research reactor FRG-2 (15 MW, operating since 1967) might be raised to 21 MW within the present rules of science and technology, without major alterations of the pool buildings and the cooling systems. A backfitting program is carried through to adjust the reactor control systems of FRG-2 and FRG-1 (5 MW, housed in the same reactor hall) to the present safety rules and recommendations, to ensure FRG-2 operation at 21 MW for the next decade. (author)

  2. Reactor operation experience

    International Nuclear Information System (INIS)

    Since the TRIGA Users Conference in Helsinki 1970 the TRIGA reactor Vienna was in operation without any larger undesired shutdown. The integrated thermal power production by August 15 1972 accumulated to 110 MWd. The TRIGA reactor is manly used for training of students, for scientific courses and research work. Cooperation with industry increased in the last two years either in form of research or in performing training courses. Close cooperation is also maintained with the IAEA, samples are irradiated and courses on various fields are arranged. Maintenance work was performed on the heat exchanger and to replace the shim rod magnet. With the view on the future power upgrading nine fuel elements type 110 have been ordered recently. Experiments, performed currently on the reactor are presented in details

  3. The MNSR reactor

    International Nuclear Information System (INIS)

    This tank-in-pool reactor is based on the same design concept as the Canadian Slowpoke. The core is a right circular cylinder, 24 cm diameter by 25 cm long, containing 411 fuel pin positions. The pins are HEU-Aluminium alloy, 0.5 cm in diameter. Critical mass is about 900 g. The reactor has a single cadmium control rod. The back-up shutdown system is the insertion of a cadmium capsule in a core position. Excess reactivity is limited to 3.5mk. In both the MNSR and Slowpoke, the insertion of the maximum excess reactivity results in a power transient limited by the coolant/moderator temperature to safe values, independent of any operator action. This reactor is used primarily in training and neutron activation analysis. Up to 64 elements have been analyzed in a great variety of different disciplines. (author)

  4. 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.

  5. Fusion reactor materials

    International Nuclear Information System (INIS)

    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

  6. Safety systems of heavy water reactors and small power reactors

    International Nuclear Information System (INIS)

    After introductional descriptions of heavy water reactors and natural circulation boiling water reactors the safety philosophy and safety systems like ECCS, residual heat removal, protection systems etc., are described. (RW)

  7. An archaeological data assessment of Persian ethnicity in LydiaLydia’da Pers etnisitesine ait arkeolojik bir veri değerlendirmesi

    Directory of Open Access Journals (Sweden)

    Hatice Kalkan

    2014-04-01

    ğerlendirilmektedir.Gömü hediyesi olarak iki lekythos, bir bronz Akhaimenid kâsenin saptandığı buluntu grubunun bu bölgede geç dönemde varlığından haberdar olduğumuz Pers etnisitesi açısından anlamı sorgulanmaktadır. 2014 yılında Ödemiş Müze Müdürlüğü tarafından yapılan Beydağ tümülüs kazılarında da parçalar halindeki benzer bir lahitle birlikte ele geçirilmiş  Akhaimenid kâseler bu alanda olası bir Anahita bağlantılı ölü kült geleneğinin araştırılmasını gerektirmiştir. Benzer bir durumun Nif Dağı araştırmalarında da ortaya çıkmış olması ve kontekstlerden gömü beraberinde bu kase tipinin ele geçmesi ön görümüzü güçlendirmektedir. Bölgedeki Hellenistik ve Roma Dönemlerinde var olan Pers etnisitesinin yazıt, sikke ve antik kaynaklardaki kanıtları bilinmektedir. Bunun  yanı sıra materyal kültür açısından  burada konu edilen yeni izlerin gömü geleneklerinde  takip edilebilmesi, Pers etkisinin başka bir yansıması olarak önem taşımaktadır. Anahita inancının Akhaimenid dönemden Roma dönemine kadar sürmüş olan popülerliği, burada sadece “Lydialı İranlılar” değil tüm yerli ve Romalı nüfus üzerinde etki yaratmış görünmektedir. Ancak Pers nüfusunun mevcudiyeti büyük ölçüde Anahita inanç ve kült pratikleri ile ilişkilidir. Bu nedenle Akhaimenid kültürünün en bilinen kültik formu phialelerin ise zaman zaman gömüler beraberinde ele geçiyor olmasının Hellenistik Dönemde özellikle Pers etnisitesinin belirlenmesinde güçlü bir arkeolojik veri olduğu göz önünde tutulmalıdır.

  8. AREVA's nuclear reactors portfolio

    International Nuclear Information System (INIS)

    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)

  9. 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.

  10. Mehmed Enisî Yalkı’nın Alman Ruhu Adlı Seyahatnamesine İmgebilimsel Bir Yaklaşım An Imagologist Approach To Mehmet Enisi Yalkı's Travelbook

    Directory of Open Access Journals (Sweden)

    Yılmaz DAŞCIOĞLU

    2012-12-01

    Full Text Available The period of second constitutional is very important in terms of providing transition between Reorganization and Republic period. Besides this, it is a pioneer period in that it encloses determinants which play an important role in bulding a new national identity. It is a clear fact that literary works take a crucial assignment in creation of a new national identity. In this respect, to asses that some literary works published during second contitutional had very important functions to build up western-type turkish identity which was systematized later by Republic period would not be wrong. In this research, one of abroad travelbook after second constitutional is scrutinized, using imagology as a method. Mehmed Enisi Yalkı, jounalist and writer from the time ofconstitutional, proposes German/Germany model in order to build up a newnation, a western type Turk, in his travelbook Alman Ruhu which is still nottranscripted from Arabic Alphabet to Latin. This model is analysed in terms ofimagery. Being resound as a background, the exclamations such as work like aGerman, immovable like a German, fortify your spirit like a German, run afterjustice like a German are the signs of proposing Germany as a model. At theend of research it is determined that ottoman intellectuals who experienced thecrisis of building a new nation wrote travelbook to educate and direct society, topresent an alternative life or culture for it rather than literary concern duringthe time from Reorganization to Republic. II. Meşrutiyet dönemi, Tanzimat ile Cumhuriyet arasındaki geçişi sağlaması yönüyle son derece önemli bir evre olduğu gibi, yeni bir ulusun kimliğinin oluşumunda rol oynayan etkenleri barındırması yönüyle de öncü bir dönemdir. Bir ulusun kimliğinin oluşmasında edebiyat eserlerinin çok önemli bir görev üstlendiği açık bir gerçektir. Bu bağlamda II. Meşrutiyet dönemi gibi kritik bir zaman zarfında ortaya konan kimi edebi eserlerin

  11. Reactor Materials Research

    International Nuclear Information System (INIS)

    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

  12. Nuclear reactor simulator

    International Nuclear Information System (INIS)

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

  13. Diagnostics for hybrid reactors

    International Nuclear Information System (INIS)

    The Hybrid Reactor(HR) can be considered an attractive actinide-burner or a fusion assisted transmutation for destruction of transuranic(TRU) nuclear waste. The hybrid reactor has two important subsystems: the tokamak neutron source and the blanket which includes a fuel zone where the TRU are placed and a tritium breeding zone. The diagnostic system for a HR must be as simple and robust as possible to monitor and control the plasma scenario, guarantee the protection of the machine and monitor the transmutation.

  14. Small mirror fusion reactors

    International Nuclear Information System (INIS)

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

  15. Reactor neutron dosimetry

    International Nuclear Information System (INIS)

    An analysis of requirements and possibilities for experimental neutron spectrum determination during the reactor pressure vessel surveil lance programme is given. Fast neutron spectrum and neutron dose rate were measured in the Fast neutron irradiation facility of our TRIGA reactor. It was shown that the facility can be used for calibration of neutron dosimeters and for irradiation of samples sensitive to neutron radiation. The investigation of the unfolding algorithm ITER was continued. Based on this investigations are two specialized unfolding program packages ITERAD and ITERGS written this year. They are able to unfold data from activation detectors and NaI(T1) gamma spectrometer respectively

  16. Perspectives on reactor safety

    International Nuclear Information System (INIS)

    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. 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.

  18. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    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)

  19. 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.

  20. Reactor gamma spectrometry: status

    International Nuclear Information System (INIS)

    Current work is described for Compton Recoil Gamma-Ray Spectrometry including developments in experimental technique as well as recent reactor spectrometry measurements. The current status of the method is described concerning gamma spectromoetry probe design and response characteristics. Emphasis is given to gamma spectrometry work in US LWR and BR programs. Gamma spectrometry in BR environments are outlined by focussing on start-up plans for the Fast Test Reactor (FTR). Gamma spectrometry results are presented for a LWR pressure vessel mockup in the Poolside Critical Assembly (PCA) at Oak Ridge National Laboratory

  1. 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.

  2. Risk prevention during reactor shutdown

    International Nuclear Information System (INIS)

    During reactor shutdown potential risks are issued of a number of maintenance operations. In this text we analyse these operations and give the modifications of technical specifications to ameliorate the reactor safety. 4 figs

  3. Power calibrations for TRIGA reactors

    International Nuclear Information System (INIS)

    The purpose of this paper is to establish a framework for the calorimetric power calibration of TRIGA reactors so that reliable results can be obtained with a precision better than ± 5%. Careful application of the same procedures has produced power calibration results that have been reproducible to ± 1.5%. The procedures are equally applicable to the Mark I, Mark II and Mark III reactors as well as to reactors having much larger reactor tanks and to TRIGA reactors capable of forced cooling up to 3 MW in some cases and 15 MW in another case. In the case of forced cooled TRIGA reactors, the calorimetric power calibration is applicable in the natural convection mode for these reactors using exactly the same procedures as are discussed below for the smaller TRIGA reactors (< 2 MW)

  4. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    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)

  5. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    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

  6. 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.

  7. 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...

  8. Estetik Bir Öğe Olarak Sinemada Ses Tasarımı Ve Örnek Bir Film Çözümlemesi Sound Design As An Aesthetical Element In Cinema And An Example Of A Film Analysis

    Directory of Open Access Journals (Sweden)

    Mustafa SÖZEN

    2013-09-01

    Full Text Available It is a well-known fact that the image itself, even in a film having the simplest story, does not provide enough message. Due to a spesific aesthetic predication of audio phonemena, the films, right from the beginning, started to be shown in accompany with sound. The soundelement in cinematography which produces the semantic expression asa parlance by means of images and sounds has its own ways of use.The sound universe of cinematography is composed of dialogs, effectsand music each having different ontologies. In today’s cinematography,all these three elements were given in. For all that, in some filmsproduced for certain aesthetic considerations and in limited numbersthe usage of effects and music are avoided. Looking at the elementsmaking up the universe of sound in a film from the perspective ofessential functions it is seen that the dialogs are used to provideinformation, effects to create a real spatial and temporal feeling, andmusic to conceive the ambiance required by narrative. By doing so,matching the sounds in harmony with images is achieved and so theenhancement of the narrative’s reality illusion is expected. Somedirectors on the other hand, by pushing the sound out of its basicfunctions, rendering images and sounds contrary oppose this approachgo in search of producing different and new meanings. This studyinvestigates the how the sound universe design of the film “Deli DeliOlma” directed by Murat Saracoğlu, as an aesthetic element ismanipulated. In analysis, sound universe has been assesed either bystructural or dramatic functional dimensions. En basit öyküye sahip bir filmde bile sadece görüntülerin yeteri kadar ileti sağlamadığı bilinen bir gerçekliktir. Ses olgusunun kendine özgü estetik bir yükleme sahip oluşundan ötürü, sinemanın ilk anlarından itibaren filmler ses eşliğinde gösterilmeye başlanmıştır. Bir dil olarak anlamsal ifadeyi görüntü ve sesler aracılığıyla üreten sinemada ses

  9. 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)

  10. Reactor safety in Eastern Europe

    International Nuclear Information System (INIS)

    The papers presented to the GRS colloquium refer to the cooperative activities for reactor accident analysis and modification of the GRS computer codes for their application to reactors of the Russian design types of WWER or RBMK. Another topic is the safety of RBMK reactors in particular, and the current status of investigations and studies addressing the containment of unit 4 of the Chernobyl reactor station. All papers are indexed separately in report GRS--117. (HP)

  11. Fast reactor programme

    International Nuclear Information System (INIS)

    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.)

  12. Thermal Reactor Safety

    International Nuclear Information System (INIS)

    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

  13. NEUTRONIC REACTOR FUEL ELEMENT

    Science.gov (United States)

    Picklesimer, M.L.; Thurber, W.C.

    1961-01-01

    A chemically nonreactive fuel composition for incorporation in aluminum- clad, plate type fuel elements for neutronic reactors is described. The composition comprises a mixture of aluminum and uranium carbide particles, the uranium carbide particles containing at least 80 wt.% UC/sub 2/.

  14. Stabilized Spheromak Fusion Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Fowler, T

    2007-04-03

    The U.S. fusion energy program is focused on research with the potential for studying plasmas at thermonuclear temperatures, currently epitomized by the tokamak-based International Thermonuclear Experimental Reactor (ITER) but also continuing exploratory work on other plasma confinement concepts. Among the latter is the spheromak pursued on the SSPX facility at LLNL. Experiments in SSPX using electrostatic current drive by coaxial guns have now demonstrated stable spheromaks with good heat confinement, if the plasma is maintained near a Taylor state, but the anticipated high current amplification by gun injection has not yet been achieved. In future experiments and reactors, creating and maintaining a stable spheromak configuration at high magnetic field strength may require auxiliary current drive using neutral beams or RF power. Here we show that neutral beam current drive soon to be explored on SSPX could yield a compact spheromak reactor with current drive efficiency comparable to that of steady state tokamaks. Thus, while more will be learned about electrostatic current drive in coming months, results already achieved in SSPX could point to a productive parallel development path pursuing auxiliary current drive, consistent with plans to install neutral beams on SSPX in the near future. Among possible outcomes, spheromak research could also yield pulsed fusion reactors at lower capital cost than any fusion concept yet proposed.

  15. Reactors. Nuclear propulsion ships

    International Nuclear Information System (INIS)

    This article has for object the development of nuclear-powered ships and the conception of the nuclear-powered ship. The technology of the naval propulsion P.W.R. type reactor is described in the article B.N.3 141 'Nuclear Boilers ships'. (N.C.)

  16. Pressure tube type reactor

    International Nuclear Information System (INIS)

    Heretofore, a pressure tube type reactor has a problem in that the evaluation for the reactor core performance is complicate and no sufficient consideration is made for the economical property, to increase the size of a calandria tank and make the cost expensive. Then, in the present invention, the inner diameter of a pressure tube is set to greater than 50% of the lattice gap in a square lattice like arrangement, and the difference between the inner and the outer diameters of the calandria tube is set smaller than 20% of the lattice gap. Further, the inner diameter of the pressure tube is set to greater than 40% and the difference between the inner and the outer diameters of the calandria tube is set smaller than 30% of the lattice gap in a triangle lattice arrangement. Then, heavy water-to-fuel volume ratio can be determined appropriately and the value for the coolant void coefficient is made more negative side, to improve the self controllability inherent to the reactor. In particular, when 72 to 90 fuel rods are arranged per one pressure tube, the power density per one fuel rod is can be increased by about twice. Accordingly, the number of the pressure tubes can be reduced about to one-half, thereby enabling to remarkably decrease the diameter of the reactor core and to reduce the size of the calandria, which is economical. (N.H.)

  17. Fusion reactor materials

    International Nuclear Information System (INIS)

    At the Belgian Nuclear Research Centre SCK-CEN, activities related to fusion focus on environmental tolerance of opto-electronic components. The objective of this program is to contribute to the knowledge on the behaviour, during and after neutron irradiation, of fusion-reactor materials and components. The main scientific activities for 1997 are summarized

  18. Integral Fast Reactor Program

    International Nuclear Information System (INIS)

    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

  19. Nuclear reactor building

    Science.gov (United States)

    Gou, Perng-Fei; Townsend, Harold E.; Barbanti, Giancarlo

    1994-01-01

    A reactor building for enclosing a nuclear reactor includes a containment vessel having a wetwell disposed therein. The wetwell includes inner and outer walls, a floor, and a roof defining a wetwell pool and a suppression chamber disposed thereabove. The wetwell and containment vessel define a drywell surrounding the reactor. A plurality of vents are disposed in the wetwell pool in flow communication with the drywell for channeling into the wetwell pool steam released in the drywell from the reactor during a LOCA for example, for condensing the steam. A shell is disposed inside the wetwell and extends into the wetwell pool to define a dry gap devoid of wetwell water and disposed in flow communication with the suppression chamber. In a preferred embodiment, the wetwell roof is in the form of a slab disposed on spaced apart support beams which define therebetween an auxiliary chamber. The dry gap, and additionally the auxiliary chamber, provide increased volume to the suppression chamber for improving pressure margin.

  20. Studies on reactor physics

    International Nuclear Information System (INIS)

    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

  1. Nuclear power reactor physics

    International Nuclear Information System (INIS)

    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

  2. Cermet fuel reactors

    Energy Technology Data Exchange (ETDEWEB)

    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.

  3. Cermet fuel reactors

    International Nuclear Information System (INIS)

    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

  4. The Chernobyl reactor accident

    International Nuclear Information System (INIS)

    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)

  5. SRP reactor safety evolution

    International Nuclear Information System (INIS)

    The Savannah River Plant reactors have operated for over 100 reactor years without an incident of significant consequence to on or off-site personnel. The reactor safety posture incorporates a conservative, failure-tolerant design; extensive administrative controls carried out through detailed operating and emergency written procedures; and multiple engineered safety systems backed by comprehensive safety analyses, adapting through the years as operating experience, changes in reactor operational modes, equipment modernization, and experience in the nuclear power industry suggested. Independent technical reviews and audits as well as a strong organizational structure also contribute to the defense-in-depth safety posture. A complete review of safety history would discuss all of the above contributors and the interplay of roles. This report, however, is limited to evolution of the engineered safety features and some of the supporting analyses. The discussion of safety history is divided into finite periods of operating history for preservation of historical perspective and ease of understanding by the reader. Programs in progress are also included. The accident at Three Mile Island was assessed for its safety implications to SRP operation. Resulting recommendations and their current status are discussed separately at the end of the report. 16 refs., 3 figs

  6. Fusion reactor materials

    International Nuclear Information System (INIS)

    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

  7. 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.

  8. Department of reactor technology

    International Nuclear Information System (INIS)

    The activities of the Department of Reactor Technology at Risoe during 1980 are described. The work is presented in three chapters: General Information on the Department, Summary of the Department's Development during 1980, and Activities of the Department. Lists of staff, publications, computer programs, and test facilities are included. (author)

  9. The AP1000 reactor

    International Nuclear Information System (INIS)

    The design of the AP1000 reactor began 20 years ago when Westinghouse launched the AP600 reactor project. In fact by re-assessing AP600's safety margins Westinghouse realized that the its power output could be raised without putting at risk its safety standard. The AP1000 was born, it yields 1100 MWe. The main AP1000's design features is its passive safety (particularly after the Fukushima accident) and its modularity. The passive safety of the AP1000 implies: -) no humane intervention needed for 72 hours at least after the incident; -) no necessity for redundant complex safety systems. The modularity means that the plant, the reactor and other buildings are constructed from a choice of 300 modular units. These units can be built off-site and fit together on site. The modularity allows more construction activities to be led simultaneously and more chances to cope with the construction schedule. The NRC has approved the operation license for 30 years of the first AP1000 being built in the Usa (Vogtle plant in Georgia). 4 AP1000 are being built in China (Sanmen and Haiyang sites) and 6 others are planned in the Usa. Westinghouse is convinced that the AP1000's passive safety makes it more attractive. Let us not forget that Westinghouse was at the origin of the concept of pressurized water reactors, an idea adopted for half the nuclear power stations in the world and for all the plants now active in France. (A.C.)

  10. Fast reactor programme

    International Nuclear Information System (INIS)

    This progress report summarises the fast reactor research carried out at the Netherlands Energy Research Centre during the year 1981. The neutron and fission product cross sections of various isotopes have been evaluated. In the fuel performance programme, some preliminary results are given and irradiation facilities described. Creep experiments on various stainless steel components are reported

  11. Nuclear rocket engine reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lanin, Anatoly

    2013-07-01

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

  12. 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.

  13. 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.

  14. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    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

  15. Fast reactors: potential for power

    International Nuclear Information System (INIS)

    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.)

  16. Reactor physics problems on HCPWR

    International Nuclear Information System (INIS)

    Reactor physics problems on high conversion pressurized water reactors (HCPWRs) are discussed. Described in this report are outline of the HCPWR, expected accuracy for the various reactor physical qualities, and method for K-effective calculation in the resonance energy area. And requested further research problems are shown. The target value of the conversion ratio are also discussed. (author)

  17. Alternative approaches to fusion. [reactor design and reactor physics for Tokamak fusion reactors

    Science.gov (United States)

    Roth, R. J.

    1976-01-01

    The limitations of the Tokamak fusion reactor concept are discussed and various other fusion reactor concepts are considered that employ the containment of thermonuclear plasmas by magnetic fields (i.e., stellarators). Progress made in the containment of plasmas in toroidal devices is reported. Reactor design concepts are illustrated. The possibility of using fusion reactors as a power source in interplanetary space travel and electric power plants is briefly examined.

  18. Reactor vessel support system. [LMFBR

    Science.gov (United States)

    Golden, M.P.; Holley, J.C.

    1980-05-09

    A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

  19. Reactor monitoring using antineutrino detectors

    Science.gov (United States)

    Bowden, N. S.

    2011-08-01

    Nuclear reactors have served as the antineutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. Measurements made with antineutrino detectors could therefore offer an alternative means for verifying the power history and fissile inventory of a reactor as part of International Atomic Energy Agency (IAEA) and/or other reactor safeguards regimes. Several efforts to develop this monitoring technique are underway worldwide.

  20. Reactor physics activities in Japan

    International Nuclear Information System (INIS)

    This report reviews the research activity in reactor physics field in Japan during July, 1992 - July, 1993. The review was performed in the following fields : nuclear data evaluation, calculational method development, fast reactor physics, thermal reactor physics, advanced core design, fusion reactor neutronics, nuclear criticality safety, shielding, incineration of radioactive nuclear wastes, noise analysis and control and national programs. The main references were taken from journals and reports published during this period. The research committee of reactor physics is responsible for the review work. (author)

  1. Standart Türkçeye Bir Katkı: us+(uk- A Contribution To The Literary Turkish: us+(uk-

    Directory of Open Access Journals (Sweden)

    İ. Gülsel SEV

    2013-07-01

    Full Text Available A language has two dimensions namely colloquial and literary. Dialects within the colloquial language have important places. Literary language, which is static and resistant to changes, improves and gets richer with the help of dialects. The best examples of this process wereobserved during the language revolution when words, notions andterms were transferred to the literary language from with collectionsfrom dialects.The focus of the present study is the usuk- verb which means‘become wise, to get silent, to calm down’ in the dialects of Turkish.usuk- was derived with the deverbal suffix +(Ik- from the noun us‘wisdom’. Us is related both u- which means to understand and -ū whichmeans ‘to be able to, to have the power’.The suffix +(Ik- is not widely used in Turkish, there are a fewexamples such as acık-, birik-, gecik-, gözük-. However, there are manyexamples of this suffix in the historical and modern dialects.us-(uk- or with the forms in dialects as usukmak ve usuhmah hasseveral meanings such as ‘to get wise, to calm down after an offence oranger, to get silent because of astonishment, not to be able to talk, toget calm’. It is stated in the article that usuk whose implied meaningwere nor encountered in the historical dialects must be transferred tothe literary language with the meanings of ‘to get wise, to get silent andto calm down’. Besides, it is expected to take a step to increase thenumber of example verbs derived with +(Ik-, considering the examplesin the historical dialects. Dilin yazı dili ve konuşma dili olmak üzere iki yönü vardır. Konuşma dili içerisinde yer alan ağızlar apayrı bir yere sahiptir. Kolay kolay değişmeyen, durgun bir yapıya sahip olan yazı dili; canlı, gelişime ve değişime açık ağızlardan beslenerek gelişir ve zenginleşir. Bunun en güzel örneklerini dil devrimi sırasında halk ağızlarından yapılan derlemelerin, sözcük, terim ve kavram olarak yazı diline kazand

  2. Stratejik maliyet yönetimi kapsamında sürece dayalı faaliyet tabanlı maliyetleme yönteminin analizi ve bir otel işletmesinde uygulama

    OpenAIRE

    Köroğlu, Çağrı

    2012-01-01

    'Stratejik Maliyet Yönetimi Kapsamında Sürece Dayalı Faaliyet Tabanlı Maliyetleme Yönteminin Analizi ve Bir Otel İşletmesinde Uygulama' isimli bu çalışma, Marmaris'de turizm sezonunda faaliyet gösteren dört yıldızlı bir otel işletmesinde uygulanmıştır. Bu çalışmanın amacı, adı saklı tutulan bu otel işletmesinin faaliyette bulunduğu Mayıs-Ekim ayları arasında katlandığı maliyetlerin sürece dayalı faaliyet tabanlı maliyetleme yöntemiyle hesaplanmasının, geleneksel faaliyet tabanlı maliyetleme y...

  3. Bir Üniversite Müzesinde Aktif Sanat Eğitimi: Barber Enstitüsü Örneği-Active Art Education in a University Museum: The Example of the Barber Institute

    OpenAIRE

    Yalçın Wells, Şehnaz

    2014-01-01

    Özet Bu çalışmada İngiltere'de Birmingham Üniversitesi'nde bulunan Barber Güzel Sanatlar Enstitüsü Galerisi, sanat eğitimi potansiyel ve işlevi bakımından incelenmektedir. Bu temel amaca paralel olarak araştırmada müzenin tarihsel gelişimi, müze olarak sahip olduğu koleksiyonun sanatsal değeri ve müze/sanat eğitimi bağlamında yapılan faaliyetler ortaya konmaktadır. Araştırma bir kurum ve süreci herhangi bir müdahalede bulunmadan mevcut haliyle ortaya koymayı amaçladığından durum çalışması ...

  4. Eleştirel medya okuryazarlığı kapsamında çocuk odaklı haber ve programlar üzerine bir değerlendirme

    OpenAIRE

    Arslan, Hicabi

    2014-01-01

    Medya okuryazarlığının erken yaşlardan itibaren başlayarak hayat boyu geliştirilecek bir beceri olması, verilecek eğitimin de okul öncesinden başlayarak yetişkin eğitime uzanan bir sürece yayılmasını gerekli kılmaktadır. Bu nedenle eğitim kurumlarında, çocuklara, toplumla uyum içinde yaşaması ve toplumun ona sağladığı fırsatlardan yararlanabilmesi için gerekli temel davranışların kazandırılması hedeflenmektedir. Uluslararası Gazeteciler Federasyonu’nun (FIJ) 2003 yılında yayınladığı “Medya...

  5. Yükseköğretim öğrencilerinin işlevsel yazma becerilerinin geliştirilmesine yönelik bir eylem araştırması

    OpenAIRE

    Nohutçu, Ufuk

    2015-01-01

    Bireylerin üniversitelere gitme sebeplerine bakıldığında ilk sırada herhangi bir devlet kurumunda ya da özel kurum ve kuruluşlarda iş sahibi olabilmek amacı yer almaktadır. Her yıl ülkemizin farklı yerlerinden binlerce öğrenci bu amacına ulaşabilmek için üniversitelere girmektedir. Bu öğrencilerin günlük ve meslek hayatlarında onlara katkı sağlayacak olan işlevsel yazma türlerinden resmi yazışma türlerini iyi bir şekilde bilmeleri gerekmektedir. Bu amaçla hangi bölüm olursa olsun her üniversi...

  6. Türkiye'de Din Fenomenolojisine İlişkin Çeviriler Üzerine Bir Değerlendirme / An Assesment on Translation Related to the Phenomenology of Religion in Turkey

    OpenAIRE

    KUŞÇU, Yrd. Doç. Dr. Emir

    2011-01-01

    Son zamanlarda, din fenomenolojisi alanında kitap ve makalelerin çevirisinde bir artış gözlemlemekteyiz. Bu makalede, din fenomenolojisi alanında tercüme edilmiş kitap ve makaleleri ele almaya çalıştık. Fenomenologlara göre, din fenomenolojisi, anlama odaklı, karşılaştırmaya dayalıdır ve dinler arası farklılıkları hesaba katar. Ancak, Van der Leeuw, Mircea Eliade ve Cantwell Smith gibi bazı fenomenologlar, din fenomenolojisinin bir misyona sahip olduğunu ve yarı-teolojik olduğunu düşünürle...

  7. Advanced reactor experimental facilities

    International Nuclear Information System (INIS)

    For many years, the NEA has been examining advanced reactor issues and disseminating information of use to regulators, designers and researchers on safety issues and research needed. Following the recommendation of participants at an NEA workshop, a Task Group on Advanced Reactor Experimental Facilities (TAREF) was initiated with the aim of providing an overview of facilities suitable for carrying out the safety research considered necessary for gas-cooled reactors (GCRs) and sodium fast reactors (SFRs), with other reactor systems possibly being considered in a subsequent phase. The TAREF was thus created in 2008 with the following participating countries: Canada, the Czech Republic, Finland, France, Germany, Hungary, Italy, Japan, Korea and the United States. In a second stage, India provided valuable information on its experimental facilities related to SFR safety research. The study method adopted entailed first identifying high-priority safety issues that require research and then categorizing the available facilities in terms of their ability to address the safety issues. For each of the technical areas, the task members agreed on a set of safety issues requiring research and established a ranking with regard to safety relevance (high, medium, low) and the status of knowledge based on the following scale relative to full knowledge: high (100%-75%), medium (75 - 25%) and low (25-0%). Only the issues identified as being of high safety relevance and for which the state of knowledge is low or medium were included in the discussion, as these issues would likely warrant further study. For each of the safety issues, the TAREF members identified appropriate facilities, providing relevant information such as operating conditions (in- or out-of reactor), operating range, description of the test section, type of testing, instrumentation, current status and availability, and uniqueness. Based on the information collected, the task members assessed prospects and priorities

  8. Reactor simulator development. Workshop material

    International Nuclear Information System (INIS)

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

  9. Reactor water spontaneous circulation structure in reactor pressure vessel

    International Nuclear Information System (INIS)

    The gap between the inner wall of a reactor pressure vessel of a BWR type reactor and a reactor core shroud forms a down comer in which reactor water flows downwardly. A feedwater jacket to which feedwater at low temperature is supplied is disposed at the outer circumference of the pressure vessel just below a gas/water separator. The reactor water at the outer circumferential portion just below the air/water separator is cooled by the feedwater jacket, and the feedwater after cooling is supplied to the feedwater entrance disposed below the feedwater jacket by way of a feedwater introduction line to supply the feedwater to the lower portion of the down comer. This can cool the reactor water in the down comer to increase the reactor water density in the down comer thereby forming strong downward flows and promote the recycling of the reactor water as a whole. With such procedures, the reactor water can be recycled stably only by the difference of the specific gravity of the reactor water without using an internal pump. In addition, the increase of the height of the pressure vessel can be suppressed. (I.N.)

  10. Safety review, assessment and inspection on research reactors, experimental reactors, nuclear heating reactors and critical facilities

    International Nuclear Information System (INIS)

    In 1998, the NNSA organized to complete the nuclear safety review on the test loop in-reactor operation of the High-flux Engineering Experimental Reactor (HFEER) and the re-operation of the China Pulsed Reactor and the Uranium-water Criticality Facility. The NNSA conducted the nuclear safety review on the CP application of the China Experimental Fast Reactor (CEFR) and the siting of China Advanced Research Reactor (CARR), and carried out the construction supervision on HTR-10, and dealt with the event about the technological tube breakage of HWRR and other events

  11. Compact fusion reactors

    CERN Document Server

    CERN. Geneva

    2015-01-01

    Fusion research is currently to a large extent focused on tokamak (ITER) and inertial confinement (NIF) research. In addition to these large international or national efforts there are private companies performing fusion research using much smaller devices than ITER or NIF. The attempt to achieve fusion energy production through relatively small and compact devices compared to tokamaks decreases the costs and building time of the reactors and this has allowed some private companies to enter the field, like EMC2, General Fusion, Helion Energy, Lawrenceville Plasma Physics and Lockheed Martin. Some of these companies are trying to demonstrate net energy production within the next few years. If they are successful their next step is to attempt to commercialize their technology. In this presentation an overview of compact fusion reactor concepts is given.

  12. Elk River Reactor dismantling

    International Nuclear Information System (INIS)

    The dismantling program was carried out in three overlapping phases: the planning phase which included the preliminary planning and selection of the dismantling approach, the dismantling phase which included all work performed to remove the reactor facility and restore the site to its pre-reactor condition, and the closeout phase which included the final site survey and efforts necessary to terminate the AEC license and contract. Of particular interest was the use of a remotely operated plasma cutting torch to section the pressure vessel internals, the pressure vessel and the outer thermal shield, the use of explosives in removal of the biological shield and the method of establishment of the criteria for material disposal

  13. Sosyolojinin Peşinde Geçen Bir Ömür: Prof. Dr. Sami ŞENER ile Söyleşi

    Directory of Open Access Journals (Sweden)

    Mine Doğan

    2012-07-01

    Full Text Available Sosyoloji Bölümünün temel problemlerine çözüm önerileri üretmeye çalışan 3. Ulusal Sosyoloji Çalıştayı bu sene Karabük Üniversitesi Sosyoloji Bölümü tarafından düzenlendi. Çalıştayın oturum başkanlarından Sakarya Üniversitesi Bölüm Başkanı Prof. Dr Sami Şener’e, Türkiye’deki sosyoloji çalışmalarına bakışı ile sosyolojinin temel problemlerini teşhis etme ve çözüm yolları üretme konusundaki düşüncelerinin neler olduğu konusunda sorular sorduk. Sosyoloji eğitiminin kalitesini yükseltebilmek için neler yapılabileceği üzerinde konuşan ŞENER hoca: “Türk üniversitelerinde eğitim alan sosyoloji öğrencilerinin, hem pratik bir çalışma ve iş üretme yeteneğine nasıl sahip olacakları ve hem de hükümetin karşı karşıya geldiği sosyal problemlerin çözümünde neden sosyologlardan daha fazla yararlanılmadığının gün yüzüne çıkarılması için bu çalıştayların yapılması gerekmektedir” dedi. Bu konuda önemli adımlardan birini atan Prof Dr. Sami ŞENER hocamız Türkiye’deki sosyologları birleştirici bir faaliyet içerisine girerek SOSYODER’i (Sosyologlar Derneğini kurmuştur. Dernek yakın bir tarihte kurulmasına rağmen ŞENER hocanın ve çok sayıda değerli akademisyenin destekleri ile Türkiye’de sesini duyurmayı başarmıştır. The 3rd National Sociology Workshop, which tries to find answers to major problems of the Sociology Department, has been held this year by the department of sociology at Karabuk University. Some questions have been addressed to Prof. Dr. Sami Şener, the head of the department of Sociology at Sakarya University, concerning his point of view on sociology, together with identifying the basic problems in the field of sociology and then determining the ways of solutions. Having proposed the way to increase the efficiency of the quality of sociology education, Prof. Dr. Sami Sener has said: “The sociology students that

  14. Üstün Yetenekli Dijital Yerlilerin Sosyal Medya Kullanımları Üzerine Nitel Bir Çalışma

    Directory of Open Access Journals (Sweden)

    İbrahim Şamil Köroğlu

    2015-08-01

    Full Text Available Ağ neslinin yeni medya teknolojilerine ilişkin algısına ve teknolojiyi kullanma motivasyonuna ilişkin yapılan nicel çalışmalar dijital antropoloji alanına ilgi duyanlar için ufuk açıcı niteliktedir. Ağ neslinin özellikli bir grubunu teşkil eden üstün yetenekli dijital yerliler ise interneti ve mobil iletişim teknolojilerini bir dil gibi kullanabilen, içerik üretimi ve paylaşımı konusunda katılımcı, bilgi edinme, eğlenme ve sosyalleşme amacıyla birincil kaynak olarak sanal ortamı gören üstün yetenekli çocuklardır. Üstün yetenekli dijital yerlilerin sosyal medya kullanım motivasyonlarını Kullanımlar ve Doyumlar Yaklaşımı ile inceleyen bu çalışma, betimsel nitelikli tarama modelinde bir araştırmadır. Araştırma grubu, 2012-2013 eğitim yılında İstanbul Bilim ve Sanat Merkezi, Beşiktaş Bilim ve Sanat Merkezi ve Beyazıt Ford Otosan İlköğretim Okulu’nda öğrenim gören 401 üstün yetenekli öğrencidir. Grupta yer alan üstün yeteneklilerin 231’i (%57,6 9–11; 148’i (%36,9 12–14; 22’si (%5,5 ise 15–17 yaş grubundadır. Araştırmaya katılan üstün yeteneklilerin 247’si erkek (%61,6; 154’ü (%38,4 kız öğrencilerden oluşmaktadır. Çalışmada üstün yetenekli dijital yerlilerin sosyal medya kullanım sıklıkları; internet kullanım amaçları ile sosyal medya kullanım amaçları ve sık kullandıkları sosyal medya sitelerinin hangileri olduğu incelenmiştir. Çalışmada elde edilen bulgular üstün yetenekli dijital yerlilerin sosyal medya kullanım sıklığının akranlarına oranla Türkiye ortalamasının altında kaldığını; internet kullanım amaçlarıyla sosyal medya kullanım amaçlarının örtüştüğünü, ayrıca YouTube, Facebook ve Twitter’ın üstün yetenekli dijital yerlilerin en sık kullandıkları sosyal medya siteleri olduğunu ortaya koymaktadır.

  15. A problem peculiar to women: Mental health in menopauseKadına özgü bir sorun: Menopozda ruh sağlığı

    Directory of Open Access Journals (Sweden)

    Şükran Ertekin Pınar

    2015-09-01

    Full Text Available Menopause ranked among reproductive health is one of the issues that requires special consideration because of the position of women. In terms of the elimination of inequalities in gender-related health, it is important to investigate this issue in a holistic approach. Today with the increasing length of life, the time that spent in menopause period is increasing too. Accepted physiological event menopause leads to changes in physiological, mental, social and sexual ways. Changes in the levels of reproductive hormones lead to menstrual cycle disruption, vasomotor symptoms, sleep disorders and mood changes. As menopause period develops with pathological events which threaten life, impair quality of life and affect marriage relationship, it is an important period needs to be addressed by health professionals. In this context, identifying mental problems gone through in menopause period is important in terms of holistic approach. Women in menopause periods should be addressed in the biopsychosocial and cultural integrity and health professionals should determine women who are at risk of mental problems at an early stage and should provide support in a mental aspect.   Özet Üreme sağlığı içinde yer alan menopoz, kadınların konumlarından dolayı özel yaklaşım gerektiren konulardan biridir. Cinsiyete bağlı sağlıkta eşitsizlik durumunun ortadan kaldırması açısından bütüncül yaklaşım içerisinde bu konunun araştırılmış olması önemlidir. Günümüzde yaşam süresinin uzaması ile birlikte menopoz döneminde geçirilen süre de artmaktadır. Fizyolojik bir olay olarak kabul edilen menopoz kadında fizyolojik, mental, sosyal ve cinsel yönden birçok değişimler yaşanmasına neden olmaktadır. Üreme hormonlarının düzeylerindeki değişiklikler sonucu adet döngüsünde bozulma, vazomotor belirtiler, uyku bozuklukları, duygu durum değişiklikleri görülebilmektedir. Menopoz dönemi yaşamı tehdit edici, ya

  16. Türkiye'de terörle mücadelede Türk kamu yönetiminin işlevleri üzerine genel bir değerlendirme: PKK örneği

    OpenAIRE

    Taş, Davut

    2014-01-01

    Bu Yüksek Lisans Tezi'nin amacı Türkiye'nin önemli bir sorunu olarak karşımızda duran PKK ve ona karşı yapılan mücadelenin Türk kamu yönetiminin işlevleri açısından bir süreç olarak incelenmesi ve terörle mücadele ile terörizme mücadele ekseninde Türk kamu yönetimindeki değişiminin araştırılmasıdır. Temel varsayım Türk kamu yönetiminin terör ve terörizmle mücadelede bir süreç olarak terörle mücadeleden terörizmle mücadele alanına kaydığı ve bunun nedeninin değişen konjonktür, değişen PKK ve k...

  17. Örgütlerde iş tatminini etkileyen demografik faktörler ve verimlilik : Karaman gıda sektöründe bir uygulama

    OpenAIRE

    Tor, Serhat Sefa; Esengün, Kemal

    2011-01-01

    Küreselleşen günümüz dünyasında teknoloji inanılmaz bir hızla gelişmekte ve tüm dünyaya yayılmaktadır. Herkese aynı bilgiler ve teknolojiler rahatça ulaşabildiğinden, rekabet ortamı her geçen gün daha da zorlu bir hal almaya ve insan gücü çok daha fazla önem kazanmaya başlamıştır. Bu yüzden bir firmanın hayatını devam ettirmesi veya rekabette ayakta kalması için gerekli olan kâr ancak, maliyeti oluşturan kalemlerin aşağıya çekilmesi ile yapabilmektedir. Bu nedenle, işçilik maliyetlerinin üzer...

  18. KOBİ’lerde Çalışanların Mobbinge Maruz Kalma Durumları: Kırklareli İlinde Bir Araştırma

    OpenAIRE

    Keskin, Aslı; Canbaz, Serdar

    2014-01-01

    Mobbing işyerinde bir çalışanın veya grubun, diğer bir çalışana yönelttiği olumsuz istenmeyen davranışlar şeklinde açıklanan, günümüzde sıklıkla karşılaşılan ve hem bireysel hem de örgütsel düzeyde ciddi tehlike arz eden bir sorundur. Çalışmamızda öncelikle KOBİ kavramının tanımı yapılmış, mobbing kavramının tanımı, gelişimi ve hangi tür davranışların mobbing kabul edildiği ve başa çıkma yöntemleri üzerinde durulmuştur. Bu çalışmada amaç KOBİ’lerde çalışanların mobbinge maruz kalma durumların...

  19. Gösteri Dünyasında Kadın Oyunculara Yönelik Cinsiyetçi Yaklaşım ve Bir Örnek Olay: Fat Actress

    OpenAIRE

    YÜKSEL, N.Aysun

    2006-01-01

    Pek çok iş alanında olduğu üzere gösteri dünyasında da kadınlara yönelik cinsiyetçi ve eşitsiz uygulamalar söz konusudur. Kadın oyuncuların yaşları ve bedenlerindeki dönüşüm bir role tercih edilmelerinde olumsuz faktörler olarak karşılarına çıkarken erkek oyuncular için ilerlemiş yaşları ve/veya deforme olmuş bedenleri başrolde oynamak için bir sorun olmamaktadır. Bu noktadan hareketle,  anılan ayrımcılığa ilişkin Kirstie Alley'in ironik bir yaklaşıma sahip, otobiyografik özellikler de taşıya...

  20. Research Methods Used in Library and Information Science Theses: An Evaluation Kütüphanecilik ve Bilgi Bilim Tezlerinde Kullanılan Bilimsel Araştırma Yöntemleri : Bir Değerlendirme

    Directory of Open Access Journals (Sweden)

    S. Serap Kurbanoğlu

    1996-12-01

    Full Text Available A literature analysis and an evaluation are made on the findings of researches which examine the research methods employed in library science and information science dissertations. The data suggest some changes regarding to research methods used in library science dissertations. Separate examinations of library science dissertations and information science dissertations suggest that there are differences as much assimilarities between these sister disciplines. Kütüphanecilik ve bilgi bilim tezlerinde kullanılan araştırma yöntemleri konusunda yapılan araştırmaların bulguları üzerine bir literatür çalışması ve bir değerlendirme yapılmıştır. Bulgular kütüphanecilik tezlerinde kullanılan araştırma yöntemleri konusunda zaman içinde bir çeşitlenme olduğunu göstermektedir. Kütüphanecilik ve bilgi bilim tezleri üzerinde ayrı ayrı yürütülen incelemeler ise bu iki kardeş disiplin arasında benzerlikler kadar farklılıklar da olduğunu ortaya koymaktadır.

  1. REACTOR MODERATOR STRUCTURE

    Science.gov (United States)

    Greenstreet, B.L.

    1963-12-31

    A system for maintaining the alignment of moderator block structures in reactors is presented. Integral restraining grids are placed between each layer of blocks in the moderator structure, at the top of the uppermost layer, and at the bottom of the lowermost layer. Slots are provided in the top and bottom surfaces of the moderator blocks so as to provide a keying action with the grids. The grids are maintained in alignment by vertical guiding members disposed about their peripheries. (AEC)

  2. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    SCK-CEN's programme on fusion reactor materials includes studies (1) to investigate fracture mechanics of neutron-irradiated beryllium; (2) to describe the helium behaviour in irradiated beryllium at atomic scale; (3) to define the kinetics of beryllium reacting with air or steam; (3) to perform a feasibility study for the testing of integrated blanket modules under neutron irradiation. Progress and achievements in 1997 are reported

  3. Decommissioning of research reactors

    International Nuclear Information System (INIS)

    Research reactors of WWR-S type were built in countries under Soviet influence in '60, last century and consequently reached their service life. Decommissioning implies removal of all radioactive components, processing, conditioning and final disposal in full safety of all sources on site of radiological pollution. The WWR-S reactor at Bucuresti-Magurele was put into function in 1957 and operated until 1997 when it was stopped and put into conservation in view of decommissioning. Presented are three decommissioning variants: 1. Reactor shut-down for a long period (30-50 years) what would entail a substantial decrease of contamination with lower costs in dismantling, mechanical, chemical and physical processing followed by final disposal of the radioactive wastes. The drawback of this solution is the life prolongation of a non-productive nuclear unit requiring funds for personnel, control, maintenance, etc; 2. Decommissioning in a single stage what implies large funds for a immediate investment; 3. Extending the operation on a series of stages rather phased in time to allow a more convenient flow of funds and also to gather technical solutions, better than the present ones. This latter option seems to be optimal for the case of the WWR-S Research at Bucharest-Magurele Reactor. Equipment and technologies should be developed in order to ensure the technical background of the first operations of decommissioning: equipment for scarification, dismantling, dismemberment in a highly radioactive environment; cutting-to-pieces and disassembling technologies; decontamination modern technologies. Concomitantly, nuclear safety and quality assurance regulations and programmes, specific to decommissioning projects should be implemented, as well as a modern, coherent and reliable system of data acquisition, recording and storing. Also the impact of decommissioning must be thoroughly evaluated. The national team of specialists will be assisted by IAEA experts to ensure the

  4. Nuclear reactor container

    International Nuclear Information System (INIS)

    Upon reactor accident, hydrogen and oxygen are generated by water-zirconium reaction and radiolysis of water, which are accumulated in the reactor. If the concentration of hydrogen and oxygen exceeds a burning limit, there is a possibility of hydrogen burning to cause a danger of deteriorating the integrity of the reactor container and the equipments therein. The limit for the occurrence of the detonation is determined by a relationship between the scale of a detonation cell and the size of the container, and if the scale is greater than the container, the detonation does not occur. The scale of the cell is determined by a gas combustion rate and, if the combustion reaction is suppressed, detonation does not occur even in a large container. Then, an appropriate diluent is added to increase heat capacity of a gas mixture to thereby suppress the temperature elevation of the gas. Incombustible gases having a great heat capacity are preferred for the diluent, and CO2 is used. As the concentration of the CO2 gas to be added is increased, the detonation cell is made greater. Thus, occurrence of detonation due to combustion of the accumulated hydrogen can be prevented. (N.H.)

  5. Towards nuclear fusion reactors

    International Nuclear Information System (INIS)

    In the middle of 21st century, the population on the earth is expected to double, and the energy that mankind consumes to triple. The nuclear fusion which is said the ultimate energy source for mankind is expected to solve this energy problem. As for fusion reactors, fuel materials exist inexhaustibly, distributing evenly, they have high safety in principle, the product of burning is harmless nonradioactive substance that does not require the treatment and disposal, and the attenuation of induced radioactivity due to neutrons is quick and the effect to global environment is little. The basic plan of second stage nuclear fusion research and development was decided in 1975, aiming at attaining the critical plasma condition. JT-60 has attained it in 1987. The project of international thermonuclear fusion experimental reactor (ITER) was started, and the conceptual design was carried out. Under such background, the third stage basic plan was decided in 1992, and its objective is self ignition condition, long time burning and the basis of the reactor engineering technology. The engineering design of the ITER is investigated. (K.I.)

  6. High temperature gas reactor

    International Nuclear Information System (INIS)

    The present invention provides a reflector block structure of a high temperature gas reactor in which graphite blocks are not failed even a containing cylinder loaded to a fuel exchanger collides against to secured reflectors upon loading and withdrawing fuel constitutional elements. Namely, a protection plate made of a metal material such as stainless steel is covered on the secured reflector blocks disposed to the upper most step among secured graphite reflector blocks constituting the reactor core. In addition, positioning guide grooves are formed on the protection plate for guiding the containing cylinder loaded to the fuel exchanger to the column of the reactor core constitutional elements. With such a constitution, even if the containing cylinder of fuel exchanger is hoisted down and collided against the inner circumferential edge of the secured reflector blocks due to deviation of the position and the direction upon exchange of fuels, the reflector blocks are not failed since the above-mentioned portion is covered with the metal protection plate. In addition, the positioning guide grooves lead the fuel exchanger to a predetermined column correctly. (I.S.)

  7. BWR type reactor

    International Nuclear Information System (INIS)

    In a coolant circulation in BWR type reactors, since the mixed stream of steam fluid undergoes a great resistance, the pressure loss due to the flow rate distribution when the coolants flow from the upper plenum into the stand pipe is increased upon passing stand pipe. Also in the spontaneous recycling reactor, pressure loss is still left upon passing the swirling blade of a gas-liquid separator. In view of the above, a plurality of vertical members each having a lower end opened to a gas-liquid two phase boundary and an upper end directly suspended from a steam dryer to the gas-liquid separator. The liquid droplets from the 2-phase boundary heated in the reactor core and formed into a mixed gas-liquid 2-phase stream is directed in the vertical direction accompanied with the steam. The liquid droplets spontaneously fallen by gravity from greater ones successively and the droplets in the steam abutted against the vertical member are fallen as a liquid membrane. Thus, the gas-liquid separation is conducted, the dry steam is directly flown into the steam dryer, thereby capable of providing a gas-liquid separator having gas-liquid separation performance with lower loss than usual. (N.H.)

  8. Licensed operating reactors

    International Nuclear Information System (INIS)

    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. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. 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

  9. Fusion reactor safety

    International Nuclear Information System (INIS)

    Nuclear fusion could soon become a viable energy source. Work in plasma physics, fusion technology and fusion safety is progressing rapidly in a number of Member States and international collaboration continues on work aiming at the demonstration of fusion power generation. Safety of fusion reactors and technological and radiological aspects of waste management are important aspects in the development and design of fusion machines. In order to provide an international forum to review and discuss the status and the progress made since 1983 in programmes related to operational safety aspects of fusion reactors, their waste management and decommissioning concepts, the IAEA had organized the Technical Committee on ''Fusion Reactor Safety'' in Culham, 3-7 November 1986. All presentations of this meeting were divided into four sessions: 1. Statements on National-International Fusion Safety Programmes (5 papers); 2. Operation and System Safety (15 papers); 3. Waste Management and Decommissioning (5 papers); 4. Environmental Impacts (6 papers). A separate abstract was prepared for each of these 31 papers. Refs, figs, tabs

  10. Licensed operating reactors

    International Nuclear Information System (INIS)

    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. Since all of the data concerning operation of the units are provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. 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

  11. OECD Halden Reactor Project

    International Nuclear Information System (INIS)

    The OECD Halden Reactor project is an agreement between OECD member countries. It was first signed in 1958 and since then regularly renewed every third year. The activities at the Project is centred around the Halden heavy water rector, the HBWR. The reseach programme comprizes studies of fuel performance under various operating conditions, and the application of computers for process control. The HBWR is equipped for exposing fuel rods to temperatures and pressures, and at heat ratings met in modern BWR's and PWR's. A range of in-core instruments are available, permitting detailed measurements of the reactions of the fuel, including mechanical deformations, thermal behaviour, fission gas release, and corrosion. In the area of computer application, the studies of the communication between operator and process, and the surveillance and control of the reactor core, are of particular interst for reactor operation. 1988 represents the 30th year since the Project was started, and this publication is produced to mark this event. It gives and account of the activities and achievements of the Project through the years 1958-1988

  12. Bir Kültür Sosyologu: "Mehmet Eröz" Kalkınma ve Kürtçülük Meselesi

    Directory of Open Access Journals (Sweden)

    Mustafa Aksoy

    2006-11-01

    Full Text Available İsimler insanlara bazı şeyleri çağrıştırır. Mesela Fatih, İstanbul'u; Hz.Ömer, adaleti; Karacaoğlan, güzele söylenen sözleri vs. İşte Eröz'de bize "etnik mesele", "Marksist felsefenin sosyolojik tahlili", "onomastik" ve "ülkemizin kalkınma meselesi" ile "Alevilik-Bektaşilik" kavramlarını çağrıştırır. Kültürel yapımız ve bu yapının unsurları Eröz'ün kendisiyle özdeşleşmiştir. Bir bakıma o, kültürel yapımız ile kader birliği etmiştir. Bu nedenle Gökalp'in deyişiyle o, halka iki defa gitmiştir. Birincisinde kendi bilgisini götürmüş ikincisinde ise halkımızda yaşayan kültürün sosyolojik tahlilini yapmıştır. Kısa ömründe Anadolu'da saha araştırmaları yaparak incelemelerde bulunmuştur. O'nun için tatil araştırma yapmak demektir. O, ülkemizin önemli meselelerini 1960'lı yıllarda görerek çalışmalarını yoğunlaştırmıştır. Ancak ne yazık ki ömrü bazı kitap çalışmalarına yetmemiştir. Ümit ederiz ki O'nun çalışmaları genç araştırmacılara rehber olur da, bıraktığı yerden çalışmalarını devam ettirirler.

  13. Nuclear research reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias, E-mail: aplc@cdtn.b, E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

  14. Chernobyl reactor transient simulation study

    International Nuclear Information System (INIS)

    This paper deals with the Chernobyl nuclear power station transient simulation study. The Chernobyl (RBMK) reactor is a graphite moderated pressure tube type reactor. It is cooled by circulating light water that boils in the upper parts of vertical pressure tubes to produce steam. At equilibrium fuel irradiation, the RBMK reactor has a positive void reactivity coefficient. However, the fuel temperature coefficient is negative and the net effect of a power change depends upon the power level. Under normal operating conditions the net effect (power coefficient) is negative at full power and becomes positive under certain transient conditions. A series of dynamic performance transient analysis for RBMK reactor, pressurized water reactor (PWR) and fast breeder reactor (FBR) have been performed using digital simulator codes, the purpose of this transient study is to show that an accident of Chernobyl's severity does not occur in PWR or FBR nuclear power reactors. This appears from the study of the inherent, stability of RBMK, PWR and FBR under certain transient conditions. This inherent stability is related to the effect of the feed back reactivity. The power distribution stability in the graphite RBMK reactor is difficult to maintain throughout its entire life, so the reactor has an inherent instability. PWR has larger negative temperature coefficient of reactivity, therefore, the PWR by itself has a large amount of natural stability, so PWR is inherently safe. FBR has positive sodium expansion coefficient, therefore it has insufficient stability it has been concluded that PWR has safe operation than FBR and RBMK reactors

  15. United States Domestic Research Reactor Infrastructure TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    The purpose of this technical paper is to provide status of the United State domestic Research Reactor Infrastructure (RRI) Program at the Idaho National Laboratory. This paper states the purpose of the program, lists the universities operating TRIGA reactors that are supported by the program, identifies anticipated fresh fuel needs for the reactor facilities, discusses spent fuel activities associated with the program, and addresses successes and planned activities for the program. (author)

  16. Thermionic Reactor Design Studies

    Energy Technology Data Exchange (ETDEWEB)

    Schock, Alfred

    1994-06-01

    During the 1960's and early 70's the author performed extensive design studies, analyses, and tests aimed at thermionic reactor concepts that differed significantly from those pursued by other investigators. Those studies, like most others under Atomic Energy Commission (AEC and DOE) and the National Aeronautics and Space Administration (NASA) sponsorship, were terminated in the early 1970's. Some of this work was previously published, but much of it was never made available in the open literature. U.S. interest in thermionic reactors resumed in the early 80's, and was greatly intensified by reports about Soviet ground and flight tests in the late 80's. This recent interest resulted in renewed U.S. thermionic reactor development programs, primarily under Department of Defense (DOD) and Department of Energy (DOE) sponsorship. Since most current investigators have not had an opportunity to study all of the author's previous work, a review of the highlights of that work may be of value to them. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling. Where the author's concepts differed from the later Topaz-2 design was in the relative location of the emitter and the collector. Placing the fueled emitter on the outside of the cylindrical diodes permits much higher axial conductances to reduce ohmic

  17. Applications of Research Reactors

    International Nuclear Information System (INIS)

    One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.' One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property'. The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The purpose of the earlier publication, The Application of Research Reactors, IAEA-TECDOC-1234, was to present descriptions of the typical forms of research reactor use. The necessary criteria to enable an application to be performed were outlined for each one, and, in many cases, the minimum as well as the desirable requirements were given. This revision of the publication over a decade later maintains the original purpose and now specifically takes into account the changes in service requirements demanded by the relevant stakeholders. In particular, the significant improvements in

  18. Reactor technology: power conversion systems and reactor operation and maintenance

    International Nuclear Information System (INIS)

    The use of advanced fuels permits the use of coolants (organic, high pressure helium) that result in power conversion systems with good thermal efficiency and relatively low cost. Water coolant would significantly reduce thermal efficiency, while lithium and salt coolants, which have been proposed for DT reactors, will have comparable power conversion efficiencies, but will probably be significantly more expensive. Helium cooled blankets with direct gas turbine power conversion cycles can also be used with DT reactors, but activation problems will be more severe, and the portion of blanket power in the metallic structure will probably not be available for the direct cycle, because of temperature limitations. A very important potential advantage of advanced fuel reactors over DT fusion reactors is the possibility of easier blanket maintenance and reduced down time for replacement. If unexpected leaks occur, in most cases the leaking circuit can be shut off and a redundant cooling curcuit will take over the thermal load. With the D-He3 reactor, it appears practical to do this while the reactor is operating, as long as the leak is small enough not to shut down the reactor. Redundancy for Cat-D reactors has not been explored in detail, but appears feasible in principle. The idea of mobile units operating in the reactor chamber for service and maintenance of radioactive elements is explored

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

    International Nuclear Information System (INIS)

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

  20. Tourism as a paradox creative sector from socio-cultural perspective: A sociological analysis on Dalyan destinationSosyo-kültürel açıdan paradoks yaratıcı bir sektör olarak turizm: Dalyan destinasyonunda sosyolojik bir çözümleme

    Directory of Open Access Journals (Sweden)

    F. Özlem Güzel

    2013-04-01

    Full Text Available While the local people and tourists being in a confrontation is a desirable situation during the tourism activities’ which has economic income and employment creation impact, taking places on the destinations of which the starting point to be their natural and historical resources, it could emerge as a situation that creates paradoxes as well as, on the regions where the necessary socio-cultural awareness is no generated on the local people. In this context, the purpose of this study is to evaluate perceptions of locals in the scope of socio-cultural and economic in Dalyan destination towards tourists coming to this destination. Based on this aim, depth interview technique which is a qualitative research method based on the idea that it could provide more concrete data is preferred. Data, obtained from interviewed participants in the selected sample were subjected to sociological analysis. As a result of the sociological analysis the concerns of the local people especially about the socio-cultural degeneration on behaviors and movements of youths created by tourism which contributes economically in the region was observed. ÖzetDoğal ve tarihi kaynakları doğrultusunda çıkış noktası olan destinasyonlara istihdam yaratıcı etkisi ve ekonomik getirileri olan turizm faaliyetlerinin gerçeklemesi esnasında, yer aldığı bölge ve yörelerde yerel halk ve turistlerin karşı karşıya gelmesi belli beklentiler içinde istenen bir durum iken, yöre halkında gerekli bilincin oluşturulamadığı yerlerde sosyo-kültürel paradokslar yaratan bir durum olarak da ortaya çıkmaktadır. Bu bağlamda bu çalışmanın amacı, bu konu üzerinde herhangi bir araştırmaya uygulama alanı olarak seçilmeyen Dalyan yöresinde turist-yerel halk etkileşimini karşılıklı gözlemleme fırsatı yakalayabilen yerel esnafın, destinasyona gelen turistlere yönelik algılamalarını sosyo-kültürel ve ekonomik açıdan değerlendirmektir. Bu amaca

  1. The research reactor TRIGA Mainz

    International Nuclear Information System (INIS)

    Paper dwells upon the design and the operation of one of the German test reactors, namely, the TRIGA Mainz one (TRIGA: Training Research Isotope Production General Atomic). The TRIGA reactor is a pool test reactor the core of which contains a graphite reflector and is placed into 2 m diameter and 6.25 m height aluminum vessel. There are 75 fuel elements in the reactor core, and any of them contains about 36 g of 235U. The TRIGA reactors under the stable operation enjoy wide application to ensure tests and irradiation, namely: neutron activation analysis, radioisotope production, application of a neutron beam to ensure the physical, the chemical and the medical research efforts. Paper presents the reactor basic experimental program lines

  2. Spiral-shaped disinfection reactors

    KAUST Repository

    Ghaffour, Noreddine

    2015-08-20

    This disclosure includes disinfection reactors and processes for the disinfection of water. Some disinfection reactors include a body that defines an inlet, an outlet, and a spiral flow path between the inlet and the outlet, in which the body is configured to receive water and a disinfectant at the inlet such that the water is exposed to the disinfectant as the water flows through the spiral flow path. Also disclosed are processes for disinfecting water in such disinfection reactors.

  3. Industrializing the liquid metal reactor

    International Nuclear Information System (INIS)

    Commercial acceptance of the liquid metal reactor had its beginning with the Fermi reactor, over two decades ago. The pattern of industrialization since that time is discussed, contrasting domestic and foreign experience. The recent termination of the Clinch River reactor project marks a watershed in the U.S. approach towards commercialization. The increased emphasis on achieving cost competitive designs reflects an awareness that barriers to industrialization are institutional and financial, and not technological

  4. Acceptability of reactors in space

    Energy Technology Data Exchange (ETDEWEB)

    Buden, D.

    1981-04-01

    Reactors are the key to our future expansion into space. However, there has been some confusion in the public as to whether they are a safe and acceptable technology for use in space. The answer to these questions is explored. The US position is that when reactors are the preferred technical choice, that they can be used safely. In fact, it dies not appear that reactors add measurably to the risk associated with the Space Transportation System.

  5. Hydrogen Production in Fusion Reactors

    OpenAIRE

    Sudo, S.; Tomita, Y.; Yamaguchi, S.; Iiyoshi, A.; Momota, H.; Motojima, O.; Okamoto, M; Ohnishi, M.; Onozuka, M.; Uenosono, C.

    1993-01-01

    As one of methods of innovative energy production in fusion reactors without having a conventional turbine-type generator, an efficient use of radiation produced in a fusion reactor with utilizing semiconductor and supplying clean fuel in a form of hydrogen gas are studied. Taking the candidates of reactors such as a toroidal system and an open system for application of the new concepts, the expected efficiency and a concept of plant system are investigated.

  6. Fast reactor programme in India

    Indian Academy of Sciences (India)

    P Chellapandi; P R Vasudeva Rao; Prabhat Kumar

    2015-09-01

    Role of fast breeder reactor (FBR) in the Indian context has been discussed with appropriate justification. The FBR programme since 1985 till 2030 is highlighted focussing on the current status and future direction of fast breeder test reactor (FBTR), prototype fast breeder reactor (PFBR) and FBR-1 and 2. Design and technological challenges of PFBR and design and safety targets with means to achieve the same are the major highlights of this paper.

  7. Turning points in reactor design

    International Nuclear Information System (INIS)

    This article provides some historical aspects on nuclear reactor design, beginning with PWR development for Naval Propulsion and the first commercial application at Yankee Rowe. Five turning points in reactor design and some safety problems associated with them are reviewed: (1) stability of Dresden-1, (2) ECCS, (3) PRA, (4) TMI-2, and (5) advanced passive LWR designs. While the emphasis is on the thermal-hydraulic aspects, the discussion is also about reactor systems

  8. Optimal control of nuclear reactors

    International Nuclear Information System (INIS)

    The modern control theory is applied to the design of control systems for experimental nuclear reactors that do not belong to power reactors, the component forms of optimal control systems for nuclear reactors are demonstrated. The adoption of output quadratic integral criterion and incomplete state feedback technique can make these systems both efficient and economical. Moreover, approximate handling methods are given so as to simplify the calculations in design. In addition, the adoptable reference values of parameters are given in the illustration

  9. Turning points in reactor design

    Energy Technology Data Exchange (ETDEWEB)

    Beckjord, E.S.

    1995-09-01

    This article provides some historical aspects on nuclear reactor design, beginning with PWR development for Naval Propulsion and the first commercial application at Yankee Rowe. Five turning points in reactor design and some safety problems associated with them are reviewed: (1) stability of Dresden-1, (2) ECCS, (3) PRA, (4) TMI-2, and (5) advanced passive LWR designs. While the emphasis is on the thermal-hydraulic aspects, the discussion is also about reactor systems.

  10. Acceptability of reactors in space

    International Nuclear Information System (INIS)

    Reactors are the key to our future expansion into space. However, there has been some confusion in the public as to whether they are a safe and acceptable technology for use in space. The answer to these questions is explored. The US position is that when reactors are the preferred technical choice, that they can be used safely. In fact, it does not appear that reactors add measurably to the risk associated with the Space Transportation System

  11. Sosyal bilgiler dersinde bir eğitim aracı olarak sanal müze kullanımı

    OpenAIRE

    Turgut, Gülay

    2015-01-01

    Müzeler, Sosyal Bilgiler derslerinde bir eğitim ortamı olarak sık sık yararlanılan mekânlardandır. Öğrencilerin bilgiyi, gerçek nesnelerle ve kendi kurdukları ilişkilerle zihinlerinde yapılandırmalarını sağlayan çok önemli yaşantılar sağlar. Bütün yararlarına ve öğretim programlarında yer almasına rağmen müze gezilerini sık gerçekleştirmek oldukça zordur. Gelişen teknolojinin değişen müzecilik anlayışıyla buluşmasından ortaya çıkan sanal müzeler, gerçek müze gezilerinin risklerini ortadan kal...

  12. İşletme sermayesi yönetimi: mermer işletmelerine yönelik bir araştırma

    OpenAIRE

    Akın, Osman; ESER, Emine Dilek

    2014-01-01

    Finansın en önemli konularından biri olan işletme sermayesi, bir tesisin faaliyete başlayabilmesi ve faaliyetlerini sürdürebilmesi için kullanılan, kısa sürede paraya dönüşme özelliğine sahip varlıklar ve bu amaçla yapılan harcamalardır. İşletme sermayesi unsurları bilanço aktifindeki dönen varlıklardan oluşur. Bu dönen varlıkların yönetimi nakit, alacak ve stok yönetimi olarak üç ana başlık altında incelenmektedir. İşletmelerin tam kapasite ile çalışabilmeleri,üretime kesintisiz devam edebil...

  13. Mobbing'in Kişisel ve Örgütsel Etkileri Üzerine Bir Araştırma.

    OpenAIRE

    ÇAVUŞ, Yeter DEMİR Mustafa fedai

    2009-01-01

    Bu çalışmada, uygulama alanına giren işletme çalışanlarındaki çalışma stresi ve iş performansı ile mobbing (Psikolojik Yıldırma) uygulamaları arasındaki ilişkiler tespit edilmeye çalışılmıştır. Araştırmanın bulgularında, işletme çalışanlarının genel olarak psikolojik yıldırma davranışlarına maruz kalmadıkları görülmüştür. Çalışanların iş stresi ve iş performanslarının psikolojik yıldırma ile aralarında anlamlı bir ilişkinin bulunduğu saptanmıştır....

  14. Çocuk Kitaplarına Yeni Bir Yaklaşım: İnternet'te Resimli Çocuk Kitapları (e-books

    Directory of Open Access Journals (Sweden)

    Mübeccel Gönen

    2002-06-01

    Full Text Available Elektronik kitaplar (e-books yurtdışında oldukça yaygın bir biçimde kullanılmakta ve kullanıcı sayısı da giderek artmaktadır. İnternette yer alan bu kitaplar, her yaştaki insanın ilgi alanına hizmet edecek kadar çok ve çeşitlidir. Bu tür kitaplara internette yer alan kütüphanelerden, yayınevlerinden ve yazarlardan ulaşılmaktadır. Çocuk edebiyatı ile ilgili sitelerden de her konuda resimli çocuk kitaplarına ulaşılabilir. İnternette Türkçe resimli çocuk kitapları ve çocuk edebiyatı ile ilgili sitelere rastlanmamaktadır. Ancak elektronik çocuk kitaplarına yabancı sitelerden ulaşılabilir ve bazı sitelerden ücretsiz olarak da temin edilebilir. Bu yeni uygulama ile ülkemizde bulunan yayınevleri ve yazarların, iletişim ve bilgi teknolojisinden yararlanarak daha fazla aileye, okul ve çocuğa hizmet götürebileceği düşünülmektedir.

  15. Advanced Fission Reactor Program objectives

    International Nuclear Information System (INIS)

    The objective of an advanced fission reactor program should be to develop an economically attractive, safe, proliferation-resistant fission reactor. To achieve this objective, an aggressive and broad-based research and development program is needed. Preliminary work at Brookhaven National Laboratory shows that a reasonable goal for a research program would be a reactor combining as many as possible of the following features: (1) initial loading of uranium enriched to less than 15% uranium 235, (2) no handling of fuel for the full 30-year nominal core life, (3) inherent safety ensured by core physics, and (4) utilization of natural uranium at least 5 times as efficiently as light water reactors

  16. Reactor safety - an international task

    International Nuclear Information System (INIS)

    The dimensions and the significance of the task of ensuring reactor safety can be defined on the basis of experiences gained from Harrisburg and Chernobyl. The countries that use nuclear energy are tied together to a community by virtue of the risk they share. Therefore the GRS is working in close cooperation with the EC, OECD, IAEO and COMECON. This results in safety examinations of the Greifswald reactor, safety analyses of nuclear reactors in Germany, France and the USA and also considerations on the safety demands to be placed on new reactor concepts. (DG)

  17. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    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. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  18. Integrated modular water reactor: IMR

    International Nuclear Information System (INIS)

    The Mitsubishi Heavy Industries, Ltd. Has investigated on a concept on small scale reactor with economical efficiency comparable with large scale one. Aims of development on the integrated modular water reactor (IMR) of a small scale reactor plant concept consist in large construction cost reduction through adoption of technique specific to the small scale reactor and integrated production of plural units and in establishment of high safety target without reality in a large scale reactor to realize reduction of operation and maintenance costs by this reduction to simplification of operation and maintenance. Its concrete developmental targets are to make an integrated reactor with vessel size actually producible and the largest output, to remove feasibility of coolant loss accident (LOCA), to remove an accident with feasibility related to fuel fracture, to remove feasibility of nuclear reactor coolant to leak out from a storage vessel, to secure safety of plant without necessity of human and physical assistances from other plants at all on an accident, to make numbers of operators per unit output equal to those of large scale reactor, and to make working amounts at maintenance per unit output equal to large scale reactor by simplification of apparatus practice of rotation on main apparatus such as SG, and so on. Here were described on design concept and plan to realization. (G.K.)

  19. 3. Interindustry conference on reactor materials science

    International Nuclear Information System (INIS)

    This document contains abstracts on papers presented at the Third Interindustry Conference on Reactor Materials Science (Dimitrovgrad, 27-30 October 1992). The subject scope of the papers is a follows: fuel and fuel elements of power reactors; structural materials of fast breeder reactors and thermonuclear reactors; structural materials of WWER and RBMK type reactors; absorbers and moderators

  20. Helias reactor studies

    International Nuclear Information System (INIS)

    The Helias reactor is an upgraded version of the Wendelstein 7-X experiment. The magnetic field has 5 field periods and the main optimization principle is the reduction of the Pfirsch-Schlueter currents and the Shafranov shift, which has been verified by computations with the NEMEC and MFBE-codes. The modular coil system comprises 50 coils, which are constructed using NbTi-superconducting cables. The basic dimensions are: major radius 22 m, average plasma radius 1.8 m, magnetic field on axis 5 T, maximum field on the coils 10 T. Forces and stresses in the coil system have been investigated with the aid of the ANSYS code, which found maximum stress values of about 650 MPa in the coil casing. Helias configurations with 4 and 3 field periods have been constructed by starting from the 5-period case and by eliminating one or two periods while the shape of the coils is kept nearly invariant. In a first survey blanket concepts, developed for the DEMO tokamak, have been adapted to the Helias geometry, in particular, the solid breeder concept developed by FZK (Karlsruhe) has been extrapolated to the Helias geometry identifying the drawbacks and advantages of this concept. Furthermore, the liquid breeder concept using Li7-Pb83 and water-cooling is an interesting alternative for the Helias reactor. Maintenance of blanket and plasma facing components is possible through the portholes between modular coils. Numerical simulations of the start-up phase of the Helias reactor using the TOTAL-P code have confirmed the zero-dimensional modeling of the fusion plasma with the aid of empirical scaling laws. (author)

  1. Reactor coolant pump flywheel

    Science.gov (United States)

    Finegan, John Raymond; Kreke, Francis Joseph; Casamassa, John Joseph

    2013-11-26

    A flywheel for a pump, and in particular a flywheel having a number of high density segments for use in a nuclear reactor coolant pump. The flywheel includes an inner member and an outer member. A number of high density segments are provided between the inner and outer members. The high density segments may be formed from a tungsten based alloy. A preselected gap is provided between each of the number of high density segments. The gap accommodates thermal expansion of each of the number of segments and resists the hoop stress effect/keystoning of the segments.

  2. Licensed operating reactors

    International Nuclear Information System (INIS)

    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. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the errata page

  3. FUEL ASSAY REACTOR

    Science.gov (United States)

    Spinrad, B.I.; Sandmeier, H.A.; Martens, F.H.

    1962-12-25

    A reactor having maximum sensitivity to perturbations is described comprising a core consisting of a horizontally disposed, rectangular, annular fuel zone containing enriched uranium dioxide dispersed in graphite, the concentration of uranium dioxide increasing from the outside to the inside of the fuel zone, an internal reflector of graphite containing an axial test opening disposed within the fuel zone, an external graphite reflector, means for changing the neutron spectrum in the test opening, and means for measuring perturbations in the neutron flux caused by the introduction of different fuel elements into the test opening. (AEC)

  4. Shutting down two reactors

    International Nuclear Information System (INIS)

    Nuclear power will be phased out of the swedish energy system during the first decades of the next century. Commissioned by the swedish government, the National Energy Administration reports a study on the possibilities for, and consequences of, an earlier shut down (1994-1996) of two of the twelve swedish power reactors. Some of the questions studied are: How much will the electricity price raise ?; How will the electricity consumption be affected ?; What are the alternatives to nuclear power ?; What will the cost be ? and What will the environmental effects be ?. (L.E.)

  5. Measurement in nuclear reactors

    International Nuclear Information System (INIS)

    A nuclear reactor construction has a flux detector comprising a bundle of fibre optics each having a bead incorporating a substance which scintillates on being struck by neutrons or gamma radiations. The other ends of the fibre optics terminate at an image intensifier. The optical fibres may be of glass made from a mixture of silica, alkaline earth metal oxide, cerous oxide and alkali metal oxide. The beads may be incorporated in a disc forming a detector head, which is in a protective guide tube, through which an inert gas may be passed. (author)

  6. TRIGA reactor operating experience

    International Nuclear Information System (INIS)

    The Oregon State TRIGA Reactor (OSTR) has been in operation 3 years. Last August it was upgraded from 250 kW to 1000 kW. This was accomplished with little difficulty. During the 3 years of operation no major problems have been experienced. Most of the problems have been minor in nature and easily corrected. They came from lazy susan (dry bearing), Westronics Recorder (dead spots in the range), The Reg Rod Magnet Lead-in Circuit (a new type lead-in wire that does not require the lead-in cord to coil during rod withdrawal hss been delivered, much better than the original) and other small corrections

  7. Reactor system safety assurance

    International Nuclear Information System (INIS)

    The philosophy of reactor safety is that design should follow established and conservative engineering practices, there should be safety margins in all modes of plant operation, special systems should be provided for accidents, and safety systems should have redundant components. This philosophy provides ''defense in depth.'' Additionally, the safety of nuclear power plants relies on ''safety systems'' to assure acceptable response to design basis events. Operating experience has shown the need to study plant response to more frequent upset conditions and to account for the influence of operators and non-safety systems on overall performance. Defense in depth is being supplemented by risk and reliability assessment

  8. The Oklo reactors

    International Nuclear Information System (INIS)

    The Oklo reactors comprise up to nine 235-U depleted zones in an uranium ore in the Republic of Gabon in West Africa. The depletion in fissile U-235 has been proved to have caused by nuclear chain reactions. The study of the Oklo phenomenon indicates that very efficient retardation mechanisms may operate in nature - at least under special conditions. A closer study of these processes ought to be made to establish the limitations to their occurrence. The Oklo sandstone formation today would probably be considered unacceptable as a host rock for a repository. (EG)

  9. İskenderun Mezar Taşı Sözleri Üzerine Bir İnceleme A Research on İskenderun Gravestone Words

    Directory of Open Access Journals (Sweden)

    Hüseyin Kürşat TÜRKAN

    2012-12-01

    şına dikilen mezar taşlarının her biri ayrı anlam ifade etmektedir. Hemen hemen her kültürde görülen mezar taşları, ait olduğu kültürün öz değerlerine göre şekil alırlar. Bu şekillenme ölen kişinin inanışına, geleneklerine, sosyal ve ekonomik durumuna göre değişiklik gösterir. Ele alınan bu makalede Hatay’ın İskenderun ilçesinde yer alan mezar taşı sözleri üzerinde inceleme yapılarak bu sözlerin kültürel değerleri ortaya konulmaya çalışılmıştır. Sosyokültürel yaşamda toplum içindeki bireyler için kaçınılmaz bir sondur ölüm. Doğumla başlayan sürecin en son noktasıdır. Çoğu zaman üzerinde derinlemesine konuşulmaktan kaçınılan ölüm, kimi toplumlar için bir sonun başlangıcıyken kimi zaman da bir başlangıcın sonudur. İnsan hayatını böylesine derinlemesine etkileyen ölüm mefhumunda birçok ulusta olduğu gibi İslamiyeti benimseyen Türk milletinde de çeşitli ritüeller vardır. Bunların en başında şüphesiz ki ölene duyulan saygıdan dolayı ve ölünün yerinin kaybolmaması için mezarın başına dikilen taşlar gelir. Bu taşların üzerinde yer alan figür, resim ve yazıların Türk kültürünün ifadesi bakımından önemli bir yere sahip olduğu şüphesizdir.Mezar taşları tarihli olmaları ile etnografik ve sanat eserleri için birer belge hüviyeti taşırlar. Ayrıca yazılı mezar taşları Türk’ün bu topraklarda yaşadığına, varlığını ebedileştirdiğine en canlı birer şahit ve aynı zaman da estetik ve etnografik kıymetli haiz vesikalardır. Bu itibarla şehir, kaza ve köy tarihleri hazırlanırken mezar taşları önemlidir. Kısaca, mezar taşları yapıldıkları çevrenin ve devrin inançlarının, adetlerin, sanat geleneklerinin tabiî, iktisadi ve sosyal şartlarının ortak ürünüdür. Bu bakımdan sanat tarihimiz için olduğu kadar, kültür tarihimiz yönünden de büyük önem taşımaktadır (http://www.mezartaslari.com.

  10. Mevlana’nın Menkıbeleri Üzerine Folklorik Bir İnceleme A Folkloric Analysis on the Legends of Mevlana

    Directory of Open Access Journals (Sweden)

    Gülay KARAMAN

    2012-09-01

    article these topics are determined in Menâkıbu’l-Ârifîn to analysis: Places, occupations, belongings, manner of dressing, food and drinks, custom and traditions, medical treatments. Arapça bir kelime olan menkabe sözlükte övünülecek güzel iş, davranış anlamına gelmektedir. Çoğulu menâkıb olan kelime bu anlamıyla ilk defa, IX. yüzyıldan itibaren yazılıp derlenmeye başlayan hadis külliyatlarında Hz. Peygamber ve ashabının faziletlerini anlatmak için kullanılmıştır. Bundan başka tarihî şahsiyetlerin hal tercümeleri, önemli kişilerin övülecek işleri ve hatta bazı mukaddes şehirlerin tasvirinden ibaret yazılara da menâkıb denilmiştir. Başlangıçta, Hz. Peygamber ve sahabelerinin üstün ahlâkını ve yaşantılarını anlatmak üzere oluşturulan menâkıbnâmeler daha sonraları tasavvuf ve tarikat erbabının hayatlarını da konu edinmişlerdir. Türk menâkıbnâme edebiyatının bilinen ilk örneği Karahanlı dönemine ait Tezkire-i Satuk Buğra Han isimli eserdir. Tezkire-i Satuk Buğra Han’la başlayan Türk menâkıbnâme edebiyatı, göçlerle Anadolu’ya gelip yerleşen Müslüman Türkler arasında hızlı bir biçimde yayılmaya devam etmiştir. Yazar kendi toplumunun bir üyesi olduğu için doğal olarak eser de kendi çağının sosyal, kültürel ekonomik, politik yaşamına ayna olacaktır. Velilerin olağanüstü hayat hikâyelerini anlatan menâkıbnâmeler bu sebepten dolayı; özellikle tarih, kültür, halkbilimi ve edebiyat için çok önemli bilgi kaynaklarıdır. Menkıbeler üzerinde yapılacak dikkatli çalışmalar sonucunda çok zengin bir bilgi kaynağına ulaşmak mümkün olacaktır. Türkiye’de menâkıbnâmelerin bilimsel çalışmalarda kullanılmasına dikkat çeken ilk isim Türk Edebiyatında İlk Mutasavvıflar adlı eseriyle Fuad Köprülü’dür. Bu çalışmada Mevlana ve diğer Mevlevi büyüklerinin menkıbelerini anlatan bir menâkıbnâme olan Men

  11. Licensed reactor nuclear safety criteria applicable to DOE reactors

    Energy Technology Data Exchange (ETDEWEB)

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC (Nuclear Regulatory Commission) licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor.

  12. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

  13. Virtual nuclear reactor for education of nuclear reactor physics

    International Nuclear Information System (INIS)

    As one of projects that were programmed in the cultivation program for human resources in nuclear engineering sponsored by the Ministry of Economy, Trade and Industry, the development of a virtual reactor for education of nuclear reactor physics started in 2007. The purpose of the virtual nuclear reactor is to make nuclear reactor physics easily understood with aid of visualization. In the first year of this project, the neutron slowing down process was visualized. The data needed for visualization are provided by Monte Carlo calculations; The flights of the respective neutrons generated by nuclear fissions are traced through a reactor core until they disappear by neutron absorption or slow down to a thermal energy. With this visualization and an attached supplement textbook, it is expected that the learners can learn more clearly the physical implication of neutron slowing process that is mathematically described by the Boltzmann neutron transport equation. (author)

  14. Reactor Physics Analysis Models for a CANDU Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Hang Bok

    2007-10-15

    Canada deuterium uranium (CANDU) reactor physics analysis is typically performed in three steps. At first, macroscopic cross-sections of the reference lattice is produced by modeling the reference fuel channel. Secondly macroscopic cross-sections of reactivity devices in the reactor are generated. The macroscopic cross-sections of a reactivity device are calculated as incremental cross-sections by subtracting macroscopic cross-sections of a three-dimensional lattice without reactivity device from those of a three-dimensional lattice with a reactivity device. Using the macroscopic cross-sections of the reference lattice and incremental cross-sections of the reactivity devices, reactor physics calculations are performed. This report summarizes input data of typical CANDU reactor physics codes, which can be utilized for the future CANDU reactor physics analysis.

  15. Reactor system on barge

    International Nuclear Information System (INIS)

    Floating electrical power plants or power plant barges add new dimensions to utility planners and agencies in the world. Intrinsically safe and economical reactors (ISER) employ steel reactor pressure vessels, which significantly reduce the weight as compared with PIUS, and provide siting versatility including barge-mounted plants. In this paper, the outline of power plant barges and barge-mounted ISERs is described. Besides their mobility, power plant barges have the salient advantages such as short delivery time and better quality control due to the outfitting in shipyards. These power plant barges may be temporarily moored or permanently grounded in shallow water at the centers of industrial complexes or the suitable areas adjacent to them, and satisfy the increasing needs for electric power. A cost-effective and technically perfect barge positioning system should be designed to meet the specific requirement for the location and its condition. Offshore siting away from coast may be applicable only to large plants of 1,000 MWe or more, and inshore siting and coastal or river siting are considered for an ISER-200 barge-mounted plant. The system of a barge-mounted ISER plant is discussed in the case of a floating type and the type on a seismic base isolator. (Kako, I.)

  16. Tokamak experimental power reactor

    International Nuclear Information System (INIS)

    A tokamak experimental power reactor has been designed that is capable of producing net electric power over a wide range of possible operating conditions. A net production of 81 MW of electricity is expected from the design reference conditions that assume a value of 0.07 for beta-toroidal, a maximum toroidal magnetic field of 9 T and a thermal conversion efficiency of 30%. Impurity control is achieved through the use of a low-Z first wall coating. This approach allows a burn time of 60 seconds without the incorporation of a divertor. The system is cooled by a dual pressurized water/steam system that could potentially provide thermal efficiencies as high as 39%. The first surface facing the plasma is a low-Z coated water cooled panel that is attached to a 20 cm thick blanket module. The vacuum boundary is removed a total of 22 cm from the plasma, thereby minimizing the amount of radiation damage in this vital component. Consideration is given in the design to the possible use of the EPR as a materials test reactor. It is estimated that the total system could be built for less than 550 million dollars

  17. The EPR reactor NDE

    International Nuclear Information System (INIS)

    In May 2006, Electricite de France decided to launch the building of the first EPRR Reactor on the Flamanville site in Normandy. The 'Flamanville 3' EPR unit is the first one to be subjected to the French Ministerial Orders of the 10 November 1999 and of the 13 December 2005 from the design phase. According to these orders, the non destructive examination (NDE) planned for the in service inspection (ISI) and for the pre service inspection (PSI) must be operational with a compulsory formal qualification. The PSI is a complete inspection of the main primary and secondary systems. The PSI's objective is to perform before the first core loading all the NDE planned for the future ISI in the same conditions, in order to have a reliable reference for the detection or for the evaluation of the possible damages during the ISI. The 'Flamanville 3' PSI is planned to start end 2010. The program consists of the development and the qualification of the NDE compatible with this new generation reactor's challenges. The paper is about: - the main EPR's objectives and the technological evolutions, - the main component modifications (which have an impact on the NDE), - the place of ISI in the general safety demonstration, - the main inspection objectives, - the NDE qualification process, - the approach to set up the ISI program, - the ISI program. (authors)

  18. Status of Japanese university reactors

    Energy Technology Data Exchange (ETDEWEB)

    Fujita, Yoshiaki [Research Reactor Institute, Kyoto Univ., Kumatori, Osaka (Japan)

    1999-08-01

    Status of Japanese university reactors, their role and value in research and education, and the spent fuel problem are presented. Some of the reactors are now faced by severe difficulties in continuing their operation services. The point of measures to solve the difficulties is suggested. (author)

  19. Brookhaven leak reactor to close

    CERN Multimedia

    MacIlwain, C

    1999-01-01

    The DOE has announced that the High Flux Beam Reactor at Brookhaven is to close for good. Though the news was not unexpected researchers were angry the decision had been taken before the review to assess the impact of reopening the reactor had been concluded (1 page).

  20. Reactor Neutrino Physics -- An Update

    OpenAIRE

    Boehm, Felix

    1999-01-01

    We review the status and the results of reactor neutrino experiments. Long baseline oscillation experiments at Palo Verde and Chooz have provided limits for the oscillation parameters while the recently proposed Kamland experiment at a baseline of more than 100km is now in the planning stage. We also describe the status of neutrino magnetic moment experiments at reactors.

  1. Chemical-vapor-deposition reactor

    Science.gov (United States)

    Chern, S.

    1979-01-01

    Reactor utilizes multiple stacked trays compactly arranged in paths of horizontally channeled reactant gas streams. Design allows faster and more efficient deposits of film on substrates, and reduces gas and energy consumption. Lack of dead spots that trap reactive gases reduces reactor purge time.

  2. Cooling system for reactor container

    International Nuclear Information System (INIS)

    Purpose: To effectively cool a reactor container upon reactor shutdown with no intrusion of metal corrosion products in coolants into the main steam pipe in a BWR type reactor. Constitution: A clean up system comprising a pipeway, a recycling pump, a non-regenerative heat exchanger and a primary coolant purifier and a regenerative heat exchanger is provided branched from a residual heat removing system and the clean up system is connected by way of a valve to a feedwater pipeway, as well as connected by way of the pipeway to the main steam pipeway at the midway of two main steam separation valves outside of the reactor container. This enables to prevent metal corrosion products floating on the surface of reactor water from introducing into the main steam pipe when the pressure vessel is filled with water. Then, since the pressure vessel is filled with primary coolants, the pressure vessel can be cooled uniformly in a short time. (Ikeda, J.)

  3. Engineering reactors for catalytic reactions

    Indian Academy of Sciences (India)

    Vivek V Ranade

    2014-03-01

    Catalytic reactions are ubiquitous in chemical and allied industries. A homogeneous or heterogeneous catalyst which provides an alternative route of reaction with lower activation energy and better control on selectivity can make substantial impact on process viability and economics. Extensive studies have been conducted to establish sound basis for design and engineering of reactors for practising such catalytic reactions and for realizing 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 and recent advances in process intensification/ multifunctional reactors are discussed to illustrate the approach.

  4. Directions in advanced reactor technology

    International Nuclear Information System (INIS)

    Successful nuclear power plant concepts must simultaneously performance in terms of both safety and economics. To be attractive to both electric utility companies and the public, such plants must produce economical electric energy consistent with a level of safety which is acceptable to both the public and the plant owner. Programs for reactor development worldwide can be classified according to whether the reactor concept pursues improved safety or improved economic performance as the primary objective. When improved safety is the primary goal, safety enters the solution of the design problem as a constraint which restricts the set of allowed solutions. Conversely, when improved economic performance is the primary goal, it is allowed to be pursued only to an extent which is compatible with stringent safety requirements. The three major reactor coolants under consideration for future advanced reactor use are water, helium and sodium. Reactor development programs focuses upon safety and upon economics using each coolant are being pursued worldwide. These programs are discussed

  5. Simulator for materials testing reactors

    International Nuclear Information System (INIS)

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

  6. Antineutrino Monitoring of Thorium Reactors

    CERN Document Server

    Akindele, Oluwatomi A; Norman, Eric B

    2015-01-01

    Various groups have demonstrated that antineutrino monitoring can be successful in assessing the plutonium content in water-cooled nuclear reactors for nonproliferation applications. New reactor designs and concepts incorporate nontraditional fuels types and chemistry. Understanding how these properties affect the antineutrino emission from a reactor can extend the applicability of antineutrino monitoring.Thorium molten salt reactors (MSR) breed U-233, that if diverted constitute an IAEA direct use material. The antineutrino spectrum from the fission of U-233 has been determined, the feasibility of detecting the diversion of a significant quantity, 8 kg of U-233, within the IAEA timeliness goal of 30 days has been evaluated. The antineutrino emission from a thorium reactor operating under normal conditions is compared to a diversion scenario at a 25 meter standoff by evaluating the daily antineutrino count rate and the energy spectrum of the detected antineutrinos. It was found that the diversion of a signifi...

  7. Fast reactors and nuclear nonproliferation

    International Nuclear Information System (INIS)

    Problems are discussed with regard to nuclear fuel cycle resistance in fast reactors to nuclear proliferation risk due to the potential for use in military programs of the knowledge, technologies and materials gained from peaceful nuclear power applications. Advantages are addressed for fast reactors in the creation of a more reliable mode of nonproliferation in the closed nuclear fuel cycle in comparison with the existing fully open and partially closed fuel cycles of thermal reactors. Advantages and shortcomings are also discussed from the point of view of nonproliferation from the start with fast reactors using plutonium of thermal reactor spent fuel and enriched uranium fuel to the gradual transition using their own plutonium as fuel. (author)

  8. Automated reactor records evaluation framework

    International Nuclear Information System (INIS)

    The only truly reliable method for core physics code validation is comparison against experimental data – and for power nuclear reactors, the only reasonably acquirable kind of experimental data are the reactor records. However, the amount of the data coming from the reactor operation is often so vast that it can be discouraging for the code developers to use it properly. Thus, the validation package is further reduced because the data is hard to use. This paper presents an elaborate, fully automated framework, which was designed and implemented in our institute, for reactor records processing and its use for core physics code validation. The workflow, implemented as a Web 2.0 application, provides a practical and painless solution for use of reactor records data for code development and validation. (author)

  9. Strategic planning for research reactors. Guidance for reactor managers

    International Nuclear Information System (INIS)

    The purpose of this publication is to provide guidance on how to develop a strategic plan for a research reactor. The IAEA is convinced of the need for research reactors to have strategic plans and is issuing a series of publications to help owners and operators in this regard. One of these covers the applications of research reactors. That report brings together all of the current uses of research reactors and enables a reactor owner or operator to evaluate which applications might be possible with a particular facility. An analysis of research reactor capabilities is an early phase in the strategic planning process. The current document provides the rationale for a strategic plan, outlines the methodology of developing such a plan and then gives a model that may be followed. While there are many purposes for research reactor strategic plans, this report emphasizes the use of strategic planning in order to increase utilization. A number of examples are given in order to clearly illustrate this function

  10. Neutrino Experiments at Reactors

    Science.gov (United States)

    Reines, F.; Gurr, H. S.; Jenkins, T. L.; Munsee, J. H.

    1968-09-09

    A description is given of the electron-antineutrino program using a large fission reactor. A search has been made for a neutral weak interaction via the reaction (electron antineutrino + d .> p + n + electron antineutrino), the reaction (electron antineutrino + d .> n + n + e{sup +}) has now been detected, and an effort is underway to observe the elastic scattering reaction (electron antineutrino + e{sup -} .> electron antineutrino + e{sup -}) as well as to measure more precisely the reaction (electron antineutrino + p .> n + e{sup+}). The upper limit on the elastic scattering reaction which we have obtained with our large composite NaI, plastic, liquid scintillation detector is now about 50 times the predicted value.

  11. Licensed operating reactors

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission's annual summary of licensed nuclear power reactor data is based primarily on the report of operating data submitted by licensees for each unit for the month of December because that report contains data for the month of December, the year to date (in this case calendar 1990) and cumulative data, usually from the date of commercial operation. The data is not independently verified, but various computer checks are made. The report is divided into two sections. The first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 capacity and availability factors are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensee and notes as to the use of weighted averages and starting dates other than commercial operation are provided

  12. Reactor safety systems

    International Nuclear Information System (INIS)

    The spectrum of possible accidents may become characterized by the 'maximum credible accident', which will/will not happen. Similary, the performance of safety systems in a multitude of situations is sometimes simplified to 'the emergency system will/will not work' or even 'reactors are/ are not safe'. In assessing safety, one must avoid this fallacy of reducing a complicated situation to the simple black-and-white picture of yes/no. Similarly, there is a natural tendency continually to improve the safety of a system to assure that it is 'safe enough'. Any system can be made safer and there is usually some additional cost. It is important to balance the increased safety against the increased costs. (orig.)

  13. Reactor control rod

    International Nuclear Information System (INIS)

    Object: To enable quick descent of a control rod body even when some relative phase deviation between upper drive means and wrapper tube is produced, while permitting a coolant to effectively flow into a protective tube irrespective of the position of the control rod body. Structure: In a control rod used for a nuclear reactor such as a fast breeder, an orifice which dispenses with a cylindrical guide tube and has a greater inner diameter than the outer diameter of the protective tube of the control rod body is provided on the inner side of a wrapper tube, thus permitting smooth operation of the control rod body and also permitting the coolant to effectively flow into the protective tube irrespective of the control rod body. (Horiuchi, T.)

  14. Nuclear reactor spacer assembly

    International Nuclear Information System (INIS)

    A fuel assembly for a nuclear reactor is disclosed wherein the fuel element receiving and supporting grid is comprised of a first metal, the guide tubes which pass through the grid assembly are comprised of a second metal and the grid is supported on the guide tubes by means of expanded sleeves located intermediate the grid and guide tubes. The fuel assembly is fabricated by inserting the sleeves, of initial outer diameter commensurate with the guide tube outer diameters, through the holes in the grid assembly provided for the guide tubes and thereafter expanding the sleeves radially outwardly along their entire length such that the guide tubes can subsequently be passed through the sleeves. The step of radial expansion, as a result of windows provided in the sleeves having dimensions commensurate with the geometry of the grid, mechanically captures the grid and simultaneously preloads the sleeve against the grid whereby relative motion between the grid and guide tube will be precluded

  15. Nuclear reactor measurement system

    International Nuclear Information System (INIS)

    An instrument to detect the temperature and flow-rate of the liquid metal current of a coolant fluid sample from adjacent sub-assemblies of a liquid metal-cooled nuclear reactor is described. It includes three thermocouple hot junctions mounted in series, each intended for exposure to a sample-current from a single sub-assembly, electromagnetic coils being mounted around an induction core which detects variations in the liquid metal flow-rate by deformation of the lines of flux. The instrument may also include a thermocouple to detect the mean temperature of the sample-current of coolant fluid from several sources, the result being that the temperature of the coolant fluid current in a sub-assembly may be inferred from the three temperature readings associated with this sub-assembly

  16. OECD: Halden reactor project

    International Nuclear Information System (INIS)

    The work at the Project has continued in the two main fields: test fuel irradiation and fuel research, and computer based process supervision and control. Organizations participating in the Project continue to have their fuel irradiated in the Halden Reactor in instrumented test assemblies designed and manufactured by the Project. The Project's fuel studies continue to focus on specific subjects such as fuel pellet/cladding interaction and heat transfer, fission product release and fuel behavior under loss of coolant conditions. The work on process control and supervision continues in the highly relevant fields of core control and operator-process communication. A system for predictive core control is being developed while special mathematical methods for core power distribution control are being studied. Operator-process communication studies comprise use of computer simulation on colour display as important ingredients, while the work on developing a system for interactive plant disturbance analysis continues

  17. Tokamak fusion reactor exhaust

    International Nuclear Information System (INIS)

    This report presents a compilation of papers dealing with reactor exhaust which were produced as part of the TIGER Tokamak Installation for Generating Electricity study at Culham. The papers are entitled: (1) Exhaust impurity control and refuelling. (2) Consideration of the physical problems of a self-consistent exhaust and divertor system for a long burn Tokamak. (3) Possible bundle divertors for INTOR and TIGER. (4) Consideration of various magnetic divertor configurations for INTOR and TIGER. (5) A appraisal of divertor experiments. (6) Hybrid divertors on INTOR. (7) Refuelling and the scrape-off layer of INTOR. (8) Simple modelling of the scrape-off layer. (9) Power flow in the scrape-off layer. (10) A model of particle transport within the scrape-off plasma and divertor. (11) Controlled recirculation of exhaust gas from the divertor into the scrape-off plasma. (U.K.)

  18. Safety review, assessment and inspection on research reactors, experimental reactors, nuclear heating reactors and critical facilities

    International Nuclear Information System (INIS)

    The NNSA organized mainly in 1999 to complete the verification loop in core of the high flux experimental reactor with the 2000 kW fuel elements, the re-starting of China Pulsed Reactor, review and assessment on nuclear safety for the restarting of the Uranium-water critical Facility and treat the fracture event with the fuel tubes in the HWRR

  19. Power Reactors. Appendix VIII

    International Nuclear Information System (INIS)

    Decommissioning of nuclear facilities in many countries has evolved into a mature industry that has benefited from experience gained from previous projects and decommissioning costs can now be estimated to a good degree of accuracy. As a result of lessons learned, future decommissioning projects can be performed with higher levels of efficiency. Decommissioning of old power reactors is in progress in several countries. In some cases, decommissioning has been completed (i.e. plant sites have been released from regulatory control), while in other countries decommissioning is still in progress. Several large power reactors have been successfully decommissioned since 1995. The key areas of particular importance for decommissioning are decontamination, radiation protection, dismantling and demolition. The technologies which can be used for these tasks are commonly available on the market, but effective decommissioning still depends on an optimal choice of technologies, including site specific developments. It is not possible to recommend the use of a single specific technology for dismantling, demolition, segmentation or decontamination; rather, it is good practice to take into account as much information as possible from other decommissioning projects and to draw comparisons between various techniques in order to choose the one with the best performance in a particular situation. The exchange of information on all types of decommissioning experience, including decommissioning techniques and their applicability as well as disadvantages for specific tasks, is taking place on various levels, such as: — Collaborative working groups established by international organizations such as the IAEA, the OECD Nuclear Energy Agency and the European Commission and the publication of technical reports by such organizations; — National and international conferences; — Bilateral or multilateral cooperation and information exchange between organizations with responsibilities for

  20. Advanced fusion reactor

    Energy Technology Data Exchange (ETDEWEB)

    Tomita, Yukihiro [National Inst. for Fusion Science, Toki, Gifu (Japan)

    2003-04-01

    The main subjects on fusion research are now on D-T fueled fusion, mainly due to its high fusion reaction rate. However, many issues are still remained on the wall loading by the 14 MeV neutrons. In the case of D-D fueled fusion, the neutron wall loading is still remained, though the technology related to tritium breeding is not needed. The p-{sup 6}Li and p-{sup 11}B fueled fusions are not estimated to be the next generation candidate until the innovated plasma confinement technologies come in useful to achieve the high performance plasma parameters. The fusion reactor of D-{sup 3}He fuels has merits on the smaller neutron wall loading and tritium handling. However, there are difficulties on achieving the high temperature plasma more than 100 keV. Furthermore the high beta plasma is needed to decrease synchrotron radiation loss. In addition, the efficiency of the direct energy conversion from protons coming out from fusion reaction is one of the key parameters in keeping overall power balance. Therefore, open magnetic filed lines should surround the plasma column. In this paper, we outlined the design of the commercial base reactor (ARTEMIS) of 1 GW electric output power configured by D-{sup 3}He fueled FRC (Field Reversed Configuration). The ARTEMIS needs 64 kg of {sup 3}He per a year. On the other hand, 1 million tons of {sup 3}He is estimated to be in the moon. The {sup 3}He of about 10{sup 23} kg are to exist in gaseous planets such as Jupiter and Saturn. (Y. Tanaka)

  1. Chernobyl reactor accident

    International Nuclear Information System (INIS)

    Following the accident at Chernobyl nuclear reactor, WHO organized on 6 May 1986 in Copenhagen a one day consultation of experts with knowledge in the fields of meteorology, radiation protection, biological effects, reactor technology, emergency procedures, public health and psychology in order to analyse the development of events and their consequences and to provide guidance as to the needs for immediate public health action. The present report provides detailed information on the transportation and dispersion of the radioactive material in the atmosphere, especially volatile elements, during the release period 26 April - 5 May. Presented are the calculated directions and locations of the radioactive plume over Europe in the first 5 days after the accident, submitted by the Swedish Meteorological and Hydrological Institute. The calculations have been made for two heights, 1500m and 750m and the plume directions are grouped into five periods, covering five European areas. The consequences of the accident inside the USSR and the radiological consequences outside the USSR are presented including the exposure routes and the biological effects, paying particular attention to iodine-131 effects. Summarized are the first reported measured exposure rates above background, iodine-131 deposition and concentrations in milk and the remedial actions taken in various European countries. Concerning the cesium-137 problem, based on the UNSCEAR assessment of the consequences of the nuclear fallout, one concludes that the cesium contamination outside the USSR is not likely to cause any serious problems. Finally, the conclusions and the recommendations of the meeting, taking into account both the short-term and longer term considerations are presented

  2. Nuclear reactor fuelling machine

    International Nuclear Information System (INIS)

    The refuelling machine described comprises a rotatable support structure having a guide tube attached to it by a parellel linkage mechanism, whereby the guide tube can be displaced sideways from the support structure. A gripper unit is housed within the guide tube for gripping the end of a fuel assembly or other reactor component and has means for maintenance in the engaging condition during travel of the unit along the guide tube, except for a small portion of the travel at one end of the guide tube, where the inner surface of the guide tube is shaped so as to maintain the gripper unit in a disengaging condition. The gripper unit has a rotatable head, means for moving it linearly within the guide tube so that a component carried by the unit can be housed in the guide tube, and means for rotating the head of the unit through 1800 relative to its body, to effect rotation of a component carried by the unit. The means for rotating the head of the gripper unit comprises ring and pinion gearing, operable through a series of rotatable shafts interconnected by universal couplings. The reason for provision for 1800 rotation is that due to the variation in the neutron flux across the reactor core the side of a fuel assembly towards the outside of the core will be subjected to a lower neutron flux and therefore will grow less than the side of the fuel assembly towards the inside of the core. This can lead to bowing and possible jamming of the fuel assemblies. Full constructional details are given. See also BP 1112384. (U.K.)

  3. Reliability of reactor materials

    International Nuclear Information System (INIS)

    This report is the final technical report of the fracture mechanics part of the Reliability of Reactor Materials Programme, which was carried out at the Technical Research Centre of Finland (VTT) through the years 1981 to 1983. Research and development work was carried out in five major areas, viz. statistical treatment and modelling of cleavage fracture, crack arrest, ductile fracture, instrumented impact testing as well as comparison of numerical and experimental elastic-plastic fracture mechanics. In the area of cleavage fracture the critical variables affecting the fracture of steels are considered in the frames of a statistical model, so called WST-model. Comparison of fracture toughness values predicted by the model and corresponding experimental values shows excellent agreement for a variety of microstructures. different posibilities for using the model are discussed. The development work in the area of crack arrest testing was concentrated in the crack starter properties, test arrangement and computer control. A computerized elastic-plastic fracture testing method with a variety of test specimen geometries in a large temperature range was developed for a routine stage. Ductile fracture characteristics of reactor pressure vessel steel A533B and comparable weld material are given. The features of a new, patented instrumented impact tester are described. Experimental and theoretical comparisons between the new and conventional testers indicated clearly the improvements achieved with the new tester. A comparison of numerical and experimental elastic-plastic fracture mechanics capabilities at VTT was carried out. The comparison consisted of two-dimensional linear elastic as well as elastic-plastic finite element analysis of four specimen geometries and equivalent experimental tests. (author)

  4. Licensed reactor nuclear safety criteria applicable to DOE reactors

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards.

  5. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards

  6. Gözleme Dayalı Çalışmalarda Eğilim Skoru (Propensity Score ve Tıp Bilimleri'nde Bir Uygulama

    Directory of Open Access Journals (Sweden)

    Elif Çiğdem KASPAR

    2010-01-01

    Full Text Available Amaç: Gözlemsel çalışmalarda ve/veya retrospektif çalışmalarda, araştırmacının olgu ve kontrol gruplarındaki birimleri rastlantısal olarak gruplara atama işleminde kontrolü yoktur. Bu nedenle, olgu-kontrol gruplarına düşen bireylerin ortak değişkenlerinde bazı farklılıklar gözlemlenebilir ve bu farklılıklarda tedavi etkisinin yanlı (biased tahminlerine neden olabilmektedir. Bir dengeleme skoru olarak tanımlayabileceğimiz eğilim skoru (ES, tedavinin gözlenen ortak değişkenlere göre koşullu olasılığı olarak ifade edilir. ES tahmin ettikten sonra eşleştirme, tabakalara ayırma ve regresyon düzeltmesi yöntemleriyle yeniden örnekleme yapılarak retrospektif gözlemsel çalışmalarda örneklemedeki yanlılığın azaltılmasında, prospektif çalışmalardaki gibi kesinliğin artmasında, kanıt seviyesi bakımından göreli düşük olan olgu-kontrol çalışmalarının, prospektif bir çalışmanın kanıt seviyesine çıkartılması ve bazı ortak değişkenlerin etkilerini ortaya koymak amacıyla kullanılır. Çalışmamızda ES öncesi ve sonrası örneklem için olgu ve kontrol bireylerine lojistik regresyon uygulanarak risk faktörlerinin anlamlılıklarındaki farkları ortaya koymak amaçlanmıştır. Gereç ve Yöntemler: Çalışmamızda, göğüs cerrahisi ameliyatı geçirmiş n=478 hasta kullanılmıştır. Ameliyat sonrası delirium tanısı alan ve almayan hastalara ait, 24 risk faktörüne lojistik regresyon uygulanmış ve sonuçlar elde edilmiştir. ES lojistik regresyon ile hesaplanmış, tabakalara ayırma yöntemi kullanılarak oluşan yeni örneğe istatistik analiz uygulanmış ve değerlendirilmiştir. Bulgular: ES ile oluşturulmuş yeni örneklemdeki olgu ve kontrol grupları hemen hemen aynı karakteristiklere sahip olmuş ve yanlılık azalmıştır. Sonuç: ES öncesi ve sonrası örneklem için olgu ve kontrol bireylerine uygulanan lojistik regresyon sonucunda risk fakt

  7. HJ-1B/IRS水温反演模型及监测示范%A Model for Water Surface Temperature Retrieval from HJ- 1B/IRS Data and Its Application

    Institute of Scientific and Technical Information of China (English)

    黄妙芬; 毛志华; 邢旭峰; 孙中平; 赵祖龙; 黄薇

    2011-01-01

    Water surface temperature is one of the important environmental parameters at the breeding aquatics area in shore. The highly dynamic monitoring of this temperature will help to arrange aquaculture production and breeding production. Remote sensing technology is a very efficacious means for monitoring water surface temperature in high dynamic condition. At present, weather and ocean satellites which have lower spatial resolution are widely used in water surface temperature remote sensing monitoring, with the spatial resolution being 1 000 m.However, water bodies in shore are influenced by land and ocean as well as the spatial changes of water surface temperature, and hence satellites data which have higher spatial resolution are needed to meet the monitoring for water surface temperature in high dynamic condition. HJ - 1 B/IRS has a 4 - band infrared sensor (IRS). One of the bands is the thermal band which can be used to retrieve water surface temperature. In this paper, data of about ten images of HJ - 1 B/IRS thermal band obtained from 2008 to 2009 and the atmosphere measurement data at the time when the HJ - 1B satellite passed through the area were collected. Based on the monowindow algorithm and referring to the temperature product from EOS/MODIS, the authors established a model for water surface temperature retrieval from HJ - 1 B/IRS data. Moreover, a comparison was made between two retrieval methods for surface temperature from HJ - 1 B/IRS thermal band and from the temperature product by EOS/MODIS. The results show that the absolutely average temperature error from the monowindow algorithm and from the temperature product by EOS/MODIS is 7.84℃, while that from the method proposed in this paper is 0.83℃. The model for water surface temperature retrieval from HJ -1 B/IRS data established in this paper was applied in the area of Liaodong Bay for the purpose of carrying out dynamic monitoring of water surface temperature.%利用2008~2009年期间约10

  8. Information Requirements of Landscape Architects Çağdaş Bir Mesleğin Belge-Bilgi Gereksinimi: Peyzaj Mimarlığı

    Directory of Open Access Journals (Sweden)

    Oya Akkan

    1993-09-01

    Full Text Available Text of a speech given on 1 April 1993 during the Library Week . Difficulties faced by landcape architects, who do research work, in access to information have been expressed as lack of guidance on how and where to find information; limited open hours or not being able to take photocopies even if the service is open beyond office hours; lack of a thesaurus for landscape architecture to choose the right terms for an online literature search; insufficiency of the number of periodicals available in the country; lack of copying facilities for nonbook materials such as plans, slides, engravings, sound and video cassettes. Konuşmada, peyzaj mimarlarının bilgi edinme konusunda karşılaştıkları sorunlar, hangi bilginin nerede bulunduğunu saptamada karşılaşılan güçlükler, yöneltici rehber kaynakların eksikliği; kütüphane ve bilgi merkezlerinin açık olduğu saatlerin resmi çalışma saaatleri ile çakışması ya da bu saatlerin dışında açık olsalar bile fotokopi alınamaması, çevrimiçi yayın taraması yaptırabilmek için doğru anahtar sözcükleri seçmek için bir gömünün olmayışı; konuyla ilgili yeterli sayıda dergi bulunmaması; kitap dışı materyallere erişim ve kopya almada karşılaşılan güçlükler olarak dile getirilmiştir.

  9. İşitme Engelli Bir Çocuğun Okuma Yazma Becerilerinin Dil Deneyim Yaklaşımı İle Desteklenmesi

    Directory of Open Access Journals (Sweden)

    H. Pelin Karasu

    2015-01-01

    Full Text Available Dil Deneyim Yaklaşımı; dinleme, konuşma, okuma ve yazma becerilerinin bir arada kullanılması ve okuma materyallerinin öğrencilerin deneyimleriyle oluşturulması temeline dayanmaktadır. Bu araştırmanın amacı, işitme engelli bir çocuğun okuma yazma becerilerinin gelişiminin Dil Deneyim Yaklaşımı ile desteklenme sürecinin incelenmesidir. Araştırma, bu amaç doğrultusunda, eylem araştırması şeklinde desenlenmiştir. Araştırmanın katılımcıları; araştırmacı öğretmen, geçerlik komitesi üyeleri, ilkokul 2. sınıfa devam eden işitme engelli bir öğrenci ve sınıf öğretmenidir. Araştırma verileri; araştırmacı günlüğü, belgeler, görüşmeler, uygulama planları, uygulama videoteyp kayıtları ve formel olmayan değerlendirmeler kullanılarak elde edilmiştir. Araştırma bulguları, sürecin iki evrede gerçekleştiğini göstermektedir. Bu evreler; sıralı kartlardaki olayların sözlü ve yazılı dille paylaşılması ile kelime bankası ve sözdizimi etkinliğidir. Araştırma sonuçları; dil deneyim uygulamalarının sözlü dilin gelişmesi için fırsatlar sağladığını, sözel ipuçlarının kullanılmasına, düşüncelerin sözlü ve yazılı dille ifade edilmesine olanak verdiğini, sözcük dağarcığı ve sözdizimine ilişkin ihtiyaçların belirlenmesini sağlayarak öğrencinin düzeyine uygun etkinliklerin hazırlanmasına fırsat sağladığını göstermektedir.Anahtar Sözcükler: Dil deneyim yaklaşımı, okuma yazma becerileri, işitme engelli çocuk Supporting a Hearing Impaired Child’s Literacy Development With Language Experience Approach Abstract Language Experience Approach (LEA emphasizes the synergy among listening, speaking, reading and writing skills and suggests considering learners’ experiences while preparing reading materials. The aim of the current study is to investigate LEA’s supportive role in a hearing impaired child’s literacy development. In

  10. Akademisyen Ücretlerine İlişkin Karşılaştırmalı Bir Analiz A Comparative Analysis Concerned With Academic Salaries

    Directory of Open Access Journals (Sweden)

    Hilmi SÜNGÜ

    2013-09-01

    Full Text Available It is proved fact through scientific studies that the pay has adirect influence on productivity and job satisfaction at the same time.The pay gained as a result of the performance is considered asinterrelated both with the increase in the productivity and improvementin the quality of the service. It is vital for the organizational justice thatpeople who have similar statues and who are performing similar tasksshould receive balanced payments. However, the diversity of the publicservices, redundancy of people and formal institutions providing publicservices make it hard to guarantee a fair payment policy. It is observedas a result of comparative studies that academicians are one of theseoccupational groups who are profoundly affected by the injustice in thepayments. In order to remove the injustice in the formal officers’incomes and attain the defined goals for the 100th anniversary of thefoundation of the Republic within the scope of 2023 vision, talentedindividuals must be encouraged to become academicians. When acomparison made between public officials on the national basis, it isrealized that academic staff working at public universities are not ableto benefit from yearly increases as much as the other public officers andit leads for the fresh academicians to move away from academicprofession. As for the international point of view, it is stated that thepayments that the Turkish academicians get are below the average incomparison to their colleagues. In this study, current situation ofmonthly income of the academicians working at public universities inTurkey and it’s the yearly increases in the payment in time arementioned, national comparisons are made between differentprofessions together with international comparisons betweenacademicians from different countries. Ücretin verimlilik ve iş doyumuna etkisi yapılan akademik çalışmalarda ortaya konulmuş bir gerçektir. Çalışanın verimliliğinin artırılması ve

  11. Farklı Güneş Panellerinin Adaptif Bir Güneş Takip Sistemi Üzerinde Yıllık Performanslarının Karşılaştırılması ve Güç Tahmini

    OpenAIRE

    Orhun, Murat

    2013-01-01

    Bu araştırmada, 01 Mart 2012 – 28 Şubat 2013 tarihleri arasında farklı teknolojilerle üretilmiş, sabit ve hareketli platform üzerine yerleştirilmiş güneş panellerinin güneşin farklı algoritmalarla takibi durumunda performanslarının izlenmesi üzerine kapsamlı bir çalışmayı içermektedir. Çalışmada ilk olarak PLC tabanlı bir kontrol sistemi tasarlanmıştır. Tasarlanan kontrol sistemi geliştirilen bir bilgisayar yazılımı ile haberleşmektedir. Farklı güneş takip stratejileri güneş takip sistemi üze...

  12. United States Domestic Research Reactor Infrastructure TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

  13. On reactor type comparisons for the next generation of reactors

    International Nuclear Information System (INIS)

    In this paper, we present a broad comparison of studies for a selected set of parameters for different nuclear reactor types including the next generation. This serves as an overview of key parameters which provide a semi-quantitative decision basis for selecting nuclear strategies. Out of a number of advanced reactor designs of the LWR type, gas cooled type, and FBR type, currently on the drawing board, the Advanced Light Water Reactors (ALWR) seem to have some edge over other types of the next generation of reactors for the near-term application. This is based on a number of attributes related to the benefit of the vast operating experience with LWRs coupled with an estimated low risk profile, economics of scale, degree of utilization of passive systems, simplification in the plant design and layout, modular fabrication and manufacturing. 32 refs., 1 fig., 3 tabs

  14. KRONİK HİPERPLASTÎK PULPİTİS (PULPA POLİPİ) - Bir Olgu Nedeni İle CHRONIC HYPERPLASTIC PULPITIS (PULP POLYP) -A Case Report-

    OpenAIRE

    Ulukapı, Işın; Stich, Herrmann

    2012-01-01

    ÖZETKronik hipcrpiasük pulpitis (pulpa polipi) kronikBu çalışmada bir pulpa polipi plgusu histolojik olarak incelenmiştir.Anahtar sözcükler: Kronik pulpa hastalıkları, kronik hiperplastik pulpitis, pulpa polipi.ABTRACTChronic hyperplastic pulpitis (pulp polyp) is a quite uncommon form of chronic pulp disease. It occurs almost exclusively in children and young adults and involves teeth with large open carious lesions. The hyperplastic tissue is basically granulation tissue and inflammatory cel...

  15. Supplier Selection within the Process of Analytical Hierarchy in a Business Bir Üretim İşletmesinde Analitik Hiyerarşi Süreci İle Tedarikçi Seçimi

    Directory of Open Access Journals (Sweden)

    Kezban KAPAR

    2013-09-01

    Full Text Available Supplier selection is one of the most critical activities in today's competitive businessworld. Selecting the supplier is a very difficult task to carry out. For determining the bestsupplier selection while assessing all the cases to choose the best approach, the AnalyticalHierarchy Process (AHP is used.AHP is a method used for systematic comparison, evaluation and selection of theoptions via determining the strengths and weaknesses of options. In this study, AHP methodwas utilized in the supplier selection and Expert Choice 11.5 was used while utilizing AHPmethod. The suppliers' superiorities were determined by Expert Choice and they werecompared systematically.Tedarikçi seçimi, günümüz rekabetçi iş dünyasında en kritik faaliyetlerden biridir. Birtedarikçi seçiminde en iyi olanı seçmek zor bir iştir. En iyi tedarikçi seçiminin belirlenmesiiçin çok amaçlı karar verme tekniklerinden birisi olan ve alternatif tedarikçilerdeğerlendirilerek bütün durumlar içinden en iyi olanı seçebilen Analitik Hiyerarşi Süreci(AHS, tedarikçi seçiminde yaygın olarak kullanılan bir yöntemdir.AHS, seçim aşamasında seçeneklerin üstünlüklerinin belirlenmesi ve sistematik olarakkarşılaştırılıp değerlendirilmesini sağlayan bir yöntemdir. Bu çalışmada, bir işletmenintedarikçi seçiminde AHS yönteminden yararlanılmış ve AHS yönteminin kullanılmasındaExpert Choice 11.5 programı kullanılmıştır. Expert Choice ile tedarikçilerin üstünlükleribelirlenmiştir ve sistematik olarak karşılaştırılmıştır.

  16. Kök hücrede gen transferi ile istenen bir genin aktivasyonu veya susturulması uygulamalarının rejeneratif tıpta kullanımı

    Directory of Open Access Journals (Sweden)

    Zehra Dilşad Çoban

    2013-03-01

    Full Text Available İnsan kök hücresi kendine benzeyen hücreler oluşturabilen ve farklılaşma potansiyeline sahip özellikte hücrelerdir. Embriyonik kök hücreler farlı hücre tiplerine dönüşebildiği için kök hücre biyolojisinde ve rejeneratif tıpta paha biçilmez bir araçtır. Yeni gelişen gen teknolojileri ile ökaryot hücreye gen aktarımı mümkündür. Bu teknolojiler ile hücrede istenilen genlerin aktiflenmesi veya susturulması olasıdır. Uygun ortam sağlandığında normalde kapalı olan bazı genlerin aktif formlarının hücre çekirdeğine aktarılması ile farklanmış bir insan hücresinden indüklenmiş pluripotent kök hücreler elde edilmektedir. Bilindiği gibi, “small interference RNA” ve “micro RNA” lar hücrede gen fonksiyonlarını düzenlerler. Bu moleküller ökaryot hücrede gen susturulması amacı ile genellikle viral ve viral olmayan metodlar ile aktarılarak kullanılırlar. Gen susturulması teknolojisi, embriyonik kök hücre veya indüklenmiş pluripotent kök hücrelerin istenilen yönde örneğin bir nöron, pankreas veya kalp hücresi yönünde farklanmasında önemli bir araçtır. Tüm bu gelişmeler bize doku mühendisliği alanında hasta bazlı rejeneratif tıp uygulamalarının yapılabileceğini, kişiye özgü doku ve organ temininin mümkün olabileceğini göstermektedir.

  17. Ageing management for research reactors

    International Nuclear Information System (INIS)

    During the past several years, ageing of research reactor facilities continues to be an important safety issue. Despite the efforts exerted by operating organizations and regulatory authorities worldwide to address this issue, the need for an improved strategy as well as the need for establishing and implementing a systematic approach to ageing management at research reactors was identified. This paper discusses, on the basis of the IAEA Safety Standards, the effect of ageing on the safety of research reactors and presents a proactive strategy for ageing management. A systematic approach for ageing management is developed and presented together with its key elements, along with practical examples for their application. (author)

  18. Fueling of tandem mirror reactors

    International Nuclear Information System (INIS)

    This paper summarizes the fueling requirements for experimental and demonstration tandem mirror reactors (TMRs), reviews the status of conventional pellet injectors, and identifies some candidate accelerators that may be needed for fueling tandem mirror reactors. Characteristics and limitations of three types of accelerators are described; neutral beam injectors, electromagnetic rail guns, and laser beam drivers. Based on these characteristics and limitations, a computer module was developed for the Tandem Mirror Reactor Systems Code (TMRSC) to select the pellet injector/accelerator combination which most nearly satisfies the fueling requirements for a given machine design

  19. Concept for LEU Burst Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Klein, Steven Karl [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kimpland, Robert Herbert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-03-07

    Design and performance of a proposed LEU burst reactor are sketched. Salient conclusions reached are the following: size would be ~1,500 kg or greater, depending on the size of the central cavity; internal stresses during burst require split rings for relief; the reactor would likely require multiple control and safety rods for fine control; the energy spectrum would be comparable to that of HEU machines; and burst yields and steady-state power levels will be significantly greater in an LEU reactor.

  20. Random processes in nuclear reactors

    CERN Document Server

    Williams, M M R

    1974-01-01

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

  1. Safety of VVER-440 reactors

    CERN Document Server

    Slugen, Vladimir

    2011-01-01

    Safety of VVER-440 Reactors endeavours to promote an increase in the safety of VVER-440 nuclear reactors via the improvement of fission products limitation systems and the implementation of special non-destructive spectroscopic methods for materials testing. All theoretical and experimental studies performed the by author over the last 25 years have been undertaken with the aim of improving VVER-440 defence in depth, which is one of the most important principle for ensuring safety in nuclear power plants. Safety of VVER-440 Reactors is focused on the barrier system through which the safety pri

  2. BR2 reactor neutron beams

    International Nuclear Information System (INIS)

    The use of reactor neutron beams is becoming increasingly more widespread for the study of some properties of condensed matter. It is mainly due to the unique properties of the ''thermal'' neutrons as regards wavelength, energy, magnetic moment and overall favorable ratio of scattering to absorption cross-sections. Besides these fundamental reasons, the impetus for using neutrons is also due to the existence of powerful research reactors (such as BR2) built mainly for nuclear engineering programs, but where a number of intense neutron beams are available at marginal cost. A brief introduction to the production of suitable neutron beams from a reactor is given. (author)

  3. Nuclear reactor PBMR and cogeneration; Reactor nuclear PBMR y cogeneracion

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-10-15

    In recent years the nuclear reactor designs for the electricity generation have increased their costs, so that at the moment costs are managed of around the 5000 US D for installed kw, reason for which a big nuclear plant requires of investments of the order of billions of dollars, the designed reactors as modular of low power seek to lighten the initial investment of a big reactor dividing the power in parts and dividing in modules the components to lower the production costs, this way it can begin to build a module and finished this to build other, differing the long term investment, getting less risk therefore in the investment. On the other hand the reactors of low power can be very useful in regions where is difficult to have access to the electric net being able to take advantage of the thermal energy of the reactor to feed other processes like the water desalination or the vapor generation for the processes industry like the petrochemical, or even more the possible hydrogen production to be used as fuel. In this work the possibility to generate vapor of high quality for the petrochemical industry is described using a spheres bed reactor of high temperature. (Author)

  4. Reactor Safety Commission Code of Practice for Pressurized Water Reactors

    International Nuclear Information System (INIS)

    The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

  5. Breeder Reactors, Understanding the Atom Series.

    Science.gov (United States)

    Mitchell, Walter, III; Turner, Stanley E.

    The theory of breeder reactors in relationship to a discussion of fission is presented. Different kinds of reactors are characterized by the cooling fluids used, such as liquid metal, gas, and molten salt. The historical development of breeder reactors over the past twenty-five years includes specific examples of reactors. The location and a brief…

  6. FASTER test reactor preconceptual design report summary

    Energy Technology Data Exchange (ETDEWEB)

    Grandy, C. [Argonne National Lab. (ANL), Argonne, IL (United States); Belch, H. [Argonne National Lab. (ANL), Argonne, IL (United States); Brunett, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Heidet, F. [Argonne National Lab. (ANL), Argonne, IL (United States); Hill, R. [Argonne National Lab. (ANL), Argonne, IL (United States); Hoffman, E. [Argonne National Lab. (ANL), Argonne, IL (United States); Jin, E. [Argonne National Lab. (ANL), Argonne, IL (United States); Mohamed, W. [Argonne National Lab. (ANL), Argonne, IL (United States); Moisseytsev, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Passerini, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Sienicki, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Sumner, T. [Argonne National Lab. (ANL), Argonne, IL (United States); Vilim, R. [Argonne National Lab. (ANL), Argonne, IL (United States); Hayes, Steven [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-02-29

    The FASTER reactor plant is a sodium-cooled fast spectrum test reactor that provides high levels of fast and thermal neutron flux for scientific research and development. The 120MWe FASTER reactor plant has a superheated steam power conversion system which provides electrical power to a local grid allowing for recovery of operating costs for the reactor plant.

  7. Research reactors: design, safety requirements and applications

    International Nuclear Information System (INIS)

    There are two types of reactors: research reactors or power reactors. The difference between the research reactor and energy reactor is that the research reactor has working temperature and fuel less than the power reactor. The research reactors cooling uses light or heavy water and also research reactors need reflector of graphite or beryllium to reduce the loss of neutrons from the reactor core. Research reactors are used for research training as well as testing of materials and the production of radioisotopes for medical uses and for industrial application. The difference is also that the research reactor smaller in terms of capacity than that of power plant. Research reactors produce radioactive isotopes are not used for energy production, the power plant generates electrical energy. In the world there are more than 284 reactor research in 56 countries, operates as source of neutron for scientific research. Among the incidents related to nuclear reactors leak radiation partial reactor which took place in three mile island nuclear near pennsylvania in 1979, due to result of the loss of control of the fission reaction, which led to the explosion emitting hug amounts of radiation. However, there was control of radiation inside the building, and so no occurred then, another accident that lead to radiation leakage similar in nuclear power plant Chernobyl in Russia in 1986, has led to deaths of 4000 people and exposing hundreds of thousands to radiation, and can continue to be effect of harmful radiation to affect future generations. (author)

  8. Conceptual design study of JSFR reactor building

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, T.; Katoh, A.; Chikazawa, Y. [Japan Atomic Energy Agency (JAEA), 4002 Narita, Oarai, Ibaraki 311-1393 (Japan); Ohya, T.; Iwasaki, M.; Hara, H.; Akiyama, Y. [Mitsubishi FBR Systems, Inc. MFBR, 34-17, Jingumae 2-chome, Shibuya, Tokyo 150-0001 (Japan)

    2012-07-01

    Japan Sodium-cooled Fast Reactor (JSFR) is planning to adopt the new concepts of reactor building. One is that the steel plate reinforced concrete is adopted for containment vessel and reactor building. The other is the advanced seismic isolation system. This paper describes the detail of new concepts for JSFR reactor building and engineering evaluation of the new concepts. (authors)

  9. FASTER test reactor preconceptual design report summary

    International Nuclear Information System (INIS)

    The FASTER reactor plant is a sodium-cooled fast spectrum test reactor that provides high levels of fast and thermal neutron flux for scientific research and development. The 120MWe FASTER reactor plant has a superheated steam power conversion system which provides electrical power to a local grid allowing for recovery of operating costs for the reactor plant.

  10. Light water reactor safety research

    International Nuclear Information System (INIS)

    As the technology of light water reactors (LWR) was being commercialized, the German Federal Government funded the reactor safety research program, which was conducted by national research centers, universities, and industry, and which led to the establishment, in early 1972, of the Nuclear Safety Project in Karlsruhe. In the seventies, the PNS project mainly studied the loss-of-coolant accident. Numerous experiments were run and computer codes developed for this purpose. In the eighties, the Karlsruhe Nuclear Research Center contributed to the German Risk Study, investigating especially core meltdown accidents under the impact of the events at Three Mile Island-2 and Chernobyl-4. Safety research in the nineties is concentrated on the requirements of future reactor generations, such as the European Pressurized Water Reactor (EPR) or potential approaches which, at the present time, are discernible only as tentative theoretical designs. (orig.)

  11. Reactor operation environmental information document

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, L.R.; Hayes, D.W.; Hunter, C.H.; Marter, W.L.; Moyer, R.A.

    1989-12-01

    This volume is a reactor operation environmental information document for the Savannah River Plant. Topics include meteorology, surface hydrology, transport, environmental impacts, and radiation effects. 48 figs., 56 tabs. (KD)

  12. Fuel for advanced CANDU reactors

    International Nuclear Information System (INIS)

    The CANDU reactor system has proven itself to be a world leader in terms of station availability and low total unit energy cost. In 1985 for example, four of the top ten reactor units in the world were CANDU reactors operating in South Korea and Canada. This excellent operating record requires an equivalent performance record of the low-cost, natural uranium fuel. Future CANDU reactors will be an evolution of the present design. Engineering work is under way to refine the existing CANDU 600 and to incorporate state-of-the-art technology, reducing the capital cost and construction schedule. In addition, a smaller CANDU 300 plant has been designed using proven CANDU 600 technology and components but with an innovative new plant layout that makes it cost competitive with coal fired plants. For the long term, work on advanced fuel cycles and major system improvements is underway ensuring that CANDU plants will stay competitive well into the next century

  13. Conceptual design of RFC reactor

    International Nuclear Information System (INIS)

    A parametic analysis and a preliminary conceptual design for RFC reactor (including cusp field) with and without alpha particle heating are described. Steady state operations can be obtained for various RF ponderomotive potential in cases of alpha particle heating. (author)

  14. Methanogenesis in Thermophilic Biogas Reactors

    DEFF Research Database (Denmark)

    Ahring, Birgitte Kiær

    1995-01-01

    against Methanothrix soehngenii or Methanothrix CALS-I in any of the thermophilic biogas reactors examined. Studies using 2-14C-labeled acetate showed that at high concentrations (more than approx. 1 mM) acetate was metabolized via the aceticlastic pathway, transforming the methyl-group of acetate...... microorganism into methane. In thermophilic biogas reactors,, acetate oxidizing cultures occupied the niche of Methanothrix species, aceticlastic methanogens which dominate at low acetate concentrations in mesophilic systems. Normally, thermophilic biogas reactors are operated at temperatures from 52 to 560 C....... Experiments using biogas reactors fed with cow manure showed that the same biogas yield found at 550 C could be obtained at 610 C after a long adaptation period. However, propionate degradation was inhibited by increasing the temperature....

  15. Teaching About Nature's Nuclear Reactors

    CERN Document Server

    Herndon, J M

    2005-01-01

    Naturally occurring nuclear reactors existed in uranium deposits on Earth long before Enrico Fermi built the first man-made nuclear reactor beneath Staggs Field in 1942. In the story of their discovery, there are important lessons to be learned about scientific inquiry and scientific discovery. Now, there is evidence to suggest that the Earth's magnetic field and Jupiter's atmospheric turbulence are driven by planetary-scale nuclear reactors. The subject of planetocentric nuclear fission reactors can be a jumping off point for stimulating classroom discussions about the nature and implications of planetary energy sources and about the geomagnetic field. But more importantly, the subject can help to bring into focus the importance of discussing, debating, and challenging current thinking in a variety of areas.

  16. RA reactor operation and maintenance

    International Nuclear Information System (INIS)

    This volume includes the final report on RA reactor operation and utilization of the experimental facilities in 1962, detailed analysis of the system for heavy water distillation and calibration of the system for measuring the activity of the air

  17. Technique of nuclear reactors controls

    International Nuclear Information System (INIS)

    This report deal about 'Techniques of control of the nuclear reactors' in the goal to achieve the control of natural uranium reactors and especially the one of Saclay. This work is mainly about the measurement into nuclear parameters and go further in the measurement of thermodynamic variables,etc... putting in relief the new features required on behalf of the detectors because of their use in the thermal neutrons flux. In the domain of nuclear measurement, we indicate the realizations and the results obtained with thermal neutron detectors and for the measurement of ionizations currents. We also treat the technical problem of the start-up of a reactor and of the reactivity measurement. We give the necessary details for the comprehension of all essential diagrams and plans put on, in particular, for the reactor of Saclay. (author)

  18. Jules Horowitz Reactor, basic design

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-07-01

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

  19. Unique features of space reactors

    Science.gov (United States)

    Buden, David

    Space reactors are designed to meet a unique set of requirements; they must be sufficiently compact to be launched in a rocket to their operational location, operate for many years without maintenance and servicing, operate in extreme environments, and reject heat by radiation to space. To meet these restrictions, operating temperatures are much greater than in terrestrial power plants, and the reactors tend to have a fast neutron spectrum. Currently, a new generation of space reactor power plants is being developed. The major effort is in the SP-100 program, where the power plant is being designed for seven years of full power, and no maintenance operation at a reactor outlet operating temperature of 1350 K.

  20. Advanced Catalytic Hydrogenation Retrofit Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Reinaldo M. Machado

    2002-08-15

    Industrial hydrogenation is often performed using a slurry catalyst in large stirred-tank reactors. These systems are inherently problematic in a number of areas, including industrial hygiene, process safety, environmental contamination, waste production, process operability and productivity. This program proposed the development of a practical replacement for the slurry catalysts using a novel fixed-bed monolith catalyst reactor, which could be retrofitted onto an existing stirred-tank reactor and would mitigate many of the minitations and problems associated with slurry catalysts. The full retrofit monolith system, consisting of a recirculation pump, gas/liquid ejector and monolith catalyst, is described as a monolith loop reactor or MLR. The MLR technology can reduce waste and increase raw material efficiency, which reduces the overall energy required to produce specialty and fine chemicals.

  1. Advanced Carbothermal Electric Reactor Project

    Data.gov (United States)

    National Aeronautics and Space Administration — ORBITEC proposes to develop the Advanced Carbothermal Electric (ACE) reactor to efficiently extract oxygen from lunar regolith. Unlike state-of-the-art carbothermal...

  2. Advanced Carbothermal Electric Reactor Project

    Data.gov (United States)

    National Aeronautics and Space Administration — The overall objective of the Phase 1 effort was to demonstrate the technical feasibility of the Advanced Carbothermal Electric (ACE) Reactor concept. Unlike...

  3. Gas-cooled fast breeder reactor

    International Nuclear Information System (INIS)

    Almost all the R D works of gas-cooled fast breeder reactor in the world were terminated at the end of the year 1980. In order to show that the R D termination was not due to technical difficulties of the reactor itself, the present paper describes the reactor plant concept, reactor performances, safety, economics and fuel cycle characteristics of the reactor, and also describes the reactor technologies developed so far, technological problems remained to be solved and planned development schedules of the reactor. (author)

  4. Solid State Reactor Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Mays, G.T.

    2004-03-10

    The Solid State Reactor (SSR) is an advanced reactor concept designed to take advantage of Oak Ridge National Laboratory's (ORNL's) recently developed graphite foam that has enhanced heat transfer characteristics and excellent high-temperature mechanical properties, to provide an inherently safe, self-regulated, source of heat for power and other potential applications. This work was funded by the U.S. Department of Energy's Nuclear Energy Research Initiative (NERI) program (Project No. 99-064) from August 1999 through September 30, 2002. The initial concept of utilizing the graphite foam as a basis for developing an advanced reactor concept envisioned that a suite of reactor configurations and power levels could be developed for several different applications. The initial focus was looking at the reactor as a heat source that was scalable, independent of any heat removal/power conversion process. These applications might include conventional power generation, isotope production and destruction (actinides), and hydrogen production. Having conducted the initial research on the graphite foam and having performed the scoping parametric analyses from neutronics and thermal-hydraulic perspectives, it was necessary to focus on a particular application that would (1) demonstrate the viability of the overall concept and (2) require a reasonably structured design analysis process that would synthesize those important parameters that influence the concept the most as part of a feasible, working reactor system. Thus, the application targeted for this concept was supplying power for remote/harsh environments and a design that was easily deployable, simplistic from an operational standpoint, and utilized the new graphite foam. Specifically, a 500-kW(t) reactor concept was pursued that is naturally load following, inherently safe, optimized via neutronic studies to achieve near-zero reactivity change with burnup, and proliferation resistant. These four major areas

  5. Material test reactor fuel research at the BR2 reactor

    International Nuclear Information System (INIS)

    The construction of new, high performance material test reactor or the conversion of such reactors' core from high enriched uranium (HEU) to low enriched uranium (LEU) based fuel requires several fuel qualification steps. For the conversion of high performance reactors, high density dispersion or monolithic fuel types are being developed. The Uranium-Molybdenum fuel system has been selected as reference system for the qualification of LEU fuels. For reactors with lower performance characteristics, or as medium enriched fuel for high performance reactors, uranium silicide dispersion fuel is applied. However, on the longer term, the U-Mo based fuel types may offer a more efficient fuel alternative and-or an easier back-end solution with respect to the silicide based fuels. At the BR2 reactor of the Belgian nuclear research center, SCK-CEN in Mol, several types of fuel testing opportunities are present to contribute to such qualification process. A generic validation test for a selected fuel system is the irradiation of flat plates with representative dimensions for a fuel element. By flexible positioning and core loading, bounding irradiation conditions for fuel elements can be performed in a standard device in the BR2. For fuel element designs with curved plates, the element fabrication method compatibility of the fuel type can be addressed by incorporating a set of prototype fuel plates in a mixed driver fuel element of the BR2 reactor. These generic types of tests are performed directly in the primary coolant flow conditions of the BR2 reactor. The experiment control and interpretation is supported by detailed neutronic and thermal-hydraulic modeling of the experiments. Finally, the BR2 reactor offers the flexibility for irradiation of full size prototype fuel elements, as 200mm diameter irradiation channels are available. These channels allow the accommodation of various types of prototype fuel elements, eventually using a dedicated cooling loop to provide the

  6. LMFBR type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Iwashige, Kengo

    1996-06-21

    In an LMFBR type reactor, partitions are disposed to a coolant channel at positions lower than the free liquid level, and the width of the partitions is adapted to have a predetermined condition. Namely, when low temperature fluid overflowing the wall of the coolant channel, flows down and collided against the free liquid surface in the coolant channel, since the dropping speed thereof is reduced abruptly, large pressure waves are caused by kinetic force of the low temperature fluid. However, if appropriate numbers of partitions having an appropriate shape are formed, the dropping speed of the low temperature fluid is moderated to reduce the pressure waves. In addition, since the pressure waves are dispersed to the circumferential and lateral directions of the coolant flow channel respectively, the propagation of the pressure waves can be prevented effectively. Further, when the flow of the low temperature fluid is changed to the circumferential direction, for example, by earthquakes, since the partitions act as members resisting against the circumferential change of the low temperature fluid, the change of the direction can be suppressed. (N.H.)

  7. Natural convection type reactor

    International Nuclear Information System (INIS)

    In a natural convection type nuclear reactor, recycling flow rate of coolants is increased and the amount of entrained bubbles are increased as the driving force is increased, so that bubbles are not separated completely even if a stagnation region is disposed. Then, a space opened only at the upper portion is disposed at the outer circumference of the upper end of a riser for storing overflown coolants temporarily. The flow of coolants incorporating steam bubbles uprising in the riser turns into the horizontal direction at the upper end of the riser wall and flows into the coolant reservoir. In the coolant reservoir, since the momentum of the coolants is lost and the flow is stagnated, the bubbles are easily released to the upper space. Coolants, after releasing the bubbles, further overflow and descend in the downcomer. Then, the bubbles can be separated undergoing no influence of the driving force caused as the sum of the uprising force in the riser and the water head pressure in the downcomer, to prevent increase of carry under due to increase of the driving force. (N.H.)

  8. Reactor Simulator Testing Overview

    Science.gov (United States)

    Schoenfeld, Michael P.

    2013-01-01

    Test Objectives Summary: a) Verify operation of the core simulator, the instrumentation & control system, and the ground support gas and vacuum test equipment. b) Examine cooling & heat regeneration performance of the cold trap purification. c) Test the ALIP pump at voltages beyond 120V to see if the targeted mass flow rate of 1.75 kg/s can be obtained in the RxSim. Testing Highlights: a) Gas and vacuum ground support test equipment performed effectively for operations (NaK fill, loop pressurization, and NaK drain). b) Instrumentation & Control system effectively controlled loop temperature and flow rates or pump voltage to targeted settings and ramped within prescribed constraints. It effectively interacted with reactor simulator control model and defaulted back to temperature control mode if the transient fluctuations didn't dampen. c) Cold trap design was able to obtain the targeted cold temperature of 480 K. An outlet temperature of 636 K was obtained which was lower than the predicted 750 K but 156 K higher than the minimum temperature indicating the design provided some heat regeneration. d) ALIP produce a maximum flow rate of 1.53 kg/s at 800 K when operated at 150 V and 53 Hz.

  9. Reactor Simulator Testing

    Science.gov (United States)

    Schoenfeld, Michael P.; Webster, Kenny L.; Pearson, Boise J.

    2013-01-01

    As part of the Nuclear Systems Office Fission Surface Power Technology Demonstration Unit (TDU) project, a reactor simulator test loop (RxSim) was design & built to perform integrated testing of the TDU components. In particular, the objectives of RxSim testing was to verify the operation of the core simulator, the instrumentation and control system, and the ground support gas and vacuum test equipment. In addition, it was decided to include a thermal test of a cold trap purification design and a pump performance test at pump voltages up to 150 V since the targeted mass flow rate of 1.75 kg/s was not obtained in the RxSim at the originally constrained voltage of 120 V. This paper summarizes RxSim testing. The gas and vacuum ground support test equipment performed effectively in NaK fill, loop pressurization, and NaK drain operations. The instrumentation and control system effectively controlled loop temperature and flow rates or pump voltage to targeted settings. The cold trap design was able to obtain the targeted cold temperature of 480 K. An outlet temperature of 636 K was obtained which was lower than the predicted 750 K but 156 K higher than the cold temperature indicating the design provided some heat regeneration. The annular linear induction pump (ALIP) tested was able to produce a maximum flow rate of 1.53 kg/s at 800 K when operated at 150 V and 53 Hz.

  10. Novel Catalytic Membrane Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Stuart Nemser, PhD

    2010-10-01

    There are many industrial catalytic organic reversible reactions with amines or alcohols that have water as one of the products. Many of these reactions are homogeneously catalyzed. In all cases removal of water facilitates the reaction and produces more of the desired chemical product. By shifting the reaction to right we produce more chemical product with little or no additional capital investment. Many of these reactions can also relate to bioprocesses. Given the large number of water-organic compound separations achievable and the ability of the Compact Membrane Systems, Inc. (CMS) perfluoro membranes to withstand these harsh operating conditions, this is an ideal demonstration system for the water-of-reaction removal using a membrane reactor. Enhanced reaction synthesis is consistent with the DOE objective to lower the energy intensity of U.S. industry 25% by 2017 in accord with the Energy Policy Act of 2005 and to improve the United States manufacturing competitiveness. The objective of this program is to develop the platform technology for enhancing homogeneous catalytic chemical syntheses.

  11. OECD Halden Reactor Project

    International Nuclear Information System (INIS)

    The OECD Halden Reactor Project is both the oldest and the only one still in operation of the three major joint undertakings established at the inception of the OECD Nuclear Energy Agency. This publication has been printed in connection with its twenty-fifth anniversary as an international project. After presentation of the history and organization of the project, a thorough description of the past and present activities in the field of fuel performance and process control and surveillance is given. The projects's fuel testing programme is now focuessed on an investigation to define safety margins under normal operations as well as under various kinds of accident situations. Fuel research is also concerned with the characterisation of long term effects with regard to efficiency, operational safety and mapping of reliability and durability in the case of accidents with loss of coolant. In the field of process control and surveillance, research work is directly linked to the use of computers and colour graphics as tools in the control room. A fullscale simulator-based model and experimental control room has been constructed. The first experiments to be carried out in this laboratory will investigate the advantage of analysing alarms before they are presented to the operator. (RF)

  12. Nuclear reactor container

    International Nuclear Information System (INIS)

    A gas containing vessel has a water pool which is in communication with a dry well containing a reactor pressure vessel by way of a communication pipe is disposed. A capacity of a gas phase portion of the gas containing chamber, a capacity of the dry well, a water depth of a bent tube communicating the dry well with a pressure suppression pool of a pressure suppression chamber and a water depth of the communication pipe are determined so as to satisfy specific conditions. Since the water depth of the communication pipe is less than the water depth of the bent tube, incondensible gases and steams in the dry well flow into the water pool of the gas containing chamber at the initial stage of loss of coolant accident. Subsequently, steams in the dry well flow into the pressure suppression pool of the pressure suppression chamber by way of the bent tube. Accordingly, since the incondensible gases in the dry well do not flow into the pressure suppression chamber, pool swelling phenomenon in the pressure suppression chamber is not caused even if the water depth of the bent tube which leads to the pressure suppression chamber is great. Further, pressure increase due to transfer of the incondensible gases is decreased. (I.N.)

  13. OECD Halden reactor project

    International Nuclear Information System (INIS)

    A major part of the current research programme is devoted to irradiation experiments with a wide variety of heavily instrumented test fuel assemblies, in order to study the thermal and mechanical behavior of fuel rods through in-core measurements, in particular various forms of deformation of cladding and fuel as related to operational conditions and fuel rod design parameters. From these measurements mathematical models are being developed to explain quantitatively the deformation behavior, as well as the thermal properties of the fuel. During 1974, fifty-six instrumented fuel assemblies were irradiated in these experiments. Another major part of the Halden programme is aimed at the development and demonstration of advanced computer-based methods for plant and reactor core control, for safety and protection, and for overall supervision of nuclear power stations. Both the control methods themselves and the associated measurement and control apparatus are being elaborated, and during the year particular progress was made with the ''OPCOM'' process operator communication system

  14. MOLTEN FLUORIDE NUCLEAR REACTOR FUEL

    Science.gov (United States)

    Barton, C.J.; Grimes, W.R.

    1960-01-01

    Molten-salt reactor fuel compositions consisting of mixtures of fluoride salts are reported. In its broadest form, the composition contains an alkali fluoride such as sodium fluoride, zirconium tetrafluoride, and a uranium fluoride, the latter being the tetrafluoride or trifluoride or a mixture of the two. An outstanding property of these fuel compositions is a high coeffieient of thermal expansion which provides a negative temperature coefficient of reactivity in reactors in which they are used.

  15. Meeting on reactor safety research

    International Nuclear Information System (INIS)

    The meeting 'Reactor Safety Research' organized for the second time by the GRS by order of the BMFT gave a review of research activities on the safety of light water reactors in the Federal Repulbic of Germany, international co-operation in this field and latest results of this research institution. The central fields of interest were subjects of man/machine-interaction, operational reliability accident sequences, and risk. (orig.)

  16. Fractals in Power Reactor Noise

    International Nuclear Information System (INIS)

    In this work the non- lineal dynamic problem of power reactor is analyzed using classic concepts of fractal analysis as: attractors, Hausdorff-Besikovics dimension, phase space, etc. A new non-linear problem is also analyzed: the discrimination of chaotic signals from random neutron noise signals and processing for diagnosis purposes. The advantages of a fractal analysis approach in the power reactor noise are commented in details

  17. Stellarator fusion reactors - an overview

    International Nuclear Information System (INIS)

    The stellarator system offers a distinct alternative to the mainline approaches to magnetic fusion power and has several potentially major advantages. Since the first proposal of the stellarator concept many reactor studies have been published and these studies reflect the large variety of stellarator configurations. The main representatives are the continuous-coil configurations and the modular-coil configurations. As a continuation of the LHD experiment two reactor configurations, FFHR1 and FFHR2, have been investigated, which use continuous helical windings for providing the magnetic field. The modular coil concept has been realized in the MHH-reactor study (USA 1997) and in the Helias reactor. The Helias reactor combines the principle of plasma optimisation with a modular coil system. The paper also discusses the issues associated with the blanket and the maintenance process. Stellarator configurations with continuous coils such as LHD possess a natural helical divertor, which can be used favourably for impurity control. In advanced stellarators with modular coils the same goal can be achieved by the island divertor. Plasma parameters in the various stellarator reactors are computed on the basis of presently known scaling laws showing that confinement is sufficiently good to provide ignition and self-sustained burn. (author)

  18. Materials requirements for fusion reactors

    International Nuclear Information System (INIS)

    Once the physics of fusion devices is understood, one or more experimental power reactors (EPR) are planned which will produce net electrical power. The structural material for the device will probably be a modification of an austenitic stainless steel. Unlike fission reactors, whose pressure boundaries are subjected to no or only light irradiation, the pressure boundary of a fusion reactor is subjected to high atomic displacement-damage and high production rates of transmutation products, e.g., helium and hydrogen. The design data base must include irradiated materials. Since in situ testing to obtain tensile, fatigue, creep, crack-growth, stress-rupture, and swelling data is currently impossible for fusion reactor conditions, a program of service-temperature irradiations in fission reactors followed by postirradiation testing, simulation of fusion conditions, and low-fluence 14 MeV neutron-irradiation tests are planned. For the Demonstration Reactor (DEMO) expected to be built within ten years after theEPR, higher heat fluxes may require the use of refractory metals, at least for the first 20 cm. A partial data base may be provided by high-flux 14 MeV neutron sources being planned. Many materials other than those for structural components will be required in the EPR and DEMO. These include superconducting magnets, insulators, neutron reflectors and shields, and breeding materials. The rest of the device should utilize conventional materials except that portion involved in tritium confinement and recovery

  19. The safety of light water reactors

    International Nuclear Information System (INIS)

    The book describes the principles and practices of reactor safety as applied to the design, regulation and operation of both pressurized water reactors and boiling water reactors. The central part of the book is devoted to methods and results of safety analysis. Some significant events are described, notably the Three Mile Island accident. The book concludes with a chapter on the PIUS principle of inherent reactor safety as applied to the SECURE type of reactor developed in Sweden. (G.B.)

  20. Three dimensional diffusion calculations of nuclear reactors

    International Nuclear Information System (INIS)

    This work deals with the three dimensional calculation of nuclear reactors using the code TRITON. The purposes of the work were to perform three-dimensional computations of the core of the Soreq nuclear reactor and of the power reactor ZION and to validate the TRITON code. Possible applications of the TRITON code in Soreq reactor calculations and in power reactor research are suggested. (H.K.)

  1. ICONE-4: Proceedings. Volume 2: Advanced reactors

    International Nuclear Information System (INIS)

    The proceedings for this conference are contained in 5 volumes. This volume is divided into the following areas: advanced reactor requirements; advanced reactor design and analysis; arrangement and construction; specific reactor designs; demonstration testing; safety systems and analysis; component demonstration testing; advanced reactor containment design; licensing topics and updates; accelerator applications and spallation sources; and advanced reactor development. Separate abstracts were prepared for most papers in this volume

  2. Molten-Salt Depleted-Uranium Reactor

    OpenAIRE

    Dong, Bao-Guo; Dong, Pei; Gu, Ji-Yuan

    2015-01-01

    The supercritical, reactor core melting and nuclear fuel leaking accidents have troubled fission reactors for decades, and greatly limit their extensive applications. Now these troubles are still open. Here we first show a possible perfect reactor, Molten-Salt Depleted-Uranium Reactor which is no above accident trouble. We found this reactor could be realized in practical applications in terms of all of the scientific principle, principle of operation, technology, and engineering. Our results...

  3. Calculation of reactor antineutrino spectra in TEXONO

    CERN Document Server

    Chen Dong Liang; Mao Ze Pu; Wong, T H

    2002-01-01

    In the low energy reactor antineutrino physics experiments, either for the researches of antineutrino oscillation and antineutrino reactions, or for the measurement of abnormal magnetic moment of antineutrino, the flux and the spectra of reactor antineutrino must be described accurately. The method of calculation of reactor antineutrino spectra was discussed in detail. Furthermore, based on the actual circumstances of NP2 reactors and the arrangement of detectors, the flux and the spectra of reactor antineutrino in TEXONO were worked out

  4. Analysis of higher power research reactors' parameters

    International Nuclear Information System (INIS)

    The objective of this monograph was to analyze and compare parameters of different types of research reactors having higher power. This analysis could be used for decision making and choice of a reactor which could possibly replace the existing ageing RA reactor in Vinca. Present experimental and irradiation needs are taken into account together with the existing reactors operated in our country, RB and TRIGA reactor

  5. Güvenlik bağlamında Avrupa Birliği (AB), NATO ve ABD ilişkileri: AGSK'dan ODGP'ye geçiş

    OpenAIRE

    MENGİ, Ergun

    2014-01-01

    Bu çalışmadan, Soğuk savaş (SS) sonrası ortaya çıkan küresel tehditler kapsamında Avrupa Güvenliği bağlamında AB'nin savunma boyutunda, AGSP'nin bağımsız güçlü Avrupa savunması yolunda mı ilerleyeceği, yoksa AGSP-NATO, dolayısıyla AB-ABD işbirliği içinde transatlantik bağı güçlü tutarak mı gelişeceğinin belirlenmesi amaçlanmıştır. Araştırmada başta Fransa olmak üzere AB ülkelerinin yaklaşımları ele alınmış, bulguların konjonktürel karşılaştırmalı bir analizi yapılarak, ta...

  6. Sultan I. Ahmed’e Sunulan Nur-i Muhammedî Konulu Bir Eser: Nûr-Nâme A Work Presented To I. Ahmed About The Nûr-i Muhammedî: Nûr-Nâme

    Directory of Open Access Journals (Sweden)

    Mücahit KAÇAR

    2013-03-01

    Full Text Available The term of Nûr-ı Muhammedî, sometimes is expressed in Nûr-ı Muhammediyye, used to refer to the Prophet Muhammad's spiritual personality in the mystical works. These two terms refer to the Prophet Muhammad is first and foremost, the universe was created from it, and hence the Prophet Mohammed is source of virtues. The idea of Nûr-ı Muhammedî, not only in the mystical scholars’ works like İbnü’l-Arabî, is found in the basic İslamic books read by the wider public in Ottoman Empire. This idea, shared by all layers of Ottoman society, can be considered as the main point of Ottoman’s knowledge understanding. Nûr-nâme which are subject to this study and shows the feature of siyer and mawlid works, was written by Cafer Iyânî, one of the authors of 16th century. In Nûr-nâme, there is information about the idea of Nûr-ı Muhammedîas well as the virtues of the Prophet Muhammad and the work is noteworthy in this respect. In this study, After giving brief information about the idea of Nûr-ı Muhammedî, the author and Nûr-nâme will be informed. Finally, the contribution of this work to attempts understanding the otoman empire will be assessed and then the the text of the Nûr-nâme will be presented. Dînî-tasavvufî eserlerde Hz. Peygamber'in manevî şahsiyetini ifade etmek için kullanılan bir terim olan Nûr-ı Muhammedî, bazen de hakîkat-i Muhammediyye şeklinde ifade edilmektedir. Bu iki terim de Hz. Muhammed’in her şeyden önce yaratıldığını, kâinatın da ondan yaratıldığını ve dolayısıyla Hz. Muhammed’in bütün faziletlerin kaynağı olduğunu ifade etmek üzere kullanılır. Nûr-ı Muhammedî anlayışı, Osmanlı’da geniş halk tabakaları tarafından okunan temel İslâmî kitaplarda da daha basit ve anlaşılır şekillerde ele alınmıştır. Dolayısıyla bu anlayış sadece İbnü’l-Arabî gibi mutasavvıfların eserlerinde kalmamış avam tarafından da kabul edilen yaygın bir inan

  7. Osmanlı Ordusunda Venezuelalı Bir Gezgin Şövalye: Rafael de Nogales Méndez A Venezuelian Knight Errant In The Ottoman Army: Rafael de Nogales Méndez

    Directory of Open Access Journals (Sweden)

    Hüseyin Güngör ŞAHİN

    2013-09-01

    ör Porfirio Diaz'ın emrinde görevli bir atlı sınır muhafızıyken, yıllar sonra Diaz karşıtı isyancı kuvvetlere katılan bir devrimci, Uzakdoğu'da gizli ajan, Guatemala’da suikast timi üyesi, ülkesinde yıllarca bir asi, yaşamının son döneminde ise bir devlet görevlisi olmuştur. Şiarının "iyi bir savaş görürsen, savaşmak için ona gönüllü yazıl,"1 olduğunu belirten Nogales, bir asker, savaşçı, gezgin, maceraperest ve yazardı. Kendisini "bir dünya vatandaşı ve bir gezgin şövalye"2 olarak tanımlıyordu. Tabiri caizse, o, 20. yüzyılın Don Kişot'u idi.Bu çalışmada, Nogales'in anılarını aktardığı kitaplarında yer alan bilgilerden hareketle yaşam öyküsü irdelenirken, yazarın dönemin tarihi olaylarına dair anlatıları özgün kaynaklarla mukayeseli olarak incelenmiştir. Bu amaçla çok sayıda resmi kaynak ve hatırat gözden geçirilmiş, arşiv araştırması yapılmıştır. Öte yandan bu alanda literatüre yeni bilgi ve belge kazandırmak, çalışmanın amaçları arasında yer almaktadır.

  8. Faaliyet tabanlı maliyetleme yöntemi ve beş yıldızlı bir otel işletmesinde örnek uygulaması

    OpenAIRE

    Bozkurt, Ramazan

    2010-01-01

    İşletmeler arası rekabetin had safhalara ulaştığı günümüz piyasa koşullarında işletmeler için açığa çıkan maliyet bilgilerinin doğru ve güvenilir olması hiç şüphesiz işletme performansı açısından çok büyük öneme sahiptir. Bunun yanı sıra gelişen teknolojinin de etkisi ile işletmelerde birçok genel üretim giderleri ortaya çıkmış ancak mevut geleneksel maliyetleme yöntemleri bu giderleri ideal bir şekilde maliyetlemede yetersiz kalmıştır. Bu nedenle Faaliyet Tabanlı Maliyetleme modeli Gelenekse...

  9. Yöneticilik Yaklaşımında Cinsiyet Faktörü- Afyonkarahisar İli Banka Yöneticileri Üzerinde Bir Araştırma

    OpenAIRE

    Karcı, Aslı

    2012-01-01

    Günümüzde artık iş dünyasında “yöneticiliğin erkeklere özgü bir meslek olduğu” görüşü değişmektedir ve kadın yöneticilerin işyerlerine farklı bir hava taşıdıkları, gerek yönetim fonksiyonun ele alış şeklinin erkeklere göre farklı ve benzer yönlerin in olduğu, gerekse de yönetim kültürünün meydana gelmesinde, kadın yöneticilerin erkeklerden ayrılan yönleri, etkileri ve benzeri konular bilimsel çalışmalar açısından ele alınmaya başlandığı sıkça görülmektedir. Bu görüşten hareketle kadın ve ...

  10. Nisâ Sûresi 65. Âyete Dair Abdülmecîd-i Sîvâsî’nin (971/1049-1563/1639 Bilinmeyen Bir Risalesi

    Directory of Open Access Journals (Sweden)

    mehmet çiçek

    2011-09-01

    Full Text Available Osmanlı dönemi tefsir geleneğine dair yapılan çalışmalar, henüz beklenilen ve hedeflenen noktadan uzak görünmektedir. Bu makale, bir nebze de olsa mevcut duruma işaret etme ve “bilinmeyeni” ortaya çıkarma hedefini gütmektedir.  Abdülmecid-i Sivasi’ye ait Nisa suresi 65. Ayete dair risaleyi ele aldığımız bu makalede eser hakkında bilgi vermeye çalıştık. Değerlendirmelerimizi ise metod ve içerik olmak üzere iki açıdan ele aldık. Risale, söz konusu Nisâ suresi 60 ila 65. ayetlerin münafıklar hakkında indirildiğine dikkat çekmektedir. Ayrıca Zübeyr b. Avvam’ın sebeb-i nüzûlle ilgili rivâyetine bir cevap vermeyi hedeflemiştir, diyebiliriz. Buna ilaveten risalenin Bedir ehlinin üstünlüğüne dair hassasiyeti dikkate aldığı söylenebilir.

  11. Kara Bela Münasebetiyle Eleştirilen Bir Ekol: Namık Kemal A Literary School Criticized on Merits of “Kara Bela” (“Misfortune”: Namık Kemal

    Directory of Open Access Journals (Sweden)

    Hacer GÜLŞEN

    2013-03-01

    Full Text Available One of the most notable writers of Turkish literature, Namık Kemal was rather a school unto himself, owing to his pursuits in the creation of a New literature, his works and critical essays. Several prominent figures assembled around him, sharing his thoughts, and also defending him ardently. More often than not praised, he was sometimes criticized bitterly. Introducing Western literary forms to a nascent universe, he assigned importance to theater. For him, it isentertainment – but a most useful distraction. “Mukaddime-i Celal” isthe preface of the title “Celalettin Harzemşah.” This prelude wascomposed with an allusion to Victor Hugo’s Cromwell foreword. In this,his views on drama are markedly captivating. He penned his play “KaraBela” (“Misfortune” while in exile in Famagusta. Publishedposthumously, it was purported, however, to be rather a tenuous piece.“Kara Bela” was criticized in “Tenkidat-ı Edebiye – Namık Kemal - KaraBela Münasebetiyle” (“A Literary Critique – On Merits of Namık Kemal’s‘Misfortune’,” written in 1911 by Şahabettin Süleyman, among theillustrious portraits of the Fecr-i Âti (“Pending Twilight” period. Heportrays Namık Kemal as a crony of the commoners. Thereafter, headjudges that its plotline fails to align with real life. Remarkably, hechooses the less formal reference of “Kemal,” who has prevailed in theliterary realm long before his debut. Criticized in this article for hisartistic stature, Namık Kemal will be assessed with the Author-BasedCritical Approach. Evidently, this method places the artist at the core ofthe critique. Türk edebiyatının önemli sanatkârlarından biri olan Namık Kemal, yeni bir edebiyatın oluşmasında ve tanınmasında gösterdiği gayretlerle, eserleriyle, eleştirileriyle, âdeta bir ekol olmuştur. İsminin etrafında birçok isim toplanmış, düşüncelerini paylaşıp, onu savunmuşlardır. Çoğu zaman övülen Namık Kemal

  12. II. Pehlevi Dönemi İran Dış Siyaseti Üzerine Bir Deneme Essay on the Foreign Policy of Iran in the era of the Pahlavi II

    Directory of Open Access Journals (Sweden)

    M. Serkan TAFLIOĞLU

    2013-09-01

    Full Text Available Since the early 1970s, Iran has been regarded as an vital key player in the Middle East, Iran had conducted to accumulate significant strategic value during the Cold War. Iran under Pahlavi Dynasty, due to the struggle among rival foreign forces, was transformed into a significant regional power in the twentieth century by his pro-westernpolicy in particular USA. In the 1950s superpower rivalry, restrictingthe ability of the great powers to use military force in the region, clearedfield for Nasser’s attempt to use Pan-Arab ideology to gather the Arabstates, though against Western intrusion. During this period, Shah hasendeavor to consolidate strenght of monarchy by exerting the powerstruggle in the Middle East between the West and East Blocks in hisfavor. The vital necessity for the West to Iran, in particular Americanadministration, caused to prepare ground a more authoritariangovernment in Iran. In this article, I do try to evaluate Iran’s foreignpolicy in a certain time period the Shah Mohammed Reza Pahlavi. Ourgravity point will be politics of Iran between Great Powers in that period.In this context, Whilst analyzing this policy, I do try to merge; core offoreign policy and political history. Essay is assorted due to thechronology. Research period is accedence of Shah Mohammed RezaPahlavi to the throne till to the flee from Iran. 1970’li yılların başından itibaren İran, Soğuk Savaş döneminde stratejik bir değer kazanarak, Ortadoğu’da hayati bir oyuncu kabul edilmiştir. Yirminci yüzyılda Pehlevi hanedanı yönetimindeki İran, dış güçlerin arasındaki mücadele sayesinde Batı ve özellikle Amerikan yanlısı siyasetiyle, etkili bir bölgesel güce dönüşmüştür. 1950’li yılların başlarında Büyük Güçler arasındaki mücadele Ortadoğu’ya müdahale kabiliyetini sınırlandırmaktaydı, bu durum Nasır’ın Pan- Arap siyasetini kullanarak, Batı müdahalesine karşı, Arap devletlerini bir araya

  13. Impact of proposed research reactor standards on reactor operation

    International Nuclear Information System (INIS)

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

  14. Prometheus Project Reactor Module Final Report, For Naval Reactors Information

    International Nuclear Information System (INIS)

    The Naval Reactors Prime Contractor Team (NRPCT) led the development of a power plant for a civilian nuclear electric propulsion (NEP) system concept as part of the Prometheus Project. This report provides a summary of the facts, technical insights, and programmatic perspectives gained from this two-year program. The Prometheus Project experience has been extensively documented to better position the US for future space reactor development. Major Technological and engineering challenges exist to develop a system that provides useful electric power from a nuclear fission heat source operating in deep space. General issues include meeting mission requirements in a system that has a mass low enough to launch from earth while assuring public safety and remaining safely shutdown during credible launch accidents. These challenges may be overcome in the future if there is a space mission with a compelling need for nuclear power to drive development. Past experience and notional mission requirements indicate that any useful space reactor system will be unlike past space reactors and existing terrestrial reactors

  15. Repairing liner of the reactor; Reparacion del liner del reactor

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar H, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2001-07-15

    Due to the corrosion problems of the aluminum coating of the reactor pool, a periodic inspections program by ultrasound to evaluate the advance grade and the corrosion speed was settled down. This inspections have shown the necessity to repair some areas, in those that the slimming is significant, of not making it can arrive to the water escape of the reactor pool. The objective of the repair is to place patches of plates of 1/4 inch aluminum thickness in the areas of the reactor 'liner', in those that it has been detected by ultrasound a smaller thickness or similar to 3 mm. To carry out this the fuels are move (of the core and those that are decaying) to a temporary storage, the structure of the core is confined in a tank that this placed inside the pool of the reactor, a shield is placed in the thermal column and it is completely extracted the water for to leave uncover the 'liner' of the reactor. (Author)

  16. Operating experiences of the research reactors

    International Nuclear Information System (INIS)

    Nuclear research reactors are devices of wide importance, being used for different scientific research tasks, for testing and improving reactor systems and components, for the production of radioisotopes, for the purposes of defence, for staff training and for other purposes. There are three research reactors in Yugoslavia: RA, RB and TRIGA. Reactors RA and RB at the 'Boris Kidric' Institute of Nuclear Sciences are of heavy water type power being 6500 and 10 kW, and maximum thermal neutron flux of 1014 and 1011(n/cm2s), respectively. TRIGA reactor at the 'Jozef Stefan' Institute in Ljubljana is of 250 kW power and maximum thermal neutron flux of 1013(n/cm2s). Reactors RA and RB use soviet fuel in the form of uranium dioxide (80% enriched) and metallic uranium (2%). Besides, RB reactor operates with natural uranium too. TRIGA reactor uses american uranium fuel 70% and 20% enriched, uranium being mixed homogeneously with moderator (ZrH). Experiences in handling and controlling the fuel before irradiation in the reactor, in reactor and after it are numerous and valuable, involving either the commercial arrangements with foreign producers, or optimal burn up in reactor or fuel treatment after the reactor irradiation. Twenty years of operating experience of these reactors have great importance especially having in mind the number of trained staff. Maintenance of reactors systems and fluids in continuous operation is valuable experience from the point of view of water reactor utilization. The case of the RA reactor primary cycle cobalt decontamination and other events connected with nuclear and radiation security for all three reactors are also specially emphasized. Owing to our research reactors, numerous theoretical, numerical and experimental methods are developed for nuclear and other analyses and design of research and power reactors,as well as methods for control and protection of radiation. (author)

  17. Establishment of licensing process for development reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Jong Chull; Yune, Young Gill; Kim, Woong Sik (and others)

    2006-02-15

    A study on licensing processes for development reactors has been performed to prepare the licensing of development reactors developed in Korea. The contents and results of the study are summarized as follows. The licensing processes for nuclear reactors in Korea, U.S.A., Japan, France, U.K., Canada, and IAEA were surveyed and analyzed to obtain technical bases necessary for establishing licensing processes applicable to development reactors in Korea. Based on the technical bases obtained the above analysis, the purpose, power output, and design characteristics of development reactors were analyzed in detail. The analysis results suggested that development reactors should be classified as a new reactor category (called as 'development reactor') separated from the current reactor categories such as the research reactor and the power reactor. Therefore, it is proposed to establish a new reactor category classified as 'development reactor' for the development reactors. And licensing processes, including licensing technical requirements, licensing document requirements, and other regulatory requirements, were also proposed for the development reactors. In order to institutionalize the licensing processes developed in this study, it is necessary to revise the current laws. Therefore, draft provisions of Atomic Energy Act, Enforcement Decree of the Atomic Energy Act, and Enforcement Regulation of the Atomic Energy Act have been developed for the preparation of the future legalization of the licensing processes proposed for the development reactors. Conclusively, a proposal of licensing processes and draft provisions of laws have been developed for the development reactors. The results proposed in this study can be applied directly to the licensing of the future development reactors. Furthermore, they will also contribute to establishing successfully the licensing processes of the development reactors.

  18. Torus mandibularis varlığında kısmi dişsiz bir hastanın protetik rehabilitasyonu: olgu sunumu

    Directory of Open Access Journals (Sweden)

    Arife Dogan

    2011-10-01

    Full Text Available

    The torus mandibularis is the one of the most common intraoral exostoses. It is often bilateral, occurs at the canin to premolar region on the lingual aspect of the mandible. It has been reported that the factors such as genetic and environmental factors, masticator hiperfunction, nutrition, race and ethnic groups might play role in occurence of them. Such type of bony protuberances may present many challenges when fabricating a removable partial or complete

    dentures. In this case report, after a general knowledge about mandibular tori, the prosthetic rehabilitation of a partially edentulous patient had bilaterally mandibular tori has been presented.

    ÖZET

    Torus mandibularis ağız içinde en sık görülen eksostoz türlerinden biridir. Genellikle, mandibulanın lingual yüzeyinde, kanin ve premolar bölgesinde yerleşim göstermesiyle karakterizedir. Etyolojisinde kalıtım, çevresel faktörler, artmış çiğneme fonksiyonu, beslenme, ırk ve etnik grup farklılıklarının etkili olduğu düşünülmektedir. Bu tür kemik büyümeleri hareketli parsiyel veya tam protez yapımında güçlüklere neden olabilir. Bu olgu sunumunda kısmi dişsiz ve çift taraflı mandibular torusa sahip bir hastanın protetik tedavisi bildirilmiş ve toruslar hakkında genel bilgi verilmiştir.

    Anahtar sözcükler: Torus mandibularis, kısmi dişsiz hasta

  19. Esneyebilir bir protez kaide rezin ile hareketli bölümlü protezlerin yapımı: vaka sunumu

    Directory of Open Access Journals (Sweden)

    Ayse Kubra Demir

    2011-11-01

    Full Text Available

    Aesthetic considerations in dental treatment are directly related to the sentiments and opinions of the patient. Aesthetics has been a crucial factor for fixed rehabilitations, but nowadays removable partial dentures also show great interest in satisfying the aesthetic requirements. Tooth selection, teeth arrangement, and the compatibility of the artificial tooth with face structure are known to affect aesthetics in removable partial dentures. In addition to these, poor design of clasp systems can be the major impairment factors in structural components of these dentures. Although development of precision attachments, and the clasp systems, it is unable to obtain satisfying aesthetic with removable partial dentures. In this study, we present a case report that describes the rehabilitation of a patient with a polyamide (PA6.6 denture base resin in order to remedy both the functional and aesthetic considerations.

     

    ÖZET

    Diş hekimliğinde estetik gereksinimler hastaların duygu ve düşünceleriyle direk ilgilidir. Estetik yaklaşımlar protetik tedavide özellikle sabit rehabilitasyonlar için öncelik taşısa da bugün hareketli bölümlü protezler için de aynı derecede önem oluşturmaktadır. Hareketli bölümlü protezlerde estetin sağlanmasında diş seçimi, diş dizimi, yapay dişlerin yüz şekliyle uygunluğu gibi faktörlerin etkili olduğu bilinmektedir. Bununla birlikte bu protezlerin yapısal unsurları arasında estetiği olumsuz yönde etkileyen en önemlisi kroşe sistemleridir. Estetik gereksinimleri karşılaması açısından birçok kroşe sistemi, hassas tutucular geliştirilmesine karşın bazı vakalarda bu sistemler yeterli olamamaktadır. Bu çalışmada fonksiyonel ve estetik gereksinimleri karşılamak amacıyla geliştirilmiş poliamid (PA 6.6 protez kaide rezin ile yapılan vakamızı sunmayı amaçladık.

    Anahtar Kelimeler: Hareketli b

  20. Nordic study on reactor waste

    International Nuclear Information System (INIS)

    In 1981, 14 nuclear power reactors are in operation and 2 under construction in the Nordic countries. So far, the reactor waste originating from day-to-day operation of these plants has been stored in solidified form at the reactor sites. Within a few years a satisfactory disposal procedure needs to be established. While the main R and D effects in the waste field have earlier been devoted to the question of irradiated fuel and waste from reprocessing, there is therefore now an increased interest in reactor waste with its much lower radioactivity but somewhat larger volumes. Since 1977, efforts have been made in a joint Nordic study to examine which facts need to be known in order to perform a comprehensive safety assessment of a reactor waste management system. In the present study a Reference system related to the waste generated over 30 years from six 500 MW-reactors is examined. The dominating radionuclides during storage and transportation accident scenarios are Cs-134, Cs-137 and Co-60. For most of the release scenarios from repositories Cs-137 and Sr-90 are dominating. Some scenarios are, however, dominated by the very longlived nuclides I-129 and C-14. A closer examination of the concentration in the waste of these nuclides and of their leaching properties indicates that their small - but significant - influence, as calculated, is probably grossly overestimated. The mechanical stability obtained in routine solidification processes of reactor waste products in conjunction with the outer container (steel drum, transport container, etc.) turns out to be sufficient. Difficulties were encountered in applying ICRP methodology and available dose calculation methods to calculation of population doses due to small activity releases, and effects extending into the far future. (EG)

  1. When reactors reach old age

    International Nuclear Information System (INIS)

    While the battle over whether to build new nuclear plants has quieted in recent times, a second struggle is shaping up in the United States as reactors approach a new stage of life: retirement. Four decades into the nuclear power age, questions of how best to dismantle and dispose of a nuclear power plant remain largely unanswered. The debates have been mainly academic until now - although reactors have operated for 25 years, decommissioning retired reactors has simply not been fully planned in this country. But the Shippingport Atomic Power Station in Pennsylvania, the first large-scale power reactor to be retired, is now being decommissioned. The work has rekindled the debates in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane. Virtually all groups involved in decommissioning a reactor in the United States - the utility, the Nuclear Regulatory Commission, the U.S. Department of Energy, the U.S. Environmental Protection Agency, state public service commissions, and citizen organizations - agree that for the most part the technology to dismantle and dispose of a reactor safely is available. They disagree, however, on which technical option is the safest or cheapest and on who should pay for dismantlement. And there are further complications: Which regulations must be complied with. How much radiation exposure for workers and the public is acceptable. Even with answers to these questions, uncertainty about where to dispose of the radioactive waste and about how much residual radiation can be left at a former reactor site plagues the architects of decommissioning. This article discusses these questions

  2. Market introduction of innovative reactors

    International Nuclear Information System (INIS)

    Besides the development of evolutionary and passive LWR, also that of innovative reactors is attractive, because other applications (new markets) besides base load electricity generation can be thought of, and interesting new features on the area of safety or waste incineration can be shown. For market introduction however, a (partial) new infrastructure and a demonstration plant are required. Taking the abundance of fossil fuels and the accompanying low fuel prices today and in the near future into account, the funds to finance this will only become available when 1)the projected energy generating costs will be substantially lower than those of today, and 2)the costs of market introduction (i.e. the demonstration plant and the required infrastructure) will be limited. Generally speaking, there are two ways to seek competitiveness of a reactor type: 1)application of economy of scale, and 2)simplification. In this paper, an example of the second possibility is pursued for an innovative reactor type. The HR1 is a 40 MWth high temperature gas cooled reactor for heat and power cogeneration, a simplified version of the German HTR Module. The power level is chosen so small that additional safety features become apparent. For example, after a total loss of coolant the fuel remains fully intact, even if the reactor shutdown system fails and the reactor goes critical again after a number of hours. These safety features are used to omit certain components, like the emergency core cooling system, or to select a cheaper version of components, e.g. replacing the containment building by a confinement. Moreover, degradation of the safety class of certain components comes within the realm of possibilities. The cost reduction offered by these two measures are used to more than offset the economy-of-scale disadvantage of this small reactor system. (author)

  3. University of Florida training reactor. Annual progress report, September 1, 1984-August 31, 1985

    International Nuclear Information System (INIS)

    This annual progress report of the University of Florida Training Reactor discusses: reactor operation; personnel; modifications made to the reactors; reactor maintenance; and testing of reactor systems

  4. Reactivity determination in accelerator driven reactors using reactor noise analysis

    Directory of Open Access Journals (Sweden)

    Kostić Ljiljana 1

    2002-01-01

    Full Text Available Feynman-alpha and Rossi-alpha methods are used in traditional nuclear reactors to determine the subcritical reactivity of a system. The methods are based on the measurement of the mean value, variance and the covariance of detector counts for different measurement times. Such methods attracted renewed attention recently with the advent of the so-called accelerator driven reactors (ADS proposed some time ago. The ADS systems, intended to be used either in energy generation or transuranium transmutation, will use a subcritical core with a strong spallation source. A spallation source has statistical properties that are different from those traditionally used by radioactive sources. In such reactors the monitoring of the subcritical reactivity is very important, and a statistical method, such as the Feynman-alpha method, is capable of resolving this problem.

  5. Fast Reactor Development Strategy in China

    International Nuclear Information System (INIS)

    As one of the largest developing countries, China needs a reliable energy supplement. At the same time, China should improve the energy structure to decrease CO2 emissions. Nuclear and renewable energies are the main solutions to these issues. According to the research results, the nuclear capacity should increase to 400 GW(e) up to 2050. Fast reactors must be developed considering the limitation of uranium resources. In order to deploy fast reactor technology, the ‘experimental reactor, demonstration reactor and commercial reactor’ strategy has been suggested. China has finished the construction of the China Experimental Fast Reactor (CEFR) and gained necessary experience about fast reactors. The China Institute of Atomic Energy (CIAE) has begun to design the CFR-600, a 600 MW(e) demonstration fast reactor. This reactor will be put into operation before 2025. After that, a larger commercial reactor will be constructed. Besides fast reactors, all of other key sectors of fuel cycle will be developed at the same time such as reprocessing, fast reactor fuel, etc. There are two main tasks of fast reactors, one of which is to raise the utility ratio of uranium, and the other one is to transmute the long life waste of light water reactors. The fast reactor will be designed as a breeder and burner, respectively. (author)

  6. Inherently safe light water reactors

    International Nuclear Information System (INIS)

    Today's large nuclear power reactors of world-wise use have been designed based on the philosophy. It seems that recent less electricity demand rates, higher capital cost and the TMI accident let us acknowledge relative small and simplified nuclear plants with safer features, and that Chernobyl accident in 1983 underlines the needs of intrinsic and passive safety characteristics. In such background, several inherently safe reactor concepts have been presented abroad and domestically. First describing 'Can inherently safe reactors be designed,' then I introduce representative reactor concepts of inherently safe LWRs advocated abroad so far. All of these innovative reactors employ intrinsic and passive features in their design, as follows: (1) PIUS, an acronym for Process Inherent Ultimate Safety, or an integral PWR with passive heat sink and passive shutdown mechanism, advocated by ASEA-ATOM of Sweden. (2) MAP(Minimum Attention Plant), or a self-pressurized, natural circulation integral PWR, promoted by CE Inc. of the U.S. (3) TPS(TRIGA Power System), or a compact PWR with passive heat sink and inherent fuel characteristics of large prompt temperature coefficient, prompted by GA Technologies Inc. of the U.S. (4) PIUS-BWR, or an inherently safe BWR employing passively actuated fluid valves, in competition with PIUS, prompted by ORNL of the U.S. Then, I will describe the domestic trends in Japan and the innovative inherently safe LWRs presented domestically so far. (author)

  7. Utilization of nuclear research reactors

    International Nuclear Information System (INIS)

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

  8. Thermonuclear Reflect AB-Reactor

    CERN Document Server

    Bolonkin, Alexander

    2008-01-01

    The author offers a new kind of thermonuclear reflect reactor. The remarkable feature of this new reactor is a three net AB reflector, which confines the high temperature plasma. The plasma loses part of its energy when it contacts with the net but this loss can be compensated by an additional permanent plasma heating. When the plasma is rarefied (has a small density), the heat flow to the AB reflector is not large and the temperature in the triple reflector net is lower than 2000 - 3000 K. This offered AB-reactor has significantly less power then the currently contemplated power reactors with magnetic or inertial confinement (hundreds-thousands of kW, not millions of kW). But it is enough for many vehicles and ships and particularly valuable for tunnelers, subs and space apparatus, where air to burn chemical fuel is at a premium or simply not available. The author has made a number of innovations in this reactor, researched its theory, developed methods of computation, made a sample computation of typical pr...

  9. Heterogeneous Transmutation Sodium Fast Reactor

    Energy Technology Data Exchange (ETDEWEB)

    S. E. Bays

    2007-09-01

    The threshold-fission (fertile) nature of Am-241 is used to destroy this minor actinide by capitalizing upon neutron capture instead of fission within a sodium fast reactor. This neutron-capture and its subsequent decay chain leads to the breeding of even neutron number plutonium isotopes. A slightly moderated target design is proposed for breeding plutonium in an axial blanket located above the active “fast reactor” driver fuel region. A parametric study on the core height and fuel pin diameter-to-pitch ratio is used to explore the reactor and fuel cycle aspects of this design. This study resulted in both non-flattened and flattened core geometries. Both of these designs demonstrated a high capacity for removing americium from the fuel cycle. A reactivity coefficient analysis revealed that this heterogeneous design will have comparable safety aspects to a homogeneous reactor of comparable size. A mass balance analysis revealed that the heterogeneous design may reduce the number of fast reactors needed to close the current once-through light water reactor fuel cycle.

  10. Water shielding nuclear reactor container

    International Nuclear Information System (INIS)

    The reactor container of the present invention contains a reactor pressure vessel, and has double steel plate walls endurable to elevated inner pressure and keeping airtightness, and shielding water is filled inside from a water injection port. It is endurable to a great inner pressure satisfactorily and keep airtightness by the two spaced relatively thin steel plates. It exhibits radiation shielding effect by filling water substantially the same as that of a conventional reactor container made of iron reinforced concretes. Then, it is no more necessary to use concretes for the construction of the reactor container, which shortens the term of the construction, and saves the construction cost. In addition, a cooling effect for the reactor container is provided. Syphons are disposed contiguously to a water injection port and the top end of the syphon is immersed in an equipment temporarily storage pool, and further, pipelines are connected to the double steel plate walls or the syphons for supplying shielding water to enhance the cooling effect. (N.H.)

  11. Moving ring reactor 'Karin-1'

    International Nuclear Information System (INIS)

    The conceptual design of a moving ring reactor ''Karin-1'' has been carried out to advance fusion system design, to clarify the research and development problems, and to decide their priority. In order to attain these objectives, a D-T reactor with tritium breeding blanket is designed, a commercial reactor with net power output of 500 MWe is designed, the compatibility of plasma physics with fusion engineering is demonstrated, and some other guideline is indicated. A moving ring reactor is composed mainly of three parts. In the first formation section, a plasma ring is formed and heated up to ignition temperature. The plasma ring of compact torus is transported from the formation section through the next burning section to generate fusion power. Then the plasma ring moves into the last recovery section, and the energy and particles of the plasma ring are recovered. The outline of a moving ring reactor ''Karin-1'' is described. As a candidate material for the first wall, SiC was adopted to reduce the MHD effect and to minimize the interaction with neutrons and charged particles. The thin metal lining was applied to the SiC surface to solve the problem of the compatibility with lithium blanket. Plasma physics, the engineering aspect and the items of research and development are described. (Kako, I.)

  12. Economic analysis of nuclear reactors

    International Nuclear Information System (INIS)

    The report presents several methods for estimating the power costs of nuclear reactors. When based on a consistent set of economic assumptions, total power costs may be useful in comparing reactor alternatives. The principal items contributing to the total power costs of a nuclear power plant are: (1) capital costs, (2) fuel cycle costs, (3) operation and maintenance costs, and (4) income taxes and fixed charges. There is a large variation in capital costs and fuel expenses among different reactor types. For example, the standard once-through LWR has relatively low capital costs; however, the fuel costs may be very high if U3O8 is expensive. In contrast, the FBR has relatively high capital costs but low fuel expenses. Thus, the distribution of expenses varies significantly between these two reactors. In order to compare power costs, expenses and revenues associated with each reactor may be spread over the lifetime of the plant. A single annual cost, often called a levelized cost, may be obtained by the methods described. Levelized power costs may then be used as a basis for economic comparisons. The paper discusses each of the power cost components. An exact expression for total levelized power costs is derived. Approximate techniques of estimating power costs will be presented

  13. Simplifying Microbial Electrosynthesis Reactor Design

    Directory of Open Access Journals (Sweden)

    Cloelle G.S. Giddings

    2015-05-01

    Full Text Available Microbial electrosynthesis, an artificial form of photosynthesis, can efficiently convert carbon dioxide into organic commodities; however, this process has only previously been demonstrated in reactors that have features likely to be a barrier to scale-up. Therefore, the possibility of simplifying reactor design by both eliminating potentiostatic control of the cathode and removing the membrane separating the anode and cathode was investigated with biofilms of Sporomusa ovata, which reduces carbon dioxide to acetate. In traditional ‘H-cell’ reactors, where the anode and cathode chambers were separated with a proton-selective membrane, the rates and columbic efficiencies of microbial electrosynthesis remained high when electron delivery at the cathode was powered with a direct current power source rather than with a poteniostat-poised cathode utilized in previous studies. A membrane-less reactor with a direct-current power source with the cathode and anode positioned to avoid oxygen exposure at the cathode, retained high rates of acetate production as well as high columbic and energetic efficiencies. The finding that microbial electrosynthesis is feasible without a membrane separating the anode from the cathode, coupled with a direct current power source supplying the energy for electron delivery, is expected to greatly simplify future reactor design and lower construction costs.

  14. Spherical tokamak research for fusion reactor

    International Nuclear Information System (INIS)

    Between ITER and the commercial fusion reactor, there are many technological problems to be solved such as cost, neutron and steady-state operation. In the conceptual design of VECTOR and Slim CS reactors it was shown that the key is 'low aspect ratio'. The spherical tokamak (ST) has been expected as the base for fusion reactors. In US, ST is considered as a non-superconducting reactor for use in the neutron irradiation facility. Conceptual design of the superconducting ST reactor is conducted in Japan and Korea independently. In the present article, the prospect of the ST reactor design is discussed. (author)

  15. Fast breeder reactors an engineering introduction

    CERN Document Server

    Judd, A M

    1981-01-01

    Fast Breeder Reactors: An Engineering Introduction is an introductory text to fast breeder reactors and covers topics ranging from reactor physics and design to engineering and safety considerations. Reactor fuels, coolant circuits, steam plants, and control systems are also discussed. This book is comprised of five chapters and opens with a brief summary of the history of fast reactors, with emphasis on international and the prospect of making accessible enormous reserves of energy. The next chapter deals with the physics of fast reactors and considers calculation methods, flux distribution,

  16. Utilisation of thorium in reactors

    Science.gov (United States)

    Anantharaman, K.; Shivakumar, V.; Saha, D.

    2008-12-01

    India's nuclear programme envisages a large-scale utilisation of thorium, as it has limited deposits of uranium but vast deposits of thorium. The large-scale utilisation of thorium requires the adoption of closed fuel cycle. The stable nature of thoria and the radiological issues associated with thoria poses challenges in the adoption of a closed fuel cycle. A thorium fuel based Advanced Heavy Water Reactor (AHWR) is being planned to provide impetus to development of technologies for the closed thorium fuel cycle. Thoria fuel has been loaded in Indian reactors and test irradiations have been carried out with (Th-Pu) MOX fuel. Irradiated thorium assemblies have been reprocessed and the separated 233U fuel has been used for test reactor KAMINI. The paper highlights the Indian experience with the use of thorium and brings out various issues associated with the thorium cycle.

  17. Thermochemical data for reactor materials

    International Nuclear Information System (INIS)

    This report describes a computer database of thermochemical properties of nuclear reactor materials to be used for source term calculations in reactor accident codes. In the first part, the structure and the content of the computer file is described. In the second part a set of thermochemical data is presented pertaining to chemical reactions occurring during severe nuclear reactor accidents and involving fuel (uranium dioxide), fission products and structural materials. These data are complementary to those collected in the databook recently published by Cordfunke and Potter after a study supported by the Commission of the European Communities. The present data were collected from review articles and databanks and follow a discussion on the uncertainties and errors involved in the calculation of complex chemical equilibria in the extrapolated temperature range

  18. Reactor vessel stud thread protector

    International Nuclear Information System (INIS)

    This patent describes a stud thread protector for a nuclear reactor pressure vessel. The vessel has a removable closure head, the closure head being sealingly engaged with the pressure vessel by a plurality of stud bolts, an upper end thereof having a threaded section for threadingly engaging a nut and a vertical bore being disposed within the stud bolt. The stud thread protector encloses the exposed upper portion of the bolt and associated nut projecting above the closure head. The reactor vessel stud thread protector is comprised of: a tubular wall portion being opened at its lower end and substantially closed at its upper end; a drip pan associated with the outer surface of the protector, the drip pan being disposed radially inwardly with respect to the outer periphery of the vessel head, whereby the drip pan collects any fluid being emitted from the reactor vessel; and means for fastening the stud thread protector to an associated stud

  19. Coolant recirculation device for reactors

    International Nuclear Information System (INIS)

    Purpose: To surely remove gases in coolants by the provision of a gas separator having a coolant stay chamber in the midway of coolant flow circuit. Constitution: In an LMFBR type reactor, a gas separator for taking out incompressible gases contained in coolants is provided in the midway of coolant flow circuit comprising a coolant flowing pipeway connected to a reactor, a heat exchange and a coolant recycling pump. The gas separator comprises a vessel-shaped coolant stay chamber, inlet and exit ports of coolants opened to the stay chamber, and a take out port for taking out gases separated from the coolants in the stay chamber. Since the incompressible gases in the coolants have lower density than the coolants, they are collected in the upper cover gas plenum and can surely be eliminated to thereby prevent the gases from flowing into the reactor. (Kawakami, Y.)

  20. The Extrap fusion reactor concept

    International Nuclear Information System (INIS)

    ABSTRACT A study has recently been initiated to assess the fusion reactor potential of the Extrap high-beta toroidal z-pinch concept. A reactor model is defined that fullfills certain economic and operational criteria that are characteristic of compact toroidal systems, including moderately large electric power output, high power density, high first wall loading, and simple construction. This model is applied to Extrap, and a 1000 MWe reference reactor having a first wall neutron loading of 10 MW/m2 is outlined. The minor plasma radius is 1.5 m, the major radius 4.5 m and the pinch current 10 MA. A 0.7 m thick blanket/refletor/shield is chosen to achieve sufficient breeding of tritium, good energy multiplication, and shielding of normal copper coils. (author). 12 refs.; 3 figs.; 1 tab

  1. On fast reactor kinetics studies

    Energy Technology Data Exchange (ETDEWEB)

    Seleznev, E. F.; Belov, A. A. [Nuclear Safety Inst. of the Russian Academy of Sciences IBRAE (Russian Federation); Matveenko, I. P.; Zhukov, A. M.; Raskach, K. F. [Inst. for Physics and Power Engineering IPPE (Russian Federation)

    2012-07-01

    The results and the program of fast reactor core time and space kinetics experiments performed and planned to be performed at the IPPE critical facility is presented. The TIMER code was taken as computation support of the experimental work, which allows transient equations to be solved in 3-D geometry with multi-group diffusion approximation. The number of delayed neutron groups varies from 6 to 8. The code implements the solution of both transient neutron transfer problems: a direct one, where neutron flux density and its derivatives, such as reactor power, etc, are determined at each time step, and an inverse one for the point kinetics equation form, where such a parameter as reactivity is determined with a well-known reactor power time variation function. (authors)

  2. Integral fast reactor safety features

    International Nuclear Information System (INIS)

    The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: (1) a pool-type primary system, (2) an advanced ternary alloy metallic fuel, and (3) an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by (1) the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and (2) a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents

  3. Research reactor education and training

    International Nuclear Information System (INIS)

    CORYS T.E.S.S. and TECHNICATOME present in this document some of the questions that can be rightfully raised concerning education and training of nuclear facilities' staffs. At first, some answers illustrate the tackled generic topics: importance of training, building of a training program, usable tools for training purposes. Afterwards, this paper deals more specifically with research reactors as an actual training tool. The pedagogical advantages they can bring are illustrated through an example consisting in the description of the AZUR facility training capabilities followed by the detailed experiences CORYS T.E.S.S. and TECHNICATOME have both gathered and keeps on gaining using research reactors for training means. The experience shows that this incomparable training material is not necessarily reserved to huge companies or organisations' numerous personnel. It offers enough flexibility to be adapted to the specific needs of a thinner audience. Thus research reactor staffs can also take advantages of this training method. (author)

  4. Prospects for toroidal fusion reactors

    International Nuclear Information System (INIS)

    Work on the International Thermonuclear Experimental Reactor (ITER) tokamak has refined understanding of the realities of a deuterium-tritium (D-T) burning magnetic fusion reactor. An ITER-like tokamak reactor using ITER costs and performance would lead to a cost of electricity (COE) of about 130 mills/kWh. Advanced tokamak physics to be tested in the Toroidal Physics Experiment (TPX), coupled with moderate components in engineering, technology, and unit costs, should lead to a COE comparable with best existing fission systems around 60 mills/kWh. However, a larger unit size, ∼2000 MW(e), is favored for the fusion system. Alternative toroidal configurations to the conventional tokamak, such as the stellarator, reversed-field pinch, and field-reversed configuration, offer some potential advantage, but are less well developed, and have their own challenges

  5. A tubular focused sonochemistry reactor

    Institute of Scientific and Technical Information of China (English)

    ZHOU GuangPing; LIANG ZhaoFeng; LI ZhengZhong; ZHANG YiHui

    2007-01-01

    This paper presents a new sonochemistry reactor, which consists of a cylindrical tube with a certain length and piezoelectric transducers at tube's end with the longitudinal vibration. The tube can effectively transform the longitudinal vibration into the radial vibration and thereby generates ultrasound. Furthermore, ultrasound can be focused to form high-intensity ultrasonic field inside tube. The reactor boasts of simple structure and its whole vessel wall can radiate ultrasound so that the electroacoustic transfer efficiency is high. The focused ultrasonic field provides good condition for sonochemical reaction. The length of the reactor can be up to 2 meters, and liquids can pass through it continuously, so it can be widely applied in liquid processing such as sonochemistry.

  6. Nuclear Reactor Engineering Analysis Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Carlos Chavez-Mercado; Jaime B. Morales-Sandoval; Benjamin E. Zayas-Perez

    1998-12-31

    The Nuclear Reactor Engineering Analysis Laboratory (NREAL) is a sophisticated computer system with state-of-the-art analytical tools and technology for analysis of light water reactors. Multiple application software tools can be activated to carry out different analyses and studies such as nuclear fuel reload evaluation, safety operation margin measurement, transient and severe accident analysis, nuclear reactor instability, operator training, normal and emergency procedures optimization, and human factors engineering studies. An advanced graphic interface, driven through touch-sensitive screens, provides the means to interact with specialized software and nuclear codes. The interface allows the visualization and control of all observable variables in a nuclear power plant (NPP), as well as a selected set of nonobservable or not directly controllable variables from conventional control panels.

  7. Nuclear reactors and fuel cycle

    International Nuclear Information System (INIS)

    The Center for Nuclear Engineering has shown expertise in the field of nuclear and energy systems ad correlated areas. Due to the experience obtained over decades in research and technological development at Brazilian Nuclear Program personnel has been trained and started to actively participate in the design of the main system that will compose the Brazilian Multipurpose Reactor (RMB) which will make Brazil self-sufficient in the production of radiopharmaceuticals. The institution has participated in the monitoring and technical support concerning the safety, licensing and modernization of the research reactors IPEN/MB-01 and IEA-R1. The Nuclear Fuel Center is responsible for the production of the nuclear fuel necessary for the continuous operation of the IEA-R1 research reactor. Development of new fuel technologies is also a permanent concern

  8. Plasma reactor waste management systems

    Science.gov (United States)

    Ness, Robert O., Jr.; Rindt, John R.; Ness, Sumitra R.

    1992-01-01

    The University of North Dakota is developing a plasma reactor system for use in closed-loop processing that includes biological, materials, manufacturing, and waste processing. Direct-current, high-frequency, or microwave discharges will be used to produce plasmas for the treatment of materials. The plasma reactors offer several advantages over other systems, including low operating temperatures, low operating pressures, mechanical simplicity, and relatively safe operation. Human fecal material, sunflowers, oats, soybeans, and plastic were oxidized in a batch plasma reactor. Over 98 percent of the organic material was converted to gaseous products. The solids were then analyzed and a large amount of water and acid-soluble materials were detected. These materials could possibly be used as nutrients for biological systems.

  9. A compact Tokamak transmutation reactor

    Institute of Scientific and Technical Information of China (English)

    QiuLi-Jian; XiaoBing-Jia

    1997-01-01

    The low aspect ration tokamak is proposed for the driver of a transmutation reactor.The main parameters of the reactor core,neutronic analysis of the blanket are given>the neutron wall loading can be lowered from the magnitude order of 1 MW/m2 to 0.5MW/m2 which is much easier to reach in the near future,and the transmutation efficiency (fission/absorption ratio)is raised further.The blanket power density is about 200MW/m3 which is not difficult to deal with.The key components such as diverter and center conductor post are also designed and compared with conventional TOkamak,Finally,by comparison with the other drivers such as FBR,PWR and accelerator,it can be anticipated that the low aspect ratio transmutation reactor would be one way of fusion energy applications in the near future.

  10. Research Reactors Types and Utilization

    International Nuclear Information System (INIS)

    A nuclear reactor, in gross terms, is a device in which nuclear chain reactions are initiated, controlled, and sustained at a steady rate. The nuclei of fuel heavy atoms (mostly 235U or 239Pu), when struck by a slow neutron, may split into two or more smaller nuclei as fission products,releasing energy and neutrons in a process called nuclear fission. These newly-born fast neutrons then undergo several successive collisions with relatively low atomic mass material, the moderator, to become thermalized or slow. Normal water, heavy water, graphite and beryllium are typical moderators. These neutrons then trigger further fissions, and so on. When this nuclear chain reaction is controlled, the energy released can be used to heat water, produce steam and drive a turbine that generates electricity. The fission process, and hence the energy release, are controlled by the insertion (or extraction) of control rods through the reactor. These rods are strongly neutron absorbents, and thus only enough neutrons to sustain the chain reaction are left in the core. The energy released, mostly in the form of heat, should be continuously removed, to protect the core from damage. The most significant use of nuclear reactors is as an energy source for the generation of electrical power and for power in some military ships. This is usually accomplished by methods that involve using heat from the nuclear reaction to power steam turbines. Research reactors are used for radioisotope production and for beam experiments with free neutrons. Historically, the first use of nuclear reactors was the production of weapons grade plutonium for nuclear weapons. Currently all commercial nuclear reactors are based on nuclear fission. Fusion power is an experimental technology based on nuclear fusion instead of fission.

  11. Spatial Kinetics in Fast Reactors

    International Nuclear Information System (INIS)

    Reactor neutronic calculations designed for calculating of unsteady processes in a real 3D geometry require processing of a large amount of information. They cannot consist of simple models, as they should reflect the processes of variations of all local reactor characteristics. The model complexity and the significant time needed for numerical solution of neutron-transport equations limit the choice of methods that can achieve the required accuracy. Thus there is an urgent need for the development of various methods enabling the solution of unsteady neutron-transport equations and estimates of their errors, spent time and consistency with the experimental data. (author)

  12. STARFIRE: a commercial tokamak reactor

    International Nuclear Information System (INIS)

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

  13. PITR: Princeton Ignition Test Reactor

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-01

    The principal objectives of the PITR - Princeton Ignition Test Reactor - are to demonstrate the attainment of thermonuclear ignition in deuterium-tritium, and to develop optimal start-up techniques for plasma heating and current induction, in order to determine the most favorable means of reducing the size and cost of tokamak power reactors. This report describes the status of the plasma and engineering design features of the PITR. The PITR geometry is chosen to provide the highest MHD-stable values of beta in a D-shaped plasma, as well as ease of access for remote handling and neutral-beam injection.

  14. Fundamentals of Nuclear Reactor Physics

    CERN Document Server

    Lewis, E E

    2008-01-01

    This new streamlined text offers a one-semester treatment of the essentials of how the fission nuclear reactor works, the various approaches to the design of reactors, and their safe and efficient operation. The book includes numerous worked-out examples and end-of-chapter questions to help reinforce the knowledge presented. This textbook offers an engineering-oriented introduction to nuclear physics, with a particular focus on how those physics are put to work in the service of generating nuclear-based power, particularly the importance of neutron reactions and neutron behavior. Engin

  15. Reactor production of Thorium-229.

    Science.gov (United States)

    Hogle, Susan; Boll, Rose Ann; Murphy, Karen; Denton, David; Owens, Allison; Haverlock, Tamara J; Garland, Marc; Mirzadeh, Saed

    2016-08-01

    Limited availability of (229)Th for clinical applications of (213)Bi necessitates investigation of alternative production routes. In reactor production, (229)Th is produced from neutron transmutation of (226)Ra, (228)Ra, (227)Ac and (228)Th. Irradiations of (226)Ra, (228)Ra, and (227)Ac targets at the Oak Ridge National Laboratory High Flux Isotope Reactor result in yields of (229)Th at 26 days of 74.0±7.4MBq/g, 260±10MBq/g, and 1200±50MBq/g, respectively. Intermediate radionuclide yields and cross sections are also studied. PMID:27163437

  16. Space reactor preliminary mechanical design

    International Nuclear Information System (INIS)

    An analysis was performed on the SABRE reactor space power system to determine the effect of the number and size of heat pipes on the design parameters of the nuclear subsystem. Small numbers of thin walled heat pipes were found to give a lower subsystem mass, but excessive fuel swelling resulted. The SP-100 preliminary design uses 120 heat pipes because of acceptable fuel swelling and a minimum nuclear subsystem mass of 1875 kg. Salient features of the reactor preliminary design are: individual fuel modules, ZrO2 block core mounts, bolted collar fuel module restraints, and a BeO central plug

  17. Reactor shutdown delays medical procedures

    Science.gov (United States)

    Gwynne, Peter

    2008-01-01

    A longer-than-expected maintenance shutdown of the Canadian nuclear reactor that produces North America's entire supply of molybdenum-99 - from which the radioactive isotopes technetium-99 and iodine-131 are made - caused delays to the diagnosis and treatment of thousands of seriously ill patients last month. Technetium-99 is a key component of nuclear-medicine scans, while iodine-131 is used to treat cancer and other diseases of the thyroid. Production eventually resumed, but only after the Canadian government had overruled the Canadian Nuclear Safety Commission (CNSC), which was still concerned about the reactor's safety.

  18. Power Reactor Information System (PRIS)

    International Nuclear Information System (INIS)

    The IAEA has been collecting Operating Experience data for Nuclear Power Plants of the IAEA Member States since 1970. In order to facilitate an analysis of nuclear power plant performance as well as to produce relevant publications, all previously collected data supplied from the questionnaires were computerized in 1980 and the Power Reactor Information System was implemented. PRIS currently contains production records for the years up to and including 1990 and about 98% of the reactors-years operating experience in the world is contained in PRIS. (orig.)

  19. Small intrinsically safe reactor implications

    International Nuclear Information System (INIS)

    Reviewing the history of nuclear power, it is found that peaceful uses of nuclear power are children of the war-like atom. Importance of special growth in a shielded environment is emphasized to exploit fully the advantages of nuclear power. Nuclear power reactors must be safe for their assimilation into society from the points of view of both technology and social psychology. ISR/ISER is identified as a missing link in the development of nuclear power reactors from this perspective and advocated for international development and utilization, being unleashed from the concerns of politicization, safety, and proliferation

  20. Research reactor modernization and refurbishment

    International Nuclear Information System (INIS)

    Many recent, high profile research reactor unplanned shutdowns can be directly linked to different challenges which have evolved over time. The concept of ageing management is certainly nothing new to nuclear facilities, however, these events are highlighting the direct impact unplanned shutdowns at research reactors have on various stakeholders who depend on research reactor goods and services. Provided the demand for these goods and services remains strong, large capital projects are anticipated to continue in order to sustain future operation of many research reactors. It is within this context that the IAEA organized a Technical Workshop to launch a broader Agency activity on research reactor modernization and refurbishment (M and R). The workshop was hosted by the operating organization of the HOR Research Reactor in Delft, the Netherlands, in October 2006. Forty participants from twenty-three countries participated in the meeting: with representation from Africa, Asia Pacific, Eastern Europe, North America, South America and Western Europe. The specific objectives of this workshop were to present facility reports on completed, existing and planned M and R projects, including the project objectives, scope and main characteristics; and to specifically report on: - the project impact (planned or actual) on the primary and key supporting motivation for the M and R project; - the project impact (planned or actual) on the design basis, safety, and/or regulatory-related reports; - the project impact (planned or actual) on facility utilization; - significant lessons learned during or following the completion of M and R work. Contributions from this workshop were reviewed by experts during a consultancy meeting held in Vienna in December 2007. The experts selected final contributions for inclusion in this report. Requests were also distributed to some authors for additional detail as well as new authors for known projects not submitted during the initial 2006 workshop