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Sample records for merje kgu anneliis

  1. Anneliis Kõiv jälle esimees / Tõnis Tõnisson

    Index Scriptorium Estoniae

    Tõnisson, Tõnis, 1945-

    2009-01-01

    29. mail valis Eesti Kultuurkapitali Raplamaa ekspertgrupi uus koosseis oma esimeheks Anneliis Kõivu, aseesimeheks Age Rebeli. Lisaks neile kuuluvad grupi uude koosseisu Darja Lehtsalu, Andres Elmik ja Riho Pohla

  2. Paberist arhitektuur / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    2007-01-01

    Skandinaaviamaade ja Jaapani lähenemisest arhitektuuri- ning disainimaailmas. Soomlaste pabermassist ehitatud paviljonist Milano messil, arhitekt Shigeru Ban. Soome firma Artek puidust salongist Turus. Paberi kasutamisest majaehitusmaterjalina. Shigeru Bani loomingust

  3. Kaks vastandit / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    2005-01-01

    Saksa disainerist Konstantin Grcic'ist (s. 1965), kes kasutab materjalidest palju plasti (üks kuulsamaid töid on sõrestiktool "stool one"). Egiptuses sündinud Kanadas üles kasvanud disainerist Karim Rashid'ist (s. 1960), kelle lemmikmaterjaliks on samuti plast. Ühistööna valminud ideaalkodu installatsioonist Kölni mööblimessil 2003. a.

  4. Kolmnurgad vanalinna foonil / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    2011-01-01

    Arhitektuuribüroos Kosmos projekteeritud äripindadega kortermajast Tallinna vanalinnas Vana-Viru ja Aia tänava nurgal. Ühiskondlikud siseruumid kujundas Ivi-Els Schneider, ühe korteri Aivar Mühlbach, Lounge Butterfly Loreida Hein

  5. Rahva informeeritus Riigikogust / Merje Meisalu

    Index Scriptorium Estoniae

    Meisalu, Merje

    2002-01-01

    Autor vaatleb sotsiaal- ja turu-uuringute firma Saar Poll poolt Riigikogu Kantselei tellimusel alates 1995. aastast regulaarselt läbi viidavate uuringute "Riik ja rahvas" tulemuste alusel, kuidas on muutunud inimeste informeeritus Riigikogu tööst ja ülesannetest ning oma kodanikuõigustest. Ülevaade peamistest infoallikatest Riigikogu tegevuse kohta info hankimisel. Diagrammid.

  6. Raua taltsutajad / Heigo Jelle ; interv. Anneliis Aunapuu

    Index Scriptorium Estoniae

    Jelle, Heigo, 1963-

    1998-01-01

    Unustatud sepatöö taas elluärkamisest. H. Jelle kaasaja sepa tööst, tellimustest, raua rollist ajaloos, heast maitsest sepatöös (Eesti sepatöö parimate näidetena toodud Maire Morgen-Hääle sepised), arhitektuuriga seotud ja iseseisvatest sepistest, materjali markidest, oma töödest.

  7. Palmse supelmaja taas kasutusel / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    1998-01-01

    Lahemaa Rahvuspark rentis poolelioleva supelmaja perekond Ong'ile, kes ehituse lõpetas, hoone sisustas ja avas kohvik-restorani 'Freifrau Isabella'. Sisekujundus autor Leila Pärtelpoeg nimetab sisekujundust palladiaanlikuks. Tänu AEL ja Tartu Kunstikooliga sõlmitud lepingule sai supelmaja kõrgetasemelise maalritöö. Maalingud eesruumis ئ Eve Erman. Sepisvalgustid ئ Ülo Sepp. Pika-laua-saalis oleva von Pahlenite vapi valmistas Andres Sapar. Inkrusteeritud puhvetkapi taastas Urmas Ong.

  8. Eestlased rajavad Veneetsiasse gaasitoru / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    2008-01-01

    Veneetsia arhitektuuribiennaalil Eestit esindav arhitektuuribüroo Salto töögrupp (Maarja Kask, Ralf Lõoke, Neeme Külm) rajab sinna gaasijuhtme NordStream sümboli. 63 meetri pikkune skulpturaalne vorm kulgeb näitusepaviljonide vahel, biennaaliala peamise käigutee kohal. Kommenteerivad Ingrid Ruudi, Maarja Kask, Ralf Lõoke

  9. Soliidne korter 'heas' majas / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    1998-01-01

    Kaks korterit on üheks liidetud. Sisearhitekt Taisi Kadarik on loonud kaasaegse interjööri, milles on tunda kolmekümnendate hõngu. Elu- ja söögituba eraldavad lükanduksed. Pehme mööbli valmistas T. Kadariku jooniste järgi PIN-Disain. Vaibad Peeter Kuutmalt. vitraaž Valev Seinalt. Köögis 'Snaidero' komplekt. Kappide liuguksed firmalt 'Rait Mööbel'. Magamis- ja vannitoast. Remondi eest vastutas firma 'Koger ja Sumberg'

  10. Luigekaelses majas luigekaelsed toolid / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    2007-01-01

    Ameerika Ühendriikides asuva Milwaukee kunstimuuseumi juurdeehitisest Quadracci paviljonist. Hoone projekteeris hispaania arhitekt Santiago Calatrava, tema loomingust. Muuseumi toolide autor on hispaania disainer Jesus Gasca. 11 ill

  11. Religiooni roll Nõukogude okupatsiooni ajal / Merje Talvik

    Index Scriptorium Estoniae

    Talvik, Merje

    2009-01-01

    Eesti kaitseväe kaplan ja Eesti Apostlik-Õigeusu Kiriku diakon Andrei Sõtšov kaitses Tartu ülikooli usuteaduskonnas doktoritöö "Eesti õigeusu piiskopkond nõukogude religioonipoliitika mõjuväljas 1954-1964"

  12. PWR type overpower tests at 1620 GJ/KGU (18,800 MWD/MTU)

    International Nuclear Information System (INIS)

    Knudsen, P.; Bagger, C.; Carlsen, H.

    1979-01-01

    Three PWR type test fuel pins accumulated a burnup of 1620 GJ/kgU at heat loads decreasing from 45 to 28 kW/m (avg. test levels). One pin was ramped to 43 kW/m at 31 W/m/s; after 15 ks the power was increased to 45 kW/m and held constant for 1.9 Ms without failure indication. The other two pins were ramped to 44 kW/m at 23 W/m/s and then to 49 kW/m in a further 1.2 ks; both failed after max. 360 s. The post-irradiation examination revealed large stress-corrosion (SCC) type cladding cracks. Other cracks, down to a few μm deep, were probably early stages of large SCC cracks. Fission gas release in the intact pin was as high as 42% and estimated to be much lower for the two failed pins

  13. The subcritical mass limit, 2.4 kgU, for the JCO's precipitation tank

    International Nuclear Information System (INIS)

    Komuro, Yuichi

    1999-01-01

    The critical safety on the precipitation tank in JCO Corporation forming a critical accident in September 30, 1999 had to be guaranteed by limiting amount of uranium contained into charging solution. The limited value of uranic mass in the precipitation tank was determined to be 2.4 kg, and from the dissolution tank positioned at upstream of this tank a solution not excess amount of solution to this value was designed to be transferred. In the 2nd Accident Survey Committee, there were found some discussions on a leading method of this value. In order to answer some requirements for this, here was described on outlines on U.S. Nuclear Safety Guide, TID-7016 Rev. 1, leading method of the limited value in 2.4 kg, and safety tolerance. As a result of reinvestigation, as it was confirmed that 2.4 kg in the limited amount contained an sufficient safety tolerance qualitatively and in comparison with already critical data. (G.K.)

  14. Eesti ilmumine Hiina rahvale - EXPO 2010 paviljon Shanghais / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    2009-01-01

    Shanghai EXPO Eesti paviljoni konkursi võidutööst "Savecity.org", autorid Ionel Lehari, Kristian Paljasma, Illimar Truverk, Priit Hamer, Janno Roos, Andres Labi. Premeeritud tööd. Žürii koosseis. Konkursitöödest on avatud näitus Eesti Arhitektuurimuuseumis 24. maini

  15. Põnevusõpe ehk uutmoodi konverentsid / Anne-Liis Arulo

    Index Scriptorium Estoniae

    Arulo, Anne-Liis

    2005-01-01

    EBS Juhtimiskoolituse Keskuse rahvusvaheliste projektide juht Baltic Development Associatoni 3. aastakonverentsi korraldamisest. Artikkel on valminud koostöös Pathway Guidance Europe asutaja ja partneri Uwe Weissflogiga

  16. Ainuke püsiv asi on muutumine / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    2008-01-01

    Taani audiovideotehnikat disainivast firmast Jacob Jensen Design. Jacob Jenseni (sünd. 1926) asutatud büroo loomingut tutvustab tema poeg Timothy Jacob Jensen (sünd. 1962). Eesti disaini tasemest, Jaapani disainitoodangust. Esikaanel ja lk. B3 fotod Timothy Jacob Jensenist

  17. Kuidas ehitati Mercedes-Benzi muuseumi / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    2007-01-01

    Betoonipäeva tähistamiseks toimus Tallinna ülikoolis seminar. Üheks esinejaks oli kutsutud sakslaste rakisefirma Peri esindaja, ehitusinsener Jochen Köhler, kes tutvustas Mercedes-Benzi muuseumihoone valmimisprotsessi. Lisaks vestlus Jochen Köhleriga

  18. Idee ja teostuse vahel, kvaliteeti otsimas / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    2009-01-01

    Tallinna 5. rakenduskunsti triennaali "Know How" peaväljapanek Eesti Tarbekunsti- ja Disainimuuseumis 21. veebruarini 2010. Kujunduse autorid Ott Kadarik ja Tuuli Aule. Lühidalt Pavel Sidorenko ja lätlase Rihards Funtsi töödest

  19. Graafiline betoon ehk kunst otse tehasest / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    2009-01-01

    Uudse tehnoloogiaga valmistatud betoonist. Esimese graafilise betooni näidiseks Eestis on Maanteemuuseumis valmiv väliala (arhitektuur büroolt Salto), kus seinalementidele on jäädvustatud suurendustena vanad fotod Eestimaa maastikest (kujundus Laika, Belka & Strelka). 28. oktoobril Tallinnas toimunud Betooni Tehnoloogiapäeva seminarist. Küsimustele vastavad E-Betoonelemendi esindajad

  20. Tallinna rannaala üldplaneering / Kaur Lass, Merje Muiso

    Index Scriptorium Estoniae

    Lass, Kaur, 1973-

    2004-01-01

    Paljassaare ja Russalka vahelise rannaala üldplaneeringu kehtestamist Tallinna Linnavalitsuse poolt on oodata 2004. a. kevadel. Vaatluse all: kesklinn, tööstuspiirkond, Paljassaare poolsaar, mere ja linna side, linnaehituslike reeglite seadmine, detailplaneeringute koostamise reeglid, arhitektuurikonkursid, sadamad, infrastruktuur

  1. Vahetuspere isa osutus seksuaalseks ahistajaks / Merje Pors ; kommenteerinud Oliver Kontram

    Index Scriptorium Estoniae

    Pors, Merje

    2011-01-01

    Vahetusõpilase ahistamise juhtumist Argentiinas, kus vahetuspere isa kuritarvitas seksuaalselt vahetusõpilast. Vahetusprogrammide kaudu välismaale õppima minejate arvu vähenemisest, mistõttu on programmid sunnitud ümber orienteeruma ja rohkem välisõpilasi Eestisse tooma

  2. Abieluakti koostamine EELKs - õigus või kohustus? / Merje Talvik

    Index Scriptorium Estoniae

    Talvik, Merje

    2008-01-01

    Vaimulike õigusest pärast siseministeeriumi korraldatava koolituse läbimist riigi nimel abielu sõlmida. Kommenteerivad Kristjan Luhamets, Rein Schihalejev, Mare Palgi, Illimar Toomet, Mart Jaanson, Anna-Liisa Vaher ja Kalle Gaston

  3. Ajalugu teatriaastal - muus keeles tehtud ja tehtavast teatrist Eestis / Anne-Liis Maripuu

    Index Scriptorium Estoniae

    Maripuu, Anne-Liis

    2006-01-01

    Eestis tegutsenud saksakeelsest teatrist (August von Kotzebue tegevusest Tallinnas, ehitas esimese pidevalt töötava asjaarmastajate-teatri, 1804.a. loodud esimesest professionaalsest teatritrupist Tallinnas, Tartu saksa teatrist), venekeelsest teatrist (1948.a. asutatud Vene Draamateatrist, lavastajatest) ja võrukeelsest teatrist Eestis, millele pani aluse Ingo Normet 1993. a., lavastades EMTA lavakunstikooli 16. lennuga Madis Kõivu ja Aivo Lõhmuse kirjutatud näidendi "Põud ja vihm..." Võrukeelset teatrit edendab Võru Teatriateljee (endine Võru Harrastusteater) ja 16. lennu lõpetanud Ain Mäeots, Riho Kütsar, Margus Jaanovitsh ja Merle Jääger

  4. Hotell Bernhard, šveitsi miraaž Nuustakul / Anneliis Aunapuu

    Index Scriptorium Estoniae

    Aunapuu, Anneliis

    1998-01-01

    Hotell 'Bernhard' Otepääl. Arhitekt Andres Lunge, sisearhitekt Taisi Kadarik. Kompleksi läbib erksinise ja telliskivikarva värvikontrast, millele lisandub hall. Kogu hoones vahelduvad eurolikud güprokpinnad krobelistega ja annavad teed klaasile, pakkudes suurepärast vaadet. Hotellis on terrassile avanev restoran ning suure basseini ja saun

  5. Arts & Lights ja DisainiÖÖ / Ilona Gurjanova ; interv. Anneliis Aunapuu

    Index Scriptorium Estoniae

    Gurjanova, Ilona, 1958-

    2008-01-01

    Tallinnas 26.-28. sept. 2008. a. toimuva rahvusvahelise disainifestivali eestvedajad, üritused, osalejad, külalised. Seminar "Disaineri roll rahvusliku kultuuripärandi loomisel" Estonia kammersaalis. Islandi disaini näitus "Made in Iceland" ja töötuba de-Ikea Kultuurikatlas. Laboratooriumi tänava moe- ja valgusshow. Disainioksjon Hobuveskis. Elustiilipoe Homeart disainikonkurss. Öö õu Raekoja platsil. Marko Ala loodud moodulsüsteemi esitlus Kultuurikatlas. Pecha Kucha vaba mikrofon Hobuveskis

  6. Esimene Teater Ö(ö)sel festival läks korda / Merje Pors

    Index Scriptorium Estoniae

    Pors, Merje

    2006-01-01

    15.-16. juulil Kuressaares ja Saare maakonnas toimunud Läänemere saari ühendavast festivalist "Teater Ö(ö)sel". Festivalist võtsid osa Rügeni, Alandi, Gotlandi, Hiiumaa ja Saaremaa teatritrupid

  7. Toward cooperative security? International integration and the construction of security in Estonia / Merje Kuus

    Index Scriptorium Estoniae

    Kuus, Merje

    2002-01-01

    Autor leiab, et Eesti ühinemine rahvusvaheliste organisatsioonidega on suures osas seotud julgeolekupoliitiliste kaalutlustega. Võimalikud ohud rahvuslikule julgeolekule ja võimalikud vastumeetmed nende vältimiseks

  8. Hakkajad noored said toetust välismaal õpingute jätkamiseks / Merje Pors

    Index Scriptorium Estoniae

    Pors, Merje

    2011-01-01

    Sihtasutus Archimedes andis 24. augustil 2011 Tallinna reaalkoolis toimunud üritusel välja kümme 4000 euro suurust preemiat andekatele noortele, kes alustavad või jätkavad bakalaureuseõpinguid maailma tunnustatud ülikoolides. Stipendiaate õnnitles ka president Toomas Hendrik Ilves

  9. Eesti on õnnetuste tõttu hukkuvate laste poolest esirinnas / Merje Pors

    Index Scriptorium Estoniae

    Pors, Merje

    2011-01-01

    Majandusliku Koostöö ja Arengu Organisatsiooni (OECD) värskest raportist "Doing Better for Families" selgub, et Eestis on aastatel 1997-2008 õnnetuste tagajärjel surma saanud 100 000 kuni 14-aastase lapse kohta enam poisse ja türdukuid kui üheski teises OECD liikmesriigis

  10. The Leech with a taste for oranges / Merje Järv-Griffiths

    Index Scriptorium Estoniae

    Järv-Griffiths, Merje

    2007-01-01

    Rockansamblist Leech (kontserdid 23. nov. klubis Rockstar's Tallinnas, 30. nov. Lutsu Teatris Tartus ja 21. dets. festivalil Green Christmas Rakveres), heliplaadist "Tram-O-Gram" (vt. www.leechband.net)

  11. Presidendi kantselei: Ilves ei üritanud sõjaraamatut tsenseerida / Merje Pors

    Index Scriptorium Estoniae

    Pors, Merje

    2011-01-01

    Presidendi kantselei lükkab ümber Briti ajalehe The Telegraph väite, nagu oleks president Toomas Hendrik Ilves avaldanud survet Toby Harndeni raamatu "Dead Men Risen: The Welsh Guards and the Real Story of Britain's War in Afghanistan "("Ülestõusnud surnud: Walesi kaardivägi ja tegelik lugu brittide sõjast Afganistanis") tsenseerimiseks

  12. Märkmeid Thbilisist / Tõnis Kimmel, Merje Müürisepp

    Index Scriptorium Estoniae

    Kimmel, Tõnis, 1977-

    2007-01-01

    Muljeid Thbilisi arhitektuurist. Hotellist "Iveria" (1967, arhitekt O. Kalandarishvili), Püha Kolmainu kirikust (2003), purskkaevudest, Teedeministeeriumi insenerikorpuse hoonest (1974, arhitektid G. Tshahhava, Z. Dzhalagania, T. Thilava jt.), Poliitharidusmaja fassaadist (1980, arhitekt A. Abramashvili, fassaad Z. Tsereteli), säilinud vanadest interjööridest. 6 värv. vaadet

  13. Raagi film lööb Euroopas laineid / Merje Pors

    Index Scriptorium Estoniae

    Pors, Merje

    2007-01-01

    Ilmar Raagi mängufilm "Klass" võitis 42. Karlovy Vary rahvusvahelise filmifestivalil kaks auhinda - ametliku kõrvalvõistlusprogrammi "East of the West" eripreemia "Special mention" ja Euroopa väärtfilmikinode keti Europa Cinemas preemia. Ka I. Raagi kommentaar

  14. Mets ja marutaud / Merje Ottson ; kommenteerinud Kalev Männiste, Kaja Kübar, Enel Niin

    Index Scriptorium Estoniae

    Ottson, Merje

    2011-01-01

    Marutõvest ja marutaudist. Rebaste ja kährikute marutaudi vastase vaktsineerimise mõjust loomade arvukuse kasvutegurina ning nende põhjustatud ohust lindude, peamiselt metsislaste, ja näriliste arvukusele ning jahimeeste osast rebaste ja kährikute arvukuse piirajana.

  15. Kellele EXPOrt? = EXPOrt for whom? / Tõnis Kimmel, Merje Müürisepp

    Index Scriptorium Estoniae

    Kimmel, Tõnis, 1977-

    2010-01-01

    Maailmanäituse EXPO 2010 eripärast. Viimase aastakümne arengutest Shanghais, maailmanäituse alast. Maailmanäituse teema "Parem linn, parem elu" käsitlemisest, oma sõnumi edastamisest. Suurbritannia (Thomas Heaterwick), Šveitsi (Buchner Bründler Architekten), Taani (Bjarke Ingels Group), Alžeeria, Hollandi (John Kormeling) ja Eesti paviljonidest, paremate linnaliste praktikate alast

  16. From threats to risk : the reconfiguration of security debates in the context of regional co-operation / Merje Kuus

    Index Scriptorium Estoniae

    Kuus, Merje

    2003-01-01

    Eesti julgeolek on viimasel ajal ümber mõtestatud kitsalt sõjalisest valdkonnast palju laiemale valdkonnale; kultuur, identiteet ning moraalsed väärtused on nihkunud kesksele kohale julgeolekuteemalistes diskussioonides

  17. Abieluakti koostamine EELKs - õigus või kohustus? / Kristjan Luhamets, Rein Schihalejev, Mare Palgi...[jt.] ; interv. Merje Talvik

    Index Scriptorium Estoniae

    2008-01-01

    Vastavalt perekonnaseaduse muudatustele on siseministeeriumi poolt korraldatava koolituse läbinud vaimulikul õigus abielu sõlmimiseks. Vaimulikud vastavad küsimusele, kuidas nad näevad perekonnaseisuametniku ja jumalasulase tööd ühendatuna. Lisatud: [koguduse vaimulikul on õigus keelduda abielu sõlmimisest, kui...

  18. Valge villa / Ilmar Heinsoo

    Index Scriptorium Estoniae

    Heinsoo, Ilmar, 1951-

    1999-01-01

    Eramu liigendus, ruumikujundus ja tehnilised näitajad. Villa projekteerija Arhitekti- ja inseneribüroo ARX OÜ, arhitekt Ilmar Heinsoo. Sisearhitektibüroo Lember & Padar, sisearhitekt Juta Lember. Kommenteerib Anneliis Aunapuu. 11 illustratsiooni

  19. Tartu Ülikool Tartu linnas = The University of Tartu in the city of Tartu / Kaja Pae, Merje Müürisepp

    Index Scriptorium Estoniae

    Pae, Kaja

    2011-01-01

    Maarjamõisa välja ja kesklinna hoonestu suhted. Ülikool ja kesklinn, ülikooli ruumiline imidž. Ülikooli ajalooline hoonestu. Tartu Ülikooli hoonete paiknemisega linnaruumis tegeldi 27. ja 28. aprillil 2010 toimunud Tartu linnafoorumil

  20. Hääletades läbi Eesti : ehk intervjuu kahe noorega, kelle jaoks loodus on sõber ja hääletamine nauding / Tea Jänes, Allan Kahar ; küsitlenud Merje Pors

    Index Scriptorium Estoniae

    Jänes, Tea

    2007-01-01

    Intervjuu tudengite igasuvise hääletusvõistluse "Kas tunned maad VII" kolmanda koha omanikega Tartu Ülikooli keskkonnatehnoloogia magistrandi Tea Jänese ja Luua Metsanduskoolis loodusretkede juhi ametit õppiva Allan Kahariga

  1. Ernst Enno etluskonkursil kõlas saja aasta tagune luule / Krista Kumberg

    Index Scriptorium Estoniae

    Kumberg, Krista, 1959-

    2007-01-01

    Läänemaal toimus maakondlik Ernst Ennole pühendatud etluskonkurss. E. Enno nimelise etluskonkursi 2007 "Saja aasta tagused luuletused" parimad etlejad olid Mike Richard Koch, Janno Allika, Hanna Ring, Karl Poll, Britta Sool, Antero Rea, Jennifer Cohen, Brita Kaljuvee, Eva-Maria Brock, Kaupo Engel, Liisi Räli, Laivi Kovalenko, Merje Viigand, Carmen Freimann, Rauno Punk, Maarja Palmiste

  2. Director läks ja küsis / Indrek Randveer, Evelyn Karming, Priit Palk ... [jt.

    Index Scriptorium Estoniae

    2010-01-01

    EMT teenindus- ja müügidirektor Indrek Randveer, Estraveli müügidirektor Evelyn Karming, ABC King/Nero/SHU/Suurtüki turundusjuht Anne-Liis Ostov, kohvik-restoran Crepp juhataja Priit Palk ja Sokos Hotel Viru kommunikatsioonijuht Peep Ehasalu vastavad küsimustele, mis puudutavad nende kogemusi keerukate ja absurdsete kliendikaebuste kohta

  3. Kolmas aed = The Third Garden / Martin Melioranski

    Index Scriptorium Estoniae

    Melioranski, Martin

    2006-01-01

    Aed ja eramu Meriväljal Viimsi ja Väina tee nurgal. Projekt: Arhitektuuriagentuur. Autorid: Inga Raukas, Toomas Tammis, Tarmo Teedumäe. Haljastuse konsultant Signe Peipman. Projekt 2005, valmis 2006. Aed ja eramu Naeri tänaval. Projekt: Kolm Pluss Üks Arhitektid. Autorid: Markus Kaasik, Andres Ojari, Ilmar Valdur, Merje Müürsepp, Kalle Komissarov (2002). Projekt 2002-2004, valmis 2005. Ill.: kaks plaani, 6 värv. vaadet

  4. Why do dismissed employees need art? / Margit Säde

    Index Scriptorium Estoniae

    Säde, Margit, 1984-

    2009-01-01

    "Koondatute kunsti keskus" Tallinna Postimajas 23.-30. aprillini 2009. Eesti Kunstiakadeemia üliõpilaste sotsiaalse kunstiprojekti eesmärgist, sellest osavõtust, dokumentaalfilmi õpikojast, mida viisid läbi Anna Škodenko, Anne-Liis Kogan ja Margit Säde. Valminud tööd ja projekti dokumentatsioon olid väljas detsembris 2009 avatud Anders Härmi kureeritud näitusel "Blue-Collar Blues" Tallinna Kunstihoones

  5. Uued agulimajad = New Suburb Houses / Andri Ksenofontov

    Index Scriptorium Estoniae

    Ksenofontov, Andri, 1962-

    2005-01-01

    Tallinna ajalooliste eeslinnade teke ja kujunemine. Agulite olukord tänapäeval ja haldus viimastel aastatel. Büroo 3+1 projekteeritud ühepereelamu Magasini kvartalis (arhitektid Andres Ojari, Markus Kaasik, Ilmar Valdur, Merje Müürisepp, Kalle Komissarov). Neljakorruseline elamu Õle t. 23/Härjapea t. 14, ühtlasi arhitektide Madis Eegi ja Margit Mutso kodu. Gert Sarve projekteeritud kahepereelamu Herne t. 9. KOKO arhitektide Raivo Kotovi ja Tõnis Kimmeli projekteeritud korterelamu Vabriku t. 33. Ill.: 12 plaani, 14 värv. vaadet

  6. COST IMPACT OF ROD CONSOLIDATION ON THE VIABILITY ASSESSMENT DESIGN

    International Nuclear Information System (INIS)

    D. Lancaster

    1999-01-01

    The cost impact to the Civilian Radioactive Waste Management System of using rod consolidation is evaluated. Previous work has demonstrated that the fuel rods of two assemblies can be packed into a canister that can fit into the same size space as that used to store a single assembly. The remaining fuel assembly hardware can be compacted into the same size canisters with a ratio of 1 hardware canister per each 6 to 12 assemblies. Transportation casks of the same size as currently available can load twice the number of assemblies by placing the compacted assemblies in the slots currently designed for a single assembly. Waste packages similarly could contain twice the number of assemblies; however, thermal constraints would require considering either a low burnup or cooling. The analysis evaluates the impact of rod consolidation on CRWMS costs for consolidation at prior to transportation and for consolidation at the Monitored Geological Repository surface facility. For this study, no design changes were made to either the transport casks or waste packages. Waste package designs used for the Viability Assessment design were employed but derated to make the thermal limits. A logistics analysis of the waste was performed to determine the number of each waste package with each loading. A review of past rod consolidation experience found cost estimates which range from $10/kgU to $32/kgU. $30/kgU was assumed for rod consolidation costs prior to transportation. Transportation cost savings are about $17/kgU and waste package cost savings are about $21/kgU. The net saving to the system is approximately $500 million if the consolidation is performed prior to transportation. If consolidation were performed at the repository surface facilities, it would cost approximately $15/kgU. No transportation savings would be realized. The net savings for consolidation at the repository site would be about $400 million dollars

  7. Large-scale production of UO2 kernels by sol–gel process at INET

    International Nuclear Information System (INIS)

    Hao, Shaochang; Ma, Jingtao; Zhao, Xingyu; Wang, Yang; Zhou, Xiangwen; Deng, Changsheng

    2014-01-01

    In order to supply elements (300,000 elements per year) for the Chinese pebble bed modular high temperature gas cooled reactor (HTR-PM), it is necessary to scale up the production of UO 2 kernels to 3–6 kgU per batch. The sol–gel process for preparation of UO 2 kernels have been improved and optimized at Institute of Nuclear and New Energy Technology (INET), Tsinghua University, PR China, and a whole set of facility was designed and constructed based on the process. This report briefly describes the main steps of the process, the key equipment and the production capacities of every step. Six batches of kernels for scale-up verification and four batches of kernels for fuel elements for in-pile irradiation tests have been successfully produced, respectively. The quality of the produced kernels meets the design requirements. The production capacity of the process reaches 3–6 kgU per batch

  8. Navy Future Fleet Platform Architecture Study

    Science.gov (United States)

    2016-07-01

    Corporation and should not be construed as an official government position, policy, or decision, unless designated by other documentation. ©2016 The...MITRE Corporation . All rights reserved. Sponsor: Department of the Navy Department No.: J63A Contract No.: W56KGU-15-C-0010 Project No.: 0716V150...attack against Sony Pictures in retaliation for the production of a movie [13]. Recent investigations into hacking of the Society of Worldwide

  9. Alloy development for high burnup cladding (PWR)

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, R. [Kraftwerk Union AG, Mulheim (Germany); Jeong, Y.H.; Baek, K.H.; Kim, S.J.; Choi, B.K.; Kim, J.M. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1999-04-01

    An overview on current alloy development for high burnup PWR fuel cladding is given. It is mainly based on literature data. First, the reasons for an increase of the current mean discharge burnup from 35 MWd / kg(U) to 70 MWd / kg(U) are outlined. From the material data, it is shown that a batch average burnup of 60-70 MWd / kg(U), as aimed by many fuel vendors, can not be achieved with stand (=ASTM-) Zry-4 cladding tubes without violating accepted design criteria. Specifically criteria which limit maximum oxide scale thickness and maximum hydrogen content, and to a less degree, maximum creep and growth rate, can not be achieved. The development potential of standard Zry-4 is shown. Even when taking advantage of this potential, it is shown that an 'improved' Zry-4 is reaching its limits when it achieves the target burnup. The behavior of some Zr alloys outside the ASTM range is shown, and the advantages and disadvantages of the 3 alloy groups (ZrSn+transition metals, ZrNb, ZrSnNb+transition metals) which are currently considered to have the development potential for high burnup cladding materials are depicted. Finally, conclusions are drawn. (author). 14 refs., 11 tabs., 82 figs.

  10. March market review

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The spot market price for uranium in unrestricted markets weakened further during March, and at month end, the NUEXCO Exchange Value had fallen $0.15, to $7.45 per pound U3O8. The Restricted American Market Penalty (RAMP) for concentrates increased $0.15, to $2.55 per pound U3O8. Ample UF6 supplies and limited demand led to a $0.50 decrease in the UF6 Value, to $25.00 per kgU as UF6, while the RAMP for UF6 increased $0.75, to $5.25 per kgU. Nine near-term uranium transactions were reported, totalling almost 3.3 million pounds equivalent U3O8. This is the largest monthly spot market volume since October 1992, and is double the volume reported in January and February. The March 31 Conversion Value was $4.25 per kgU as UF6. Beginning with the March 31 Value, NUEXCO now reports its Conversion Value in US dollars per kilogram of uranium (US$/kgU), reflecting current industry practice. The March loan market was inactive with no transactions reported. The Loan Rate remained unchanged at 3.0 percent per annum. Low demand and increased competition among sellers led to a one-dollar decrease in the SWU Value, to $65 per SWU, and the RAMP for SWU declined one dollar, to $9 per SWU

  11. Genes for carbon metabolism and the ToxA virulence factor in Pseudomonas aeruginosa are regulated through molecular interactions of PtxR and PtxS.

    Directory of Open Access Journals (Sweden)

    Abdelali Daddaoua

    Full Text Available Homologs of the transcriptional regulator PtxS are omnipresent in Pseudomonas, whereas PtxR homologues are exclusively found in human pathogenic Pseudomonas species. In all Pseudomonas sp., PtxS with 2-ketogluconate is the regulator of the gluconate degradation pathway and controls expression from its own promoter and also from the P(gad and P(kgu for the catabolic operons. There is evidence that PtxS and PtxR play a central role in the regulation of exotoxin A expression, a relevant primary virulence factor of Pseudomonas aeruginosa. We show using DNaseI-footprint analysis that in P. aeruginosa PtxR binds to the -35 region of the P(toxA promoter in front of the exotoxin A gene, whereas PtxS does not bind to this promoter. Bioinformatic and DNaseI-footprint analysis identified a PtxR binding site in the P(kgu and P(gad promoters that overlaps the -35 region, while the PtxS operator site is located 50 bp downstream from the PtxR site. In vitro, PtxS recognises PtxR with nanomolar affinity, but this interaction does not occur in the presence of 2-ketogluconate, the specific effector of PtxS. DNAaseI footprint assays of P(kgu and P(gad promoters with PtxS and PtxR showed a strong region of hyper-reactivity between both regulator binding sites, indicative of DNA distortion when both proteins are bound; however in the presence of 2-ketogluconate no protection was observed. We conclude that PtxS modulates PtxR activity in response to 2-ketogluconate by complex formation in solution in the case of the P(toxA promoter, or via the formation of a DNA loop as in the regulation of gluconate catabolic genes. Data suggest two different mechanisms of control exerted by the same regulator.

  12. Transportation impact analysis for shipment of irradiated N-reactor fuel and associated materials

    International Nuclear Information System (INIS)

    Daling, P.M.; Harris, M.S.

    1994-12-01

    An analysis of the radiological and nonradiological impacts of highway transportation of N-Reactor irradiated fuel (N-fuel) and associated materials is described in this report. N-fuel is proposed to be transported from its present locations in the 105-KE and 105-KW Basins, and possibly the PUREX Facility, to the 327 Building for characterization and testing. Each of these facilities is located on the Hanford Site, which is near Richland, Washington. The projected annual shipping quantity is 500 kgU/yr for 5 years for a total of 2500 kgU. It was assumed the irradiated fuel would be returned to the K- Basins following characterization, so the total amount of fuel shipped was assumed to be 5000 kgU. The shipping campaign may also include the transport and characterization of liquids, gases, and sludges from the storage basins, including fuel assembly and/or canister parts that may also be present in the basins. The impacts of transporting these other materials are bounded by the impacts of transporting 5000 kgU of N-fuel. This report was prepared to support an environmental assessment of the N-fuel characterization program. The RADTRAN 4 and GENII computer codes were used to evaluate the radiological impacts of the proposed shipping campaign. RADTRAN 4 was used to calculate the routine exposures and accident risks to workers and the general public from the N-fuel shipments. The GENII computer code was used to calculate the consequences of the maximum credible accident. The results indicate that the transportation of N-fuel in support of the characterization program should not cause excess radiological-induced latent cancer fatalities or traffic-related nonradiological accident fatalities. The consequences of the maximum credible accident are projected to be small and result in no excess latent cancer fatalities

  13. An Investigation of the Fine Spatial Structure of Meteor Streams Using the Relational Database ``Meteor''

    Science.gov (United States)

    Karpov, A. V.; Yumagulov, E. Z.

    2003-05-01

    We have restored and ordered the archive of meteor observations carried out with a meteor radar complex ``KGU-M5'' since 1986. A relational database has been formed under the control of the Database Management System (DBMS) Oracle 8. We also improved and tested a statistical method for studying the fine spatial structure of meteor streams with allowance for the specific features of application of the DBMS. Statistical analysis of the results of observations made it possible to obtain information about the substance distribution in the Quadrantid, Geminid, and Perseid meteor streams.

  14. Maintenance Plan for Historic Buildings within the Presidio of San Francisco Historic Landmark District.

    Science.gov (United States)

    1982-12-10

    i_._uy^j^MiIQ^Cf^ip^^l»*y.y.*jr’>\\?.𔄃.w-\\’vy;.\\_?;??*\\i\\<-•:• • •• v.v v fr> * ^ vj ^50d TO MATCH EX. INFLACS CUT SKIP 3.5.3 /A/52er swot ...AWN. Or 2" UNCUT IKEA MUST MOWN Z£LO>VarrfuKGU7TZK. / £C=/" tNFQR&nCCK, tXisrs BEAM ɝFDGH£NDp i/4 ROUND 7KM NEW FASC/A, MAX. &". QSa/L 5

  15. Feasibility study of power reactor fuel elements factory development: I. Economical aspects

    International Nuclear Information System (INIS)

    Marwoto; Ratih-Langenati, R.R.; Susanti, P.

    1996-01-01

    For determining the feasibility study on manufacturing nuclear fuel element from economical aspect point of view, it necessary to fix its capacity which it was found from fuel element reloading requirement for nuclear power plat (PLTN). NEWJEC report which use as a base in this study that is possibly of a complex of NPP as big as 7200 MW in Muria region. If the capacity factor is 80 %, the reload requirement is therefore become from 120 to 142 tons uranium every year. So, its considered to fix the nominal capacity of a fabric for nuclear fuel element manufacturing as much as 200 tons-U per year with economical lifetimes of 20 years. NEWJEC data show, for manufacturing capacity of 200 tons-U per year with, plant have a fixed capital investment of US$ 43.9 million. With working capital as much as 15 % correspond to fixed capital investment (FCI); 10 % of interest rate; US$ 17 million of fixed cost; US$ 106.2/kg-U of variable production cost, its calculated that break even point/BEP is 50 % for price of nuclear fuel is US$ 350/kg-U without uranium cost. On this economic condition, it was found that the return on investment/ROI is 20.2 %; the internal rate of return/IRR is 11.2 % and the benefit cost ration/BCR is 1.22. For all of above, it was assumed that such nuclear fuel element manufacturing service will be operate in the year of 2012. Some of NEWJEC data have been revised, there were the value of FCI; cost of salary; the value in percent of working capital/WC; the cost of non-uranium materials and the price of product service are US$ 68 million; US$ 4.1 million; 30 %; US$ 100/kg-U and US$ 370/kg-U respectively, where the new data appear as higher than old date from NEWJEC, excluding the cost of salary. For all new economical data in the latest, we found that 45 %; 16.73 %; 11.8 % and 1.25 for BEB; IRR and BCR respectively

  16. An analysis on human factor issues in criticality accident at a uranium processing plant

    International Nuclear Information System (INIS)

    Sasou, Kunihide; Goda, Hidenori; Hirotsu, Yuko

    2000-01-01

    This report analyses latent factors of a human behavior directly contributing to the criticality accident. It is pouring some 16 kg-U with an enrichment of 18.8% into the precipitation tank. It is the fact that the direct cause of this accident is the workers' unsafe act. However, the authors find lots of latent factors relating to the production-biased company's policy, the poor climate for safety in the work place, the inadequate safety management and the unsuitable equipment. This accident was caused by many organizational factors. This paper also discusses lessons learned from this accident. (author)

  17. Preliminary assessment of alternative dry storage methods for the storage of commercial spent nuclear fuel

    International Nuclear Information System (INIS)

    1981-11-01

    This report presents the results of an assessment of the (1) state of technology, (2) licensability, (3) implementation schedule, and (4) costs of alternative dry methods for storage of spent fuel at a reactor location when used to supplement reactor pool storage facilities. The methods of storage that were considered included storage in casks, drywells, concrete silos and air-cooled vaults. The impact of disassembly of spent fuel and storage of consolidated fuel rods was also determined. The economic assessments were made based on the current projected storage requirements of Virginia Electric and Power Company's Surry Station for the period 1985 to 2009, which has two operating pressurized water reactors (824 MWe each). It was estimated that the unit cost for storage of spent fuel in casks would amount to $117/kgU and that such costs for storage in drywells would amount to $137/kgU. However, based on the overall assessment it was concluded both storage methods were equal in merit. Modular methods of storage were generally found to be more economic than those requiring all or most of the facilities to be constructed prior to commencement of storage operations

  18. In situ X-ray data collection from highly sensitive crystals of Pseudomonas putida PtxS in complex with DNA

    International Nuclear Information System (INIS)

    Pineda-Molina, E.; Daddaoua, A.; Krell, T.; Ramos, J. L.; García-Ruiz, J. M.; Gavira, J. A.

    2012-01-01

    The crystallization of both native P. putida transcriptional regulator PtxS and its complex with its DNA recognition sequence using the counter-diffusion method are reported. Pseudomonas putida PtxS is a member of the LacI protein family of transcriptional regulators involved in glucose metabolism. All genes involved in this pathway are clustered into two operons, kgu and gad. PtxS controls the expression of the kgu and gad operons as well as its own transcription. The PtxS operator is a perfect palindrome, 5′-TGAAACCGGTTTCA-3′, which is present in all three promoters. Crystallization of native PtxS failed, and PtxS–DNA crystals were finally produced by the counter-diffusion technique. A portion of the capillary used for crystal growth was attached to the end of a SPINE standard cap and directly flash-cooled in liquid nitrogen for diffraction tests. A full data set was collected with a beam size of 10 × 10 µm. The crystal belonged to the trigonal space group P3, with unit-cell parameters a = b = 213.71, c = 71.57 Å. Only unhandled crystals grown in capillaries of 0.1 mm inner diameter diffracted X-rays to 1.92 Å resolution

  19. Guaranteeing high output of a mine

    Energy Technology Data Exchange (ETDEWEB)

    Shetser, M G

    1983-05-01

    Operation of the Im. Kalinina coal mine in the Central Donbass is evluated. Seventeen coal seams, on the average 0.87 m thick, are prone to methane and coal dust explosions and to rock bursts. Some of the seams are also prone to spontaneous combustion. Rock layers in the roofs are prone to rock falls. Mining depth ranges from 740 to 850 m. Another working level is being constructed at a depth of 960 m. The steep coal seams are mined by means of the ANShch shield systems and the KGU system (with the 'Poisk' cutter loader). Strata control methods used in the mine are evaluated. Design of timber cribbings used for strata control in inclined workings is shown in a scheme. Construction of coal chutes and strata control in coal chutes are also described. Operation of KGU-1 powered supports which have been used in the mine for 10 years is evaluated. Improved strata control permitted daily coal output from a working face to be increased from 135 t in 1979 to 169 t in 1982. Yearly coal output increased from 605,000 t to 760,000 t. Labor productivity increased from 21.1 t/month to 25.9 t/month per miner. (In Russian)

  20. Welcome Address

    Science.gov (United States)

    Kiku, H.

    2014-12-01

    Ladies and Gentlemen, It is an honor for me to present my welcome address in the 3rd International Workshop on "State of the Art in Nuclear Cluster Physics"(SOTANCP3), as the president of Kanto Gakuin University. Particularly to those from abroad more than 17 countries, I am very grateful for your participation after long long trips from your home to Yokohama. On the behalf of the Kanto Gakuin University, we certainly welcome your visit to our university and stay in Yokohama. First I would like to introduce Kanto Gakuin University briefly. Kanto Gakuin University, which is called KGU, traces its roots back to the Yokohama Baptist Seminary founded in 1884 in Yamate, Yokohama. The seminary's founder was Albert Arnold Bennett, alumnus of Brown University, who came to Japan from the United States to establish a theological seminary for cultivating and training Japanese missionaries. Now KGU is a major member of the Kanto Gakuin School Corporation, which is composed of two kindergartens, two primary schools, two junior high schools, two senior high schools as well as KGU. In this university, we have eight faculties with graduate school including Humanities, Economics, Law, Sciences and Engineering, Architecture and Environmental Design, Human and Environmental Studies, Nursing, and Law School. Over eleven thousands students are currently learning in our university. By the way, my major is the geotechnical engineering, and I belong to the faculty of Sciences and Engineering in my university. Prof. T. Yamada, here, is my colleague in the same faculty. I know that the nuclear physics is one of the most active academic fields in the world. In fact, about half of the participants, namely, more than 50 scientists, come from abroad in this conference. Moreover, I know that the nuclear physics is related to not only the other fundamental physics such as the elementary particle physics and astrophysics but also chemistry, medical sciences, medical cares, and radiation metrology

  1. PWR burnable absorber evaluation

    International Nuclear Information System (INIS)

    Cacciapouti, R.J.; Weader, R.J.; Malone, J.P.

    1995-01-01

    The purpose of the study was to evaluate the relative neurotic efficiency and fuel cycle cost benefits of PWR burnable absorbers. Establishment of reference low-leakage equilibrium in-core fuel management plans for 12-, 18- and 24-month cycles. Review of the fuel management impact of the integral fuel burnable absorber (IFBA), erbium and gadolinium. Calculation of the U 3 O 8 , UF 6 , SWU, fuel fabrication, and burnable absorber requirements for the defined fuel management plans. Estimation of fuel cycle costs of each fuel management plan at spot market and long-term market fuel prices. Estimation of the comparative savings of the different burnable absorbers in dollar equivalent per kgU of fabricated fuel. (author)

  2. Market values summary/February market review/current market data

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    This article is the February 1995 uranium market summary. In the natural uranium and concentrates market, there were 10 deals, and the restricted value moved upward to $10.40. The unrestricted value remained fixed at $7.25. In the UF6 market, there were two deals in the restricted market, and the restricted value rose to $32.75 per kgU as UF6. The unrestricted value remained at $25.00. The restricted transaction value rose to $9.75, and the unrestricted value rose to $7.15. In the enrichment services market, there were three deals. The restricted SWU value rose to $90 per SWU, and the unrestricted value rose to $75 per SWU. Active uranium supply and active uranium demand dropped this reporting period

  3. Evaluation of the Cerro Solo nuclear ore, province of Chubut. On the economic parameters of the deposit. Pt. 3

    International Nuclear Information System (INIS)

    Navarra, P.R.; Sardin, P.G.; Urquiza, L.; Bernal, G.J.; Guzman Lobos, D.

    1993-01-01

    Preliminary results of the resources estimation carried out in the Cerro Solo uranium ore deposit, located in the Chubut Province, 1900 km SW from Buenos Aires and 380 Km W from Trelew, presented in tonnes of uranium recoverable at costs up to U$S 80/kgU, are as follows: a) Reasonable assured resources (indicated): 800 tU; b) Estimates Additional Resources (inferred): 2200 tU. Economic evaluation at the order-of-magnitude level, performed using the grade-tonnage model of the deposit, resulted a useful tool in the different stages of the project to identify the influence of technical parameters on the potential profitability. Research about feasibility of in-situ leaching method of exploitation for this deposit introduces an interesting alternative for future uranium production in the country. (Author)

  4. Effect of gamma irradiation on insecticides of grains and storage raw-materia

    International Nuclear Information System (INIS)

    Manco, E.A.C.

    1987-12-01

    To study the effect of gamma irradiation on deltametrina, malathion and fenitrothion, the saturated filter paper technique was used. The filter paper, saturated with the products, was submitted to increasing doses of gamma radiation - 10, 20 and 40 kGu at a 12.76 kGy rate p/h. Adults of Sitophilus zeamais Mots. reared at 25 0 +- 1 0 C and relative humidity of 70 +- 5% were used. The dead rate used and life expectancy was calculated using the best regression as indicator of the degradation factor of the insecticide. It was noted that gamma radiation degraded deltametrina and fenitrothion, the latter more markedly at a 40 kGy dose. Gamma radiation had no effect on malathion and the insects submitted to it showed a life expectancy smaller than the controls. (author) [pt

  5. A study on decontamination and decommissioning of experimental DUPIC equipment at PIEF 9405 hot cell

    International Nuclear Information System (INIS)

    Lee, H. H.; Park, J. J.; Shin, J. M.; Yang, M. S.; Lee, H. S.; Lee, E. P.

    2000-09-01

    The characterization experiment for powder and sintered fuel had been performed using about 1 kg-U spent PWR fuel at No. 9405 hot-cell in PIEF(Post Irradiated Experiment Facility) since early in 1999. Currently, The experiments in PIEF have been completed. It is supposed to dismantle and decontaminate the installed equipment by the end of year 2000. Since all of DUPIC equipment in hot-cell are contaminated by high radioactive material, the decontamination and dismantlement must br performed remotely by M/S manipulator. During the radioactive waste packing and transportation, the reduction method of radiation exposure has to be considered. Firstly, This report describes the basic plan for dismantlement/decontamination of the characterization equipment(power and sintered fuel). And methods of measurement/packing/ transportation, method of dismantlement/decontamination of the experimental apparatus and the reduction method of radiation dose exposure, etc. are explained in order

  6. Market values summary/October market review/current market data

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    This article is the October uranium market summary. During this period, volume increased to 2.2 Mlb U3O8 on the spot concentrates market. The unrestricted and restricted exchange values remained steady at $7.00 and $9.05 per pound U3O8 respectively. There were two UF6 deals during this period, and with supply more than adequate to meet the demand, the restricted UF6 price remained unchanged at $29.00 per kgU as UF6. The unrestricted value increased slightly to $24.50. The conversion value was unchanged, and the enrichment services market/prices weakened. Both active supply and demand decreased during this period

  7. Simple estimate of fission rate during JCO criticality accident

    Energy Technology Data Exchange (ETDEWEB)

    Oyamatsu, Kazuhiro [Faculty of Studies on Contemporary Society, Aichi Shukutoku Univ., Nagakute, Aichi (Japan)

    2000-03-01

    The fission rate during JCO criticality accident is estimated from fission-product (FP) radioactivities in a uranium solution sample taken from the preparation basin 20 days after the accident. The FP radioactivity data are taken from a report by JAERI released in the Accident Investigation Committee. The total fission number is found quite dependent on the FP radioactivities and estimated to be about 4x10{sup 16} per liter, or 2x10{sup 18} per 16 kgU (assuming uranium concentration 278.9 g/liter). On the contrary, the time dependence of the fission rate is rather insensitive to the FP radioactivities. Hence, it is difficult to determine the fission number in the initial burst from the radioactivity data. (author)

  8. Simple estimate of fission rate during JCO criticality accident

    International Nuclear Information System (INIS)

    Oyamatsu, Kazuhiro

    2000-01-01

    The fission rate during JCO criticality accident is estimated from fission-product (FP) radioactivities in a uranium solution sample taken from the preparation basin 20 days after the accident. The FP radioactivity data are taken from a report by JAERI released in the Accident Investigation Committee. The total fission number is found quite dependent on the FP radioactivities and estimated to be about 4x10 16 per liter, or 2x10 18 per 16 kgU (assuming uranium concentration 278.9 g/liter). On the contrary, the time dependence of the fission rate is rather insensitive to the FP radioactivities. Hence, it is difficult to determine the fission number in the initial burst from the radioactivity data. (author)

  9. The results of decontamination and decommissioning of experimental DUPIC equipment at PIEF 9405 hot cell

    Energy Technology Data Exchange (ETDEWEB)

    Lee, H. H.; Park, J. J.; Shin, J. M.; Cho, K. H.; Yang, M. S.; Lee, E. P. [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-02-01

    The characterization experiment for powder and sintered fuel had been performed using about 1 kg-U spent PWR fuel at No. 9405 hot-cell in PIEF(Post Irradiated Experiment Facility) since early in 1999. Currently, the experiments in PIEF have been completed. Since all DUPIC equipment in hot-cell are contaminated by high radioactive material, the decontamination and dismantlement must be performed remotely by M/S manipulator. During the radioactive waste packing and transportation, the reduction method of radiation exposure has to be considered. This report describes the basic plan for dismantlement/decontamination of the characterization equipment (power and sintered fuel). And methods of measurement/packing/transportation, method of dismantlement/decontamination of the experimental apparatus and the reduction method of radiation dose exposure, etc. are explained in order. 7 refs., 42 figs., 10 tabs. (Author)

  10. Comparison of the Reactor Core Characteristics of the AHR and the OPAL

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Chul Gyo; Lee, Byung Chul; Park, C.; Chae, Hee Taek

    2008-09-15

    The AHR (Advanced HANARO research Reactor) was designed using the experiences from the design, operation and utilization of HANARO. Its neutronic performance was compared to that of the OPAL with a 20 MW power which started its operation recently in Australia. As the OPAL does not have any in-core irradiation hole, a modified core model of the AHR, in which an in-core irradiation hole was changed into a fuel channel, was used for the comparison. For a clean, unperturbed core condition with all fresh fuels in the core and no irradiation holes in the reflector region, the maximum thermal neutron flux (E{sub n}<0.625 eV) in the AHR reaches 4.41x10{sup 14} n/cm{sup 2} s and that in the OPAL reaches 3.96x10{sup 14} n/cm{sup 2}s in the reflector region. The maximum flux in the AHR is 10.3% higher than that in the OPAL. The thermal flux region above 4.0x10{sup 14} n/cm{sup 2}s is widely distributed in the reflector of the AHR, but is not observed at all in the reflector of the OPAL. The uranium loading of the AHR core is 45.7 kgU, which is 16.3% higher than the 39.3 kgU of OPAL. For a clean core state, the excess reactivity of the AHR is higher than that of the OPAL. The assembly-average discharge burnup in the OPAL is estimated to be 49.1%U-235 whereas that in the AHR is 62.4%U-235. The difference for the discharge burnup is significant. For the conditions with the same cycle length of 30 days, the number of fuel assemblies consumed in the AHR is only 3/4 that of the OPAL.

  11. Comparison of the Reactor Core Characteristics of the AHR and the OPAL

    International Nuclear Information System (INIS)

    Seo, Chul Gyo; Lee, Byung Chul; Park, C.; Chae, Hee Taek

    2008-09-01

    The AHR (Advanced HANARO research Reactor) was designed using the experiences from the design, operation and utilization of HANARO. Its neutronic performance was compared to that of the OPAL with a 20 MW power which started its operation recently in Australia. As the OPAL does not have any in-core irradiation hole, a modified core model of the AHR, in which an in-core irradiation hole was changed into a fuel channel, was used for the comparison. For a clean, unperturbed core condition with all fresh fuels in the core and no irradiation holes in the reflector region, the maximum thermal neutron flux (E n 14 n/cm 2 s and that in the OPAL reaches 3.96x10 14 n/cm 2 s in the reflector region. The maximum flux in the AHR is 10.3% higher than that in the OPAL. The thermal flux region above 4.0x10 14 n/cm 2 s is widely distributed in the reflector of the AHR, but is not observed at all in the reflector of the OPAL. The uranium loading of the AHR core is 45.7 kgU, which is 16.3% higher than the 39.3 kgU of OPAL. For a clean core state, the excess reactivity of the AHR is higher than that of the OPAL. The assembly-average discharge burnup in the OPAL is estimated to be 49.1%U-235 whereas that in the AHR is 62.4%U-235. The difference for the discharge burnup is significant. For the conditions with the same cycle length of 30 days, the number of fuel assemblies consumed in the AHR is only 3/4 that of the OPAL

  12. Analysis of uranium supply to 2050

    International Nuclear Information System (INIS)

    Underhill, D.H.

    2002-01-01

    The 1999 uranium mine production was about 55% of the 61 500 tonnes uranium (t U) used by the nuclear industry, with the balance met by secondary supply. Based on a recent WEC-IIASA study which defines a wide range of possible future levels of nuclear electricity generation, it is estimated that by 2050 annual uranium requirements could increase to 177 000 and 283 000 t U respectively, in the mid and high cases, or fall to 52 000 t U in the low case. Cumulative requirements to 2050 for the low, mid and high cases are, respectively 3.39, 5.35 and 7.58 million t U. A new IAEA analysis describes how known uranium resources (RAR and EAR-1) plus undiscovered resources (EAR-II and SR), supplemented by secondary supplies, could be utilized to supply reactors to 2050. Secondary supplies include: existing inventories, blended down warhead material (LEU blended from HEU), MOX, Repu, and re-enrichment of tails. The methodology of this analysis estimates the amounts and annual deliveries of the secondary supply, plus non-market supply. The balance of demand is met from Market Based Production (MBP) or: 'Uranium produced at or below market price to satisfy requirements not met by other supply sources'. The analysis then evaluates the production role for 125 uranium deposits, which supply MBP considering individual deposit resources, production cost and capability, and timing. Production costs are classified from low ( $130/kgU). Annual supply and demand balancing is used to allocate the resources on an individual deposit basis, assuming use of the next lowest available cost production. Secondary supplies will continue to supplement mine production to about 2025, but their relative importance will decrease over the period. An analysis of the benefit of lowering the enrichment tails assay from 0.30% 235 U to 0.15% 235 U, when economically justified is also discussed. The report also discusses projected production cost trends to 2025 under the mid and high cases. The final

  13. Irradiated fuel by-product separation research in Canada

    International Nuclear Information System (INIS)

    Burston, M.

    1984-01-01

    Although no decision has been made to reprocess irradiated CANDU fuel, by-product separation research has recently been initiated in Canada because of its potential importance to Canadian research programs in advanced fuel cycles (especially U/Pu cycle development in the near term) and nuclear waste management. In addition, separated by-products could have a significant commercial potential. Demonstrated applications include: heat sources, gamma radiation sources, light sources, new materials for productions of other useful isotopes, etc. For illustrative purposes the calculated market value of by-products currently stored in irradiated CANDU fuel is approximately $210/kgU. Ontario Hydro has initiated a program to study the application of new separation technolgies, such as laser-based techniques and the plasma ion cyclotron resonance separation technique, to either augment and/or supplant the chemical extraction methods. The main goal is to develop new, more economical extraction methods in order to increase the magnitude of the advantages resulting from this approach to reprocessing. (author)

  14. Nuclear power generation and nuclear fuel

    International Nuclear Information System (INIS)

    Okajima, Yasujiro

    1985-01-01

    As of June 30, 1984, in 25 countries, 311 nuclear power plants of about 209 million kW were in operation. In Japan, 27 plants of about 19 million kW were in operation, and Japan ranks fourth in the world. The present state of nuclear power generation and nuclear fuel cycle is explained. The total uranium resources in the free world which can be mined at the cost below $130/kgU are about 3.67 million t, and it was estimated that the demand up to about 2015 would be able to be met. But it is considered also that the demand and supply of uranium in the world may become tight at the end of 1980s. The supply of uranium to Japan is ensured up to about 1995, and the yearly supply of 3000 st U 3 O 8 is expected in the latter half of 1990s. The refining, conversion and enrichment of uranium are described. In Japan, a pilot enrichment plant consisting of 7000 centrifuges has the capacity of about 50 t SWU/year. UO 2 fuel assemblies for LWRs, the working of Zircaloy, the fabrication of fuel assemblies, the quality assurance of nuclear fuel, the behavior of UO 2 fuel, the grading-up of LWRs and nuclear fuel, and the nuclear fuel business in Japan are reported. The reprocessing of spent fuel and plutonium fuel are described. (Kako, I.)

  15. The relationship of JNC and JCO in the uranium processing plant criticality accident

    International Nuclear Information System (INIS)

    Kanamori, Masashi; Yanagibashi, Katsumi; Okamoto, Naritoshi

    2002-12-01

    On September 30th 1999, the criticality accident occurred at JCO's uranium conversion building in Tokai. The accident occurred during reconversion from U 3 O 8 to uranium nitrate solution (UNH) with uranium enriched 18.8% and about 60 kgU. JCO contacted with JNC to supply UNH that is fuel material for the experimental fast breeder reactor 'JOYO'. JNC has contracted with JCO that had started nuclear fuel material processing business following a definite policy of Japanese government and developed SUMITOMO ADU PROCESS'. JNC made the first contract with JCO in 1985 and has made a contact every year. There had never been a problem in their products. JNC inspected products based on contract. JNC discharge our duty as customer inspecting products based on contract. As for safety control, JCO had taken licensing safety review and had been permitted to be 'a processing facility'. Therefore JNC understood that JCO produced following this license. 'The Uranium Processing Plant Criticality Accident Investigation' showed that JCO had been taking a different method from the permit and violating the license. However JNC had never been explained about that and JCO's operation procedures had never described about that. Therefore the Criticality Accident couldn't be avoided. This report describes the relationship of JNC and JCO in the uranium reconversion contract for JOYO, atomic development policy of Japanese government, process to the order and the contents of contract. (author)

  16. Radioactive waste management of experimental DUPIC fuel fabrication process

    International Nuclear Information System (INIS)

    Lee, H. H.; Park, J. J.; Shin, J. M.; Yang, M. S.; Hong, K. P.

    2001-01-01

    The concept of DUPIC(Direct Use of Spent PWR Fuel in CANDU Reactors) is a dry processing technology to manufacture CANDU compatible DUPIC fuel from spent PWR fuel material. Real spent PWR fuel was used in IMEF M6 hot cell to carry out DUPIC experiment. Afterwards, about 200 kg-U of spent PWR fuel is supposed to be used till 2006. This study has been conducted in some hot cells of PIEF and M6 cell of IMEF. There are various forms of nuclear material such as rod cut, powder, green pellet, sintered pellet, fabrication debris, fuel rod, fuel bundle, sample, and process waste produced from various manufacturing experiment of DUPIC fuel. After completing test, the above nuclear wastes and test equipment etc. will be classified as radioactive waste, transferred to storage facility and managed rigorously according to domestic and international laws until the final management policy is determined. It is desirable to review management options in advance for radioactive waste generated from manufacturing experiment of DUPIC nuclear fuel as well as residual nuclear material and dismantled equipment. This paper includes basic plan for DUPIC radwaste, arising source and estimated amount of radioactive waste, waste classification and packing, transport cask, transport procedures

  17. May market review

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    Seven uranium transactions totalling nearly three million pounds equivalent U3O8 were reported during May, but only two, totalling less than 200 thousand pounds equivalent U3O8, involved concentrates. As no discretionary buying occurred during the month, and as near-term supply and demand were in relative balance, prices were steady, while both buyers and sellers appeared to be awaiting some new market development to signal the direction of future spot-market prices. The May 31, 1993, Exchange Value and the Restricted American market Penalty (RAMP) for concentrates were both unchanged at $7.10, and $2.95 per pound U3O8, respectively. NUEXCO's judgement was that transactions for significant quantities of uranium concentrates that were both deliverable in and intended for consumption in the USA could have been concluded on May 31 at $10.05 per pound U3O8. Two near-term concentrate transactions were reported in which one US utility purchased less than 200 thousand pounds equivalent U3O8 from two separate sellers. These sales occurred at price levels at or near the May 31 Exchange Value plus RAMP. No long-term uranium transactions were reported during May. Consequently, the UF6 Value decreased $0.20 to $24.30 per kgU as UF6, reflecting some weakening of the UF6 market outside the USA

  18. Economic Analysis of Different Nuclear Fuel Cycle Options

    International Nuclear Information System (INIS)

    Ko, W.; Gao, F.

    2012-01-01

    An economic analysis has been performed to compare four nuclear fuel cycle options: a once-through cycle (OT), DUPIC recycling, thermal recycling using MOX fuel in a pressurized water reactor (PWR-MOX), and sodium fast reactor recycling employing pyro processing (Pyro-SFR). This comparison was made to suggest an economic competitive fuel cycle for the Republic of Korea. The fuel cycle cost (FCC) has been calculated based on the equilibrium material flows integrated with the unit cost of the fuel cycle components. The levelized fuel cycle costs (LFCC) have been derived in terms of mills/kWh for a fair comparison among the FCCs, and the results are as follows: OT 7.35 mills/kWh, DUPIC 9.06 mills/kWh, PUREX-MOX 8.94 mills/kWh, and Pyro-SFR 7.70 mills/kWh. Due to unavoidable uncertainties, a cost range has been applied to each unit cost, and an uncertainty study has been performed accordingly. A sensitivity analysis has also been carried out to obtain the break-even uranium price (215$/kgU) for the Pyro-SFR against the OT, which demonstrates that the deployment of the Pyro-SFR may be economical in the foreseeable future. The influence of pyro techniques on the LFCC has also been studied to determine at which level the potential advantages of Pyro-SFR can be realized.

  19. Performance of the Westinghouse WWER-1000 fuel design

    International Nuclear Information System (INIS)

    Höglund, J.; Jansson, A.; Latorre, R.; Davis, D.

    2015-01-01

    In 2005, six (6) Westinghouse WWER-1000 Lead Test Assemblies (LTAs) were loaded in South Ukraine Unit 3 (SU3). The LTAs completed the planned four cycles of operation and reached an average assembly burnup in excess of 43 MWd/ kgU. Post Irradiation Examination (PIE) inspections were performed after completion of each cycle and it was concluded that the 6 Westinghouse LTAs performed as expected during their operational regimes. In 2010, a full region of 42 assemblies of an enhanced WWER-1000 fuel design for Ukrainian reactors, designated WFA, was loaded in SU3. The WFA includes features that further mitigate assembly bow while at the same time improving the fuel cycle economy. In 2015, 26 WFAs completed their planned four cycles of operation reaching an average assembly burnup in excess of 42 MWd/ kgU. Currently 36 WFAs continue operating their fourth cycle in SU3. In addition, South Ukraine Unit 2 (SU2) has been loaded with WFAs and 27 assemblies have completed two cycles of operation reaching an average assembly burnup above 24 MWd/kgU. PIE for the WFAs has been completed after each cycle of operation. All assemblies have been examined for visible damage or non-standard position of fuel assembly components during unloading and reloading. All WFAs have also been subject to the standard leak testing process, with all fuel rods found to be hermetically sealed and non-leaking. Each outage, six WFAs have been subject to a more extensive inspection program. In 2012, 2013, and 2015, the Westinghouse Fuel Inspection and Repair Equipment (FIRE) workstation were used for the SU3 inspections. Excellent irradiation fuel performance has been observed and measured on all WFAs. The fuel assembly growth, rod cluster control assembly (RCCA) drag forces, oxide thickness, total fuel rod-to-nozzle gap channel closure, and fuel assembly bow data were within the bounds of the Westinghouse experience database. Results and concluding remarks from the PIEs are provided in this paper. In

  20. Australia's Uranium and thorium resources and their global significance

    International Nuclear Information System (INIS)

    Lambert, I.B.; McKay, A.; Miezitis, Y.

    2006-01-01

    Full text: Full text: Australia's world-leading uranium endowment appears to result from the emplacement of uranium enriched felsic igneous rocks in three major periods during the geological evolution of the continent. Australia has over 27% of the world's total reasonably assured uranium resources (RAR) recoverable at < US$80/kgU (which approximates recent uranium spot prices). Olympic Dam is the largest known uranium deposit, containing approximately 19% of global RAR (and over 40% of global inferred resources) recoverable at < US$80/kg U; the uranium is present at low concentrations and the viability of its recovery is underpinned by co-production of copper and gold. Most of Australia's other identified resources are within Ranger, Jabiluka, Koongarra, Kintyre and Yeelirrie, the last four of which are not currently accessible for mining. In 2004, Australia's three operating uranium mines - Ranger, Olympic Dam, and Beverley -produced 22% of global production. Canada was the only country to produce more uranium (29%) and Kazakhstan (9%) ranked third. Considerably increased uranium production has been recently foreshadowed from Australia (through developing a large open pit at Olympic Dam), Canada (mainly through opening of the Cigar Lake mine), and Kazakhstan (developing several new in situ leach mines). These increases should go a long way towards satisfying demand from about 2010. Olympic Dam has sufficient resources to sustain such increased production over many decades. Thorium is expected to be used in some future generations of nuclear reactors. Australia also has major (but incompletely quantified) resources of this commodity, mainly in heavy mineral sands deposits and associated with alkaline igneous rocks. It is inevitable that the international community will be looking increasingly to Australia to sustain its vital role in providing fuels for future nuclear power generation, given its world-leading identified resources, considerable potential for new

  1. A health recreation program for u-healthcare clients: effects on mental health.

    Science.gov (United States)

    Lee, Jisan; Kim, Jeongeun; Jeong, Suyong; Choi, Hanna; Jin, Meiling; Kim, Sukwha

    2014-10-01

    In this study, a health recreation program was implemented with elderly patients (60 years of age or older) who were receiving ubiquitous healthcare (u-healthcare) services. Furthermore, we examined the effects of health recreation on perceived stress, anxiety, and depression, by comparing survey results before and after the recreation program was conducted. Thus, the aim of this study was to develop an offline service with the ability to promote the impact of the u-healthcare service on mental healthcare. A health recreation program, consisting of a variety of weekly games, songs, and minilectures about mental health over a 10-week period, was offered at a senior citizens center in K-Gu, Seoul, Korea. This program targeted 18 elderly people currently receiving u-healthcare services. Data on the impact of the program on the mental health of the elderly were collected through surveys administered before and after the recreation program, and the results were compared with those of a control group. The control group consisted of 18 elderly people who were receiving u-healthcare services from the same district. The perceived stress and anxiety of the experimental group decreased significantly compared with those of the control group. However, the program did not result in a significant reduction in depression. This offline health recreation program offered to elderly u-healthcare service clients contributed to the promotion of their mental health. Further studies will be required to better incorporate the offline mental healthcare program into their daily lives within the u-healthcare service.

  2. Application of probability generating function to the essentials of nondestructive nuclear materials assay system using neutron correlation

    International Nuclear Information System (INIS)

    Hosoma, Takashi

    2017-01-01

    In the previous research (JAEA-Research 2015-009), essentials of neutron multiplicity counting mathematics were reconsidered where experiences obtained at the Plutonium Conversion Development Facility were taken into, and formulae of multiplicity distribution were algebraically derived up to septuplet using a probability generating function to make a strategic move in the future. Its principle was reported by K. Böhnel in 1985, but such a high-order expansion was the first case due to its increasing complexity. In this research, characteristics of the high-order correlation were investigated. It was found that higher-order correlation increases rapidly in response to the increase of leakage multiplication, crosses and leaves lower-order correlations behind, when leakage multiplication is > 1.3 that depends on detector efficiency and counter setting. In addition, fission rates and doubles count rates by fast neutron and by thermal neutron in their coexisting system were algebraically derived using a probability generating function again. Its principle was reported by I. Pázsit and L. Pál in 2012, but such a physical interpretation, i.e. associating their stochastic variables with fission rate, doubles count rate and leakage multiplication, is the first case. From Rossi-alpha combined distribution and measured ratio of each area obtained by Differential Die-Away Self-Interrogation (DDSI) and conventional assay data, it is possible to estimate: the number of induced fissions per unit time by fast neutron and by thermal neutron; the number of induced fissions (< 1) by one source neutron; and individual doubles count rates. During the research, a hypothesis introduced in their report was proved to be true. Provisional calculations were done for UO_2 of 1∼10 kgU containing ∼ 0.009 wt% "2"4"4Cm. (author)

  3. Global Uranium And Thorium Resources: Are They Adequate To Satisfy Demand Over The Next Half Century?

    Science.gov (United States)

    Lambert, I. B.

    2012-04-01

    This presentation will consider the adequacy of global uranium and thorium resources to meet realistic nuclear power demand scenarios over the next half century. It is presented on behalf of, and based on evaluations by, the Uranium Group - a joint initiative of the OECD Nuclear Energy Agency and the International Atomic Energy Agency, of which the author is a Vice Chair. The Uranium Group produces a biennial report on Uranium Resources, Production and Demand based on information from some 40 countries involved in the nuclear fuel cycle, which also briefly reviews thorium resources. Uranium: In 2008, world production of uranium amounted to almost 44,000 tonnes (tU). This supplied approximately three-quarters of world reactor requirements (approx. 59,000 tU), the remainder being met by previously mined uranium (so-called secondary sources). Information on availability of secondary sources - which include uranium from excess inventories, dismantling nuclear warheads, tails and spent fuel reprocessing - is incomplete, but such sources are expected to decrease in market importance after 2013. In 2008, the total world Reasonably Assured plus Inferred Resources of uranium (recoverable at less than 130/kgU) amounted to 5.4 million tonnes. In addition, it is clear that there are vast amounts of uranium recoverable at higher costs in known deposits, plus many as yet undiscovered deposits. The Uranium Group has concluded that the uranium resource base is more than adequate to meet projected high-case requirements for nuclear power for at least half a century. This conclusion does not assume increasing replacement of uranium by fuels from reprocessing current reactor wastes, or by thorium, nor greater reactor efficiencies, which are likely to ameliorate future uranium demand. However, progressively increasing quantities of uranium will need to be mined, against a backdrop of the relatively small number of producing facilities around the world, geopolitical uncertainties and

  4. Synthesis, chemical and biological properties of the new mono- and bis-derivatives of imidazoles

    Directory of Open Access Journals (Sweden)

    E. V. Welchinska

    2014-12-01

    Institute of Pharmacology and Toxicology of National Academy of Medical Sciences of Ukraine. The lectin’s preparations were obtained by treatment of culture Liquid of saprophytic strain Bacillus from Ukrainian Collection of Microorganisms of Institute of Microbiology and Virology (IMV: B. polymyxa 102 KGU; in future: lectine 102 was clarified by treatment with ammonium sulfate (70% concentration of a saturated solution. Results. For the first time the interaction of a series of imidazole substituted with halothane compounds have been investigated, the conditions of the reaction have been defined, the methods have been developed and the composition of the reaction products has been studied. The studies revealed that the initial heterocycle, namely imidazole reacts with the intermediate product of halothane conversion in an alkaline medium, under conditions of phase transfer catalysis DB-18-crown-6 in a solvent system (dimethyl formamide - benzene - diethyl ether or in another variant: in DMSO with the presence of anhydrous potassium carbonate with the formation of mono-and bis-derivatives of imidazole. This reaction made possible a new strategy of synthesis of selectively poly-functionalized molecules, the chemical structure of which is available for incorporation of new pharmacophore fragments into molecule. It has been discovered that mono-, bis-derivatives of imidazole, molecular complex of bis-derivative of imidazole and antitumour bacterial lectin are low toxic preparations (LD50: from 278 mg/kg to 102 mg/kg. Conclusion. New mono- and bis-adducts of imidazole, molecular complex of Bacillus polymyxa 102 KGU and imidazole bis-derivative have been prepared and its toxicity has been tested. New convenient methods for the preparation of heterocyclic mono- and bis-adducts of imidazole with 1,1,1-trifluoro-2-bromo-2-chloroethane (halothane have been described. The reactions were catalyzed by DB-18-crown-6-complex (at the alkali medium. Investigation of the critical toxicity

  5. Opening Address

    Science.gov (United States)

    Yamada, T.

    2014-12-01

    Ladies and Gentlemen, it is my great honor and pleasure to present an opening address of the 3rd International Workshop on "State of the Art in Nuclear Cluster Physics"(SOTANCP3). On the behalf of the organizing committee, I certainly welcome all your visits to KGU Kannai Media Center belonging to Kanto Gakuin University, and stay in Yokohama. In particular, to whom come from abroad more than 17 countries, I would appreciate your participations after long long trips from your homeland to Yokohama. The first international workshop on "State of the Art in Nuclear Cluster Physics", called SOTANCP, was held in Strasbourg, France, in 2008, and the second one was held in Brussels, Belgium, in 2010. Then the third workshop is now held in Yokohama. In this period, we had the traditional 10th cluster conference in Debrecen, Hungary, in 2012. Thus we have the traditional cluster conference and SOTANCP, one after another, every two years. This obviously shows our field of nuclear cluster physics is very active and flourishing. It is for the first time in about 10 years to hold the international workshop on nuclear cluster physics in Japan, because the last cluster conference held in Japan was in Nara in 2003, about 10 years ago. The president in Nara conference was Prof. K. Ikeda, and the chairpersons were Prof. H. Horiuchi and Prof. I. Tanihata. I think, quite a lot of persons in this room had participated at the Nara conference. Since then, about ten years passed. So, this workshop has profound significance for our Japanese colleagues. The subjects of this workshop are to discuss "the state of the art in nuclear cluster physics" and also discuss the prospect of this field. In a couple of years, we saw significant progresses of this field both in theory and in experiment, which have brought better and new understandings on the clustering aspects in stable and unstable nuclei. I think, the concept of clustering has been more important than ever. This is true also in the

  6. Latest data shows long-term security of uranium supply

    International Nuclear Information System (INIS)

    2010-01-01

    Full text: According to Uranium 2009: Resources, Production and Demand just published by the OECD Nuclear En ergy Agency (NEA) and the International Atomic Energy Agency (IAEA), uranium resources, production and demand are all on the rise. Exploration efforts have increased recently in line with the expected expansion of nuclear energy in the coming years. Total identified resources have grown but so too have costs of production. Worldwide exploration and mine development expenditures have more than doubled since the publication of the previous edition, Uranium 2007: Resources, Production and Demand. These expenditures have increased despite declining uranium market prices since mid- 2007. The uranium resources presented in this edition, reflecting the situation as of 1 January 2009, show that total identified resources amounted to 6 306 300 tU, an increase of about 15% compared to 2007, including those reported in the high-cost category (< USD 260/kgU or < USD 100/lbU O), reintroduced for the first time since the 1980s. This high-cost 3 8 category was used in the 2009 edition in response to the generally increased market prices for uranium in recent years, despite the decline since mid-2007, expectations of increasing demand as new nuclear power plants are being planned and built, and increased mining costs. Although total identified resources have increased overall, there has been a significant reduction in lower-cost resources owing to increased mining costs. At 2008 rates of consumption, total identified resources are sufficient for over 100 years of supply. The recognition by an increasing number of governments that nuclear power can produce competitively priced, baseload electricity that is essentially free of greenhouse gas emissions, coupled with the role that nuclear can play in enhancing security of energy supply, increases the prospects for growth in nuclear generating capacity, although the magnitude of that growth remains to be determined. According to