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Sample records for heljo jnes kersti

  1. International contributions of JNES on seismic safety areas

    International Nuclear Information System (INIS)

    Ebisawa, Katsumi; Uchiyama, Yuichi; Yamada, Hiroyuki

    2010-01-01

    JNES actively promotes the international cooperation in seismic safety areas, aiming to play a role as the important international hub for it. To meet this purpose, JNES is now mainly focusing on the increased support of the international organizations including IAEA and the technological improvement in the seismic related assessment of Asian countries. This paper summarizes these efforts made by JNES. (author)

  2. Safety research activities on radioactive waste management in JNES

    International Nuclear Information System (INIS)

    Otsuka, Ichiro; Aoki, Hiroomi; Suko, Takeshi; Onishi, Yuko; Masuda, Yusuke; Kato, Masami

    2010-01-01

    Research activities in safety regulation of radioactive waste management are presented. Major activities are as follows. As for the geological disposal, major research areas are, developing 'safety indicators' to judge the adequacy of site investigation results presented by an implementer (NUMO), compiling basic requirements of safety design and safety assessment needed to make a safety review of the license application and developing an independent safety assessment methodology. In proceeding research, JNES, Japan Atomic Energy Agency (JAEA) and the National Institute of Advanced Industrial Science and Technology (AIST) signed an agreement of cooperative study on geological disposal in 2007. One of the ongoing joint studies under this agreement has been aimed at investigating regional-scale hydrogeological modeling using JAEA's Horonobe Underground Research Center. In the intermediate depth disposal, JNES conducted example analysis of reference facility and submitted the result to Nuclear Safety Commission of Japan (NSC). JNES is also listing issues to be addressed in the safety review of the license application and tries to make criteria of the review. Furthermore, JNES is developing analysis tool to evaluate long term safety of the facility and conducting an experiment to investigate long term behavior of engineered barrier system. In the near surface disposal of waste package, it must be confirmed by a regulatory inspector whether each package meets safety requirements. JNES continuously updates the confirmation methodology depending on new processing technologies. The clearance system was established in 2005. Two stages of regulatory involvement were adapted, 1) approval for measurement and judgment methods developed by the nuclear operator and 2) confirmation of measurement and judgment results based on approved methods. JNES is developing verification methodology for each stage. As for decommissioning, based on the regulatory needs and a research program

  3. Physical protection enhancements in Japan and the role of JNES

    International Nuclear Information System (INIS)

    Nishida, Seishi

    2010-01-01

    The possibility of terrorist attacks on nuclear material and nuclear facilities has posed a continuing threat since the events of September 11, 2001. The Japanese government has strengthened its physical protection regime, including legislative amendments, due to the necessity of upgrading the degree of protection of nuclear facilities to be equivalent to international levels, in order to cope effectively with the threat of theft of nuclear material and sabotage of nuclear facilities. In relation to these enhancements of the physical protection regime in Japan, the Japan Nuclear Energy Safety Organization (JNES) gives technical support to the regulatory agency, the Nuclear and Industrial Safety Agency (NISA), in the area of physical protection examination and inspection, through the development of technical guides for inspectors and operators, acquisition, analysis, and evaluation of related information, and international cooperation. This support is aimed at ensuring the consistent implementation of physical protection measures in Japan. In the future also, the JNES will provide further support to the NISA aimed at a well-developed physical protection framework in Japan, giving consideration to international physical protection enhancements such as publication of IAEA nuclear security series documents, inter alia Recommendations for physical protection of nuclear material and nuclear facilities being also Revision 5 of INFCIRC 225. (author)

  4. Proceedings of the JNES Congress and DERBI International Conference

    International Nuclear Information System (INIS)

    2016-06-01

    The DERBI (Development of Renewable Energies in Building and Industry) competitiveness cluster and the CNRS via the Federation for Research on Solar Energy (FedEsol) have joined forces once again to co-host 'The 2015 International Conference DERBI 2016' and 'The 2015 JNES Congress' from 29-30 June on the University Campus in Perpignan. The combination of these two events provides the national community working in the field of the use and the rational exploitation of solar energy with a forum for information and exchange across the entire range of themes within the industry, thus facilitating intensive interaction between the scientific and industrial communities. This year will see a particular focus on the theme of energy storage. The Production-Consumption adequacy, in combination with today's life styles in our societies, requires the massive development of auxiliary energy storage systems adapted to local resources and uses. These systems must warrant the networks stability and peaks smoothing in a context of continuous implementation of renewable energies, the operation of isolated sites, and finally, the de-compartmentalisation of energy vectors (electricity, gas, heat..). Scientific issues, technological challenges and economic models cover various domains such as: materials, components, systems, solar and renewable resource knowledge, optimized storage control, distributed or centralized storage through network connection and/or conversion into other energy vectors, city planning and architectures, and mobilities planning. The 3 days are made up of round tables, discussion sessions, posters and thematic workshops, enabling attendees to play an active role and learn about the latest innovations, new technologies and operational solutions. This document brings together 57 available abstracts of presentations given at the conferences

  5. Regulatory support activities of JNES by thermal-hydraulic and safety analyses

    International Nuclear Information System (INIS)

    Kasahara, Fumio

    2008-01-01

    Current status and some related topics on regulatory support activities of Japan Nuclear Energy Safety Organization (JNES) by thermal-hydraulic and safety analyses are reported. The safety of nuclear facilities is secured primarily by plant owners and operators. However, the regulatory body NISA (Nuclear and Industrial Safety Agency) has conducted a strict regulation to confirm the adequacy of the site condition as well as the basic and detailed design. The JNES has been conducting independent analyses from applicants (audit analyses, etc.) by direction of NISA and supporting its review. In addition to the audit analysis, thermal-hydraulic and safety analyses are used in such areas as analytical evaluation for investigation of causes of accidents and troubles, level 2 PSA for risk informed regulation, etc. Recent activities of audit analyses are for the application of Tsuruga 3 and 4 (APWR), the spent fuel storage facility for the establishment, and the LMFBR Monju for the core change. For the trouble event evaluation, the criticality accident analysis of Sika1 was carried out and the evaluation of effectiveness of accident management (AM) measure for Tomari 3 (PWR) and Monju was performed. The analytical codes for these evaluations are continuously revised by reflecting the state-of-art technical information and validated using the information provided by the data from JAEA, OECD project, etc. (author)

  6. Research of the improvement of the process, organization, etc. related to the emergency correspondence of JNES based on the cause analysis about emergency correspondence of JNES in case of the Fukushima Dai-ichi nuclear power plant accident

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    At the time of the occurrence of the Fukushima Dai-ichi nuclear power plant accident, JNES implemented various emergency correspondences. On the other hand, various organizations published the report about the Fukushima Dai-ichi nuclear power plant accident. In them, the problems about the regulatory body's regulatory process, regulatory organization, etc. are also pointed out. JNES is a designated public institution. JNES is required to improve process, organization, etc. related to emergency correspondence continuously based on the lessons learned obtained from the emergency corresponding experience about the Fukushima Dai-ichi nuclear power plant accident. Specifically, the following activities will be implemented in the 2014 and 2015 fiscal year. 1. Collect systematically and comprehensively the information about emergency correspondence of JNES in case of the Fukushima Dai-ichi nuclear power plant accident, and create the timeline of the event. 2. Specify problems and analyze human factors and organizational factors. 3. Specify the requirements for establishing a designated public institution's emergency correspondence based on the viewpoint of a human and an organization. 4. Publish the report which indicates collected information, the contents of analysis, proposals of improvement, etc. (author)

  7. JNES's Activities in the Extra-budgetary Programme of the International Seismic Safety Centre: WA1 Seismic Hazard

    International Nuclear Information System (INIS)

    Wu, Changjiang

    2014-01-01

    Issues in design basis ground motion development, the study items of Work Area 1 of IAEA/ISSC/EBP, and JNES's contributions were explained. It was also noted that the discussions and resolutions of this WS would be summarized in a technical document as task 1.4 of WA1. (author)

  8. Validation and Improvement of the FEMAXI-JNES Code by Using PIE Data at Extended Burnup. Final Report for FUMEX-III

    International Nuclear Information System (INIS)

    Hirose, Tsutomu; Miura, Hiromichi; Kitamura, Toshiya; Kamimura, Katsuichiro

    2013-01-01

    Japan Nuclear Energy Safety Organization (JNES) has participated in the IAEA FUMEX-III Coordinated Research Project (CRP) on the Improvement of Computer Codes Used for Fuel Behaviour Simulation for the following purpose. 1. Cooperate between member states and exchange information and expertise for understanding of fuel modelling and improvement 2. Develop and improve the FEMAXI-JNES code as an audit code for Japanese safety licensing review of fuel rod design, especially, - High burnup fuel - MOX fuel 3. Set the standard models for the FEMAXI-JNES code to provide best-estimate predictions of the thermal and mechanical performance of LWR fuel rod This is the JNES's final report for the FUMEX-III CRP. During the period of the CRP, JNES has modified pellet swelling and fission gas release models, and demonstrated the predictive capability relative to fuel centerline temperature, fission gas release, fuel rod internal gas pressure, cladding diametral deformation and cladding elongation by comparisons of integral code predictions of these parameters to experimental (measured) data from OECD/NEA IFPE database. (author)

  9. Vilistlasküsimus: Kes endistest õpetajatest on olnud sulle elus eeskujuks? / Aino Arro, Kersti Luha, Evar Ojasaar ...[jt.

    Index Scriptorium Estoniae

    2008-01-01

    Küsimusele vastavad Väike-Maarja Gümnaasiumi vilistlased: 41. lennu lõpetanu Aino Arro, 73. lennu lõpetanu Kersti Luha, 73. lennu lõpetanu Evar Ojasaar, 76. lennu lõpetanu Nele Münter-Trušin ja 80. lennu lõpetanu Arnis Alt

  10. Tööandja maine teadlik kujundamine loob edu / Kersti Hellerma

    Index Scriptorium Estoniae

    Hellerma, Kersti

    2007-01-01

    Kersti Hellerma magistritööst "Employer branding" selgub, et töötajad on sattunud otsustaja positsiooni, kus üks oluline töökoha valikukriteerium on tööandja maine ühiskonnas ehk kuvand, mille ettevõte on neile tööandjana jätnud. Vt. samas: Tööandja maineratas; Positiivne imago vähendab kulutusi; 10 atraktiivsemat tööandjat; Turundus ja finants populaarsed; Tehtav töö kõige olulisem; Riigifirmadel arenguruumi

  11. Kas õpilaste stress on viimase kümmekonna aastaga suurenenud? / Marit Tarkin, Enda Trubok, Kersti Rohtmets, Leena Arras, Kaie Lõhmus

    Index Scriptorium Estoniae

    2010-01-01

    Küsimusele vastavad Kuressaare gümnaasiumi õpetaja Marit Tarkin, Albu põhikooli õpetaja Enda Trubok, Audru keskkooli direktor Kersti Rohtmets, Tallinna Pääsküla gümnaasiumi direktor Leena Arras, C. R. Jakobsoni nim gümnaasiumi õppealajuhataja Kaie Lõhmus

  12. Pärnu Vallikääru park = Vallikääru park, Pärnu / Kersti Lootus ; intervjueerinud Margit Mutso

    Index Scriptorium Estoniae

    Lootus, Kersti, 1953-

    2012-01-01

    Pärnu Vallikääru pargi arhitektid Kersti Lootus, Kiur Lootus, Heidi Viilop ja Siim Lootus ning maastikuarhitekt Katri Soonberg (Lootusprojekt) pälvisid EK arhitektuuri sihtkapitali 2011. a. maastikuarhitektuuri preemia nüüdisaegse linnapargi lahenduse eest ajaloolises linnakindlustusvööndis. Metallikunstnik Harvi Varkki

  13. Kaadrid otsustavad endiselt kõik / Kersti Kivirüüt, Epp Adler, Andi Einaste, Maris Liiders ; intervjueerinud Meeli Parijõgi

    Index Scriptorium Estoniae

    2014-01-01

    Saku gümnaasiumis arutleti õpilaste korraldatud foorumil Eesti hariduse oleviku ja tuleviku üle. Intervjuu külalisesinejatega, kelleks tänavu olid haridus- ja teadusministeeriumi üldharidusosakonna peaekspert Kersti Kivirüüt, Epp Adler MTÜ-st HeadEst, Saku abivallavanem haridus-, kultuuri- ja sotsiaalhoolekande alal Andi Einaste ning Harju maavalitsuse haridus- ja sotsiaalosakonna juhataja Maris Liiders

  14. Armastuse valem / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2008-01-01

    17. okt. Rahvusooperis Estonia esietenduvast Mari Vihmandi ooperist "Armastuse valem", mis on loodud argentiina-saksa päritolu kirjaniku Esther Vilari romaani "Die Mathematik der Nina Gluckstein" ainetel (ooperi- ja raamatuesitlus toimub 18. okt. Rahvusooper Estonia talveaias, kohal on ka romaani autor)

  15. Lohutust Svingist / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2003-01-01

    Helilooja Raimond Valgre 90. sünniaastapäeva tähistamisest kontserdiga "Swing mind ikka lohutab..." Pärnu kontserdimajas 5. okt., Vanemuise kontserdimajas 6. okt., Estonia kontserdisaalis 7. oktoobril

  16. Riigilt saab toetust senisest rohkem inimesi / Heljo Pikhof

    Index Scriptorium Estoniae

    Pikhof, Heljo, 1958-

    2001-01-01

    Ilmunud ka: Meie Maa, 30. okt. 2001, lk. 2; Vooremaa, 30. okt. 2001, lk. 2; Koit, 30. okt. 2001, lk. 6; Lääne Elu, 30. okt. 2001, lk. 4. Vastuseks M. Treiali art.-le üle 80-aastastele pensionilisa maksmise kohta. Vanus ei ole objektiivne alus, et lisaraha maksta. Uuest toetuste süsteemist. Autor: Rahvaerakond Mõõdukad

  17. Töösuhted hakkavad looma / Heljo Pikhof

    Index Scriptorium Estoniae

    Pikhof, Heljo, 1958-

    2008-01-01

    Töölepingu seaduse eelnõust ning töösuhetest. Ilmunud ka Järva Teataja 14. okt. 2008, lk. 2 ; Vooremaa 14. okt. 2008, lk. 2 ; Türi Rahvaleht 17. okt. 2008, lk. 4 ; Harju Ekspress 17. okt. 2008, lk. 4 ; Meie Maa 17. okt. 2008, lk. 2 ; Valgamaalane 14. okt. 2008, lk. 2 ; Sakala 23. okt. 2008, lk. 2, pealkiri kujul: töösuhted võtavad ilmet ; Pärnu Postimees 22. okt. 2008, lk. 11 ; Koit 23. okt. 2008, lk. 6

  18. Pensioniraha jõuab igaüheni / Heljo Pikhof

    Index Scriptorium Estoniae

    Pikhof, Heljo, 1958-

    2008-01-01

    Pensionikindlustuse seaduse muudatusest, mis puudutab pensionide koju toomist. Ilmunud ka Sõnumitooja 29. okt. 2008, lk. 2 ; Võrumaa Teataja 28. okt. 2008, lk. 2 ; Koit 28. okt. 2008, lk. 4 ; Pärnu Postimees 29. okt. 2008, lk. 11 ; Vooremaa 30. okt. 2008, lk. 2 ; Harju Ekspress 31. okt. 2008, lk. 6 ; Sakala 4. november 2008, lk. 2 ; Virumaa Teataja 13. nov. 2008, lk. 11

  19. 12 kuulsat tugitooli / Kersti Pikk

    Index Scriptorium Estoniae

    Pikk, Kersti

    2012-01-01

    Eileen Gray, Alvar Aalto, Charles ja Ray Eames'i, Arne Jacobseni, Yrjö Kukkapuro, Alessandro Mendini, Ron Arad'i, Marcel Wanders'i, Fernando ja Humberto Campana, Antonio Citterio, Vincent van Duysen'i, Paola Navone disainitud tugitoolid

  20. Hotell Hilton Tallinn Park / Kersti Pikk

    Index Scriptorium Estoniae

    Pikk, Kersti

    2016-01-01

    Äriklassihotellide ketti Hilton kuuluv hotell Tallinnas. Arhitektuurse lahenduse autor Meelis Press. Interjööri kujundasid Soome büroo dSign Vertti Kivi & Co ja Allianss Arhitektid. Hotelli tube ja üldalasid kaunistavad Katrin Karu ja Maria Simsoni maalid

  1. Armin Tuulse ja kirikute uurimine / Kersti Markus

    Index Scriptorium Estoniae

    Markus, Kersti, 1962-

    2008-01-01

    Arhitektuuri- ja kunstiajaloolase tegevusest 1930. aastate Eestis ja Teise maailmasõja järgses Rootsis. Saksa ja rootsi teadlaste vahelistest kultuuriregiooni vaidlustest. Eesti kunsti omapära otsingutest. Keskaegse sakraalkunsti uurimise meetoditest

  2. Jõuluaja võimsaim kontsert / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2008-01-01

    Eesti Filharmoonia Kammerkoor esitab Georg Friedrich Händeli teose "Iisrael Egiptuses" 19. dets. Estonia kontserdisaalis, 20. dets. Jõhvi kontserdimajas ja 21. dets. Pärnu kontserdimajas (dirigent Daniel Reuss)

  3. Kes ikkagi asutas Pirita kloostri? / Kersti Markus

    Index Scriptorium Estoniae

    Markus, Kersti, 1962-

    2012-01-01

    Tegelik kloostri ülesehitaja oli Hinrich Swalbart. Kuna birgitiinide kloostrid allusid kohalikule piiskopile ning Swalbart oli kloostri rajamisega seotud alates 1405. aastast, siis võiks väita, et Pirita kloostri rajamise idee pärineb Saksa ordu kõrgmeistri Konrad von Jungingeni lähikonnast. Nimelt sai 1405. aastal Tallinna uueks piiskopiks Johannes III Aken, kes oli eelnevalt olnud ordu kõrgmeistri kaplan

  4. Alta peab tasuma Kalevile mais / Kersti Saar

    Index Scriptorium Estoniae

    Saar, Kersti

    2008-01-01

    Indrek Rahumaa juhitav Alta Capital peab tasuma Oliver Kruudale Kalevi tütarfirmade eest 660 miljonit krooni hiljemalt 30. maiks. Vt. samas: Investorid teavad tehingu hinda ja lõplikku tähtaega. Diagramm: Kalevi turuväärtus jääb Alta müügihinnale alla

  5. RAM publiku ees uue peadirigendiga / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2005-01-01

    Läti dirigent Kaspars Putninsh alustab oma esimest hooaega Eesti Rahvusmeeskoori peadirigendina Sergei Rahmaninovi teosega "Koguöine teenistus" (kontserdid 21. okt. Jõhvi Mihkli kirikus ja 25. okt. Tallinna Jaani kirikus)

  6. Disaininädal Stockholmis / Kersti Pikk

    Index Scriptorium Estoniae

    Pikk, Kersti

    2015-01-01

    Stockholmi mööbli- ja valgustimess veebruaris 2015. Tartu Kõrgema Kunstikooli üliõpilaste ja Triin Maripuu looming Greenhouse näitusealal. Näiteid messil eksponeeritud mööblist ja valgustitest

  7. Kaunikõlaline punkt / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2007-01-01

    Tallinna Filharmoonia hooaja lõppkontsertidest 17. mail Tallinna Mustpeade majas, 17. mail Jõhvi kontserdimajas, 18. mail Vanemuise kontserdimajas ja 19. mail Estonia kontserdisaalis//Tartu Noortekoor - segakoor

  8. Harmoonia Haydni ja Adamsiga / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2004-01-01

    Kontsertidel 21. dets. Pärnu kontserdimajas, 22. dets. Vanemuise kontserdimajas ja 23. dets. Estonia kontserdisaalis tulevad esitusele Joseph Haydni "Harmooniamissa" ja John Adamsi oratoorium "Harmonium"

  9. Võimsaim jõulusõnum / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2006-01-01

    J. S. Bachi "Jõuluoratoorium" Eesti Filharmoonia Kammerkoori ja Tallinn Baroque Orkestri esituses 21. dets. Vanemuise kontserdimajas, 22. dets. Pärnu kontserdimajas ja 23. dets. Estonia kontserdisaalis. Benjamin Britteni kantaadi "Püha Nicolaus" ja Gerald Finzi "In Terra Pax" esitusest 16. ja 17. dets. Tallinnas Niguliste kirikus

  10. Passion House - kirega loodud valmismaja / Kersti Pikk

    Index Scriptorium Estoniae

    Pikk, Kersti

    2013-01-01

    Janar Toomesso ja Priit Vahe valmismajade projektist Passion Smart Design Houses. Valminud on moodulmaja mudel M1 (Architect 11 meeskond, peaarhitekt Eero Endjärv). Sisearhitektid Hannelore Kääramees, Kätlin Ölluk, Maarja Valk-Falk

  11. Valge fungi uus tulemine / Kersti Pikk

    Index Scriptorium Estoniae

    Pikk, Kersti

    2007-01-01

    Peeter Tambu projekteeritud valge "eestiaegne" funk eramu, kus avatud planeeringu asemel on paraja suurusega eraldi toad, esikohal ruumide otstarbekus ja ratsionaalsus. Arhitekt on kujundanud interjööri ja mööbli

  12. Nargen Opera esimene festivalisuvi / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2006-01-01

    Dirigent Tõnu Kaljuste asutatud Nargen Opera avas 15. juunil Naissaarel oma esimese suure festivalisuve Veljo Tormise "Eesti naiste lauludega" (etendused 16., 17., 19-22. juunil), Nargen Festivali kontsertidest: "Merelaulud", Marko Matvere 4. juulil Viimsi mõisa õues, 8.-10. aug. Naissaarel, 14., 15. aug. Viinistu kunstimuuseumis, "Õhtud Jaan Tättega" 6., 9. juulil Reiu jõekäärus, "Vastutuulelaev" 22, 23, 26-30. juulil Naissaarel, "Õhtud Arvo Pärdiga" 3., 4. aug. Naissaarel, Joseph Haydni ooper "Üksik saar" 16., 17. aug. Viinistu kunstimuuseumis (info: www.nargenopera.ee)

  13. Sügisõhtu : [luuletused] / Kersti Merilaas

    Index Scriptorium Estoniae

    Merilaas, Kersti, pseud., 1913-1986

    1998-01-01

    Sisu: Sügisõhtu ; Hulguse laul ; Öö ; Mina magan ; Suletud luugid ; Viimne paat ; Usalda oma silmi ; Punane moon ; Rannapääsuke ; Mägiste Märt ; Võõrdumus ; "Minna midagi nõudmata..." ; Lihtne lauluke ; Kohtupäev ; Diogenes ; Kui põletasin need kirjad ; Laul ; Need vanad astjad ; Hobune ; Käolina ; Usutunnistus ; Nägemus

  14. Neli korrust, neli kaardimasti / Kersti Pikk

    Index Scriptorium Estoniae

    Pikk, Kersti

    2016-01-01

    Jan Skolimowski (KAMP Arhitektid) kujundatud Playtechi uued bürooruumid Ülemiste Citys. Kontori põhitoon on sinine ja läbiv kujunduselement kolmnurk. Graafika valmis koostöös disainibürooga Tuumik ning Martin Eelmaga

  15. Maailma tipud Mozarti festivalil / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2006-01-01

    Korea kammerorkestrist (kontserdid festivali "Mozart 250" raames 20. jaan. Pärnu kontserdimajas, 21. jaan. Estonia kontserdisaalis ja 22. jaan. Jõhvi kontserdimajas). Orkestrist The Orchestra of the Age of Enlightenment (kontsert 26. jaan. Estonia kontserdisaalis)

  16. Soome disainiklassika Adamson-Ericus / Kersti Koll

    Index Scriptorium Estoniae

    Koll, Kersti

    2000-01-01

    Adamson-Ericu muuseumis näitus "Soome disain 1900. Tehas "Iris", Louis Sparre ja Alfred William Finch". Näha saab ka Aito Mäkineni filmi "A. W. Finch - eurooppalainen". Koostajad ja kujundajad Marketta Tamminen, Heidi Gustafsson, Juha Jämbäck

  17. Ettevõtjaks juba koolis / Kersti Loor

    Index Scriptorium Estoniae

    Loor, Kersti

    2009-01-01

    Õpilasfirma on JAA (Junior Achievmenti Arengufond) ettevõtlusõppe programm, mille käigus keskkooliõpilased moodustavad oma firma, mõtlevad välja toote või teenuse, turustavad ja arendavad seda. Tänavuse Eesti võistluse võitja oli Tallinna 21. Kooli õpilasfirma Roheline Jälg, teiseks tuli Toila Gümnaasiumi firma Aktsioon ja kolmandaks Kohila Gümnaasiumi õpilasfirma Stuupak

  18. Noor talent ERSO ees / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2005-01-01

    Tallinna Muusikakeskkooli 10. klassi õpilane Jaan Kapp ja Eesti Riiklik Sümfooniaorkester esitavad Sergei Rahmaninovi teise klaverikontserdi 26. veebr. Estonia kontserdisaalis, pianistist. Ettekandel ka Richard Straussi "Alpisümfoonia"

  19. Trilli-Rilli : [lasteluuletused] / Heljo Mänd ; eesti keelest tõlkinud Nora Javorskaja

    Index Scriptorium Estoniae

    Mänd, Heljo

    2000-01-01

    Sisu: Trilli-Rilli ; Veliki li rebjatishki? ; Otkroite dveri ; Utro ; Kto tshto nossit ; Lessenka bozhei korovki ; Pessenka sredi travõ. Orig.: Mere taga, metsa taga... ; Tehke lahti värav ; Hommik : "Väiksed linnud harutavad..." ; Mida keegi kannab ; Lepatriinu trepp ; Rohulaul

  20. Õpetatud Eesti Seltsi Muuseumi asutamisest/ Kersti Taal

    Index Scriptorium Estoniae

    Taal, Kersti, 1953-

    2013-01-01

    1838. aastal asutatud Õpetatud Eesti Seltsi ülesannete elluviimiseks nähti ette ka muuseumi asutamine. Ettevalmistustöödest muuseumi asutamiseks. Ruumi- ja rahapuuduse kiuste kogunesid seltsile väärtuslikud kogud, kuigi muuseumi asutamiseni ei jõutud

  1. Muusikapärlid kõlavad taas / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2009-01-01

    Estonia kontserdisaalis 28. ja Vanemuise kontserdimajas 29. jaanuaril toimuvast Põhjamaade Sümfooniaorkestri kontserdist "Kohtumispaik Eesti" (dirigent Anu Tali, esitusel D. Shostakovitši ja P. Tšaikovski looming, soleerivad trompetist Sergei Nakariakov ja pianist Maria Meerovitš)

  2. Hino Mustjärve taimkatte areng / Kersti Kihno

    Index Scriptorium Estoniae

    Kihno, Kersti

    2008-01-01

    Hino Mustjärve setete õietolmu ja eoste analüüsist. Taimkatte piirkondliku arengu eripärast. Põhiliselt võib eristada kahte muutust : esiteks okasmetsade asendumist laialehiste ja segametsadega, teiseks metsade koosseisu muutust 3300-3400 aastat tagasi, kui valdavaks said männi-kase segametsad, paiguti kuusikud.

  3. Elamus väärt kontserdist / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2007-01-01

    Tallinna Filharmoonia uue sarja "Klaveripalavik" avakontserdil 30. sept. Mustpeade Majas esines koos Tallinna Kammerorkestriga pianist Irina Zahharenkova. Kontserdil anti üle Eesti Muusikanõukogu 2007. aasta muusikapreemiad, mille pälvisid Tõnu Kõrvits, Aile Asszonyi ja Jaan Ross

  4. Eesti kooriteose esiettekanne lätlastelt / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2003-01-01

    Ansambli LRC Chamber Singers kontsertidest Pärnu kontserdimaja kammersaalis 17. okt., Vanemuise kontserdimajas 18. okt., Rotermanni soolalaos 19. okt. Esiettekande tuleb NYYD 03 tellimusel valminud Rene Eespere ladinakeelne teos koorile ja vibrafonile "Armastaja sõnad"

  5. Pärnust otse Brüsselisse / Kersti Liiva

    Index Scriptorium Estoniae

    Liiva, Kersti

    2005-01-01

    Europe Direct on üle-euroopaline Euroopa Komisjoni algatatud infovõrgustik eesmärgiga anda infot Euroopa Liidu institutsioonide, seadusandluse, poliitikate, programmide ja rahastamisvõimaluste kohta. Europe Direct Pärnumaa infopunktist

  6. Eesti kodanikuühendused alkoholipoliitika kujundamisel / Kersti Kollom

    Index Scriptorium Estoniae

    Kollom, Kersti

    2007-01-01

    Kodanikuühenduste seas läbi viidud uuringust, nende hinnangust riiklikule alkoholipoliitikale ja kodanikuühenduste osast selle kujundamisel. Alkoholi liigtarvitamisega kaasnevatest probleemidest Eestis, alkoholipoliitika hetkeseisust

  7. Nokia tuleb ühes muusikaga / Kersti Saar

    Index Scriptorium Estoniae

    Saar, Kersti

    2008-01-01

    Nokia plaanib avada uut teenust Comes with Music, mis avab kliendile ligipääsu suurimate plaadifirmade Universal Music Croupi muusikakataloogidele. Diagramm: Nokia aktsia hind. Lisa: Comes with Music

  8. Pühade eel Haydni "Loomine" / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2007-01-01

    Joseph Haydni oratooriumi "Loomine" ettekandest 18. dets. Jõhvi kontserdimajas, 19. dets. Estonia kontserdisaalis, 21. dets. Vanemuise kontserdimajas ja 22. dets. Pärnu kontserdimajas, esinevad The Choir of New College Oxford, ERSO ja lauljad

  9. Pedagoogikaraamatukogude seminar Jyväskyläs / Kersti Kikkas

    Index Scriptorium Estoniae

    Kikkas, Kersti

    1997-01-01

    16.-19. oktoobrini 1997 toimus Jyväskylä Ülikooli Raamatukogus Põhja- ja Baltimaade pedagoogikaraamatukogude ühisseminar, mis oli mõeldud nimetatud raamatukogude direktoritele ja nende raamatukogude omanike esindajatele, rektoritele

  10. Peterburi eestlased Õpetatud Eesti Seltsis / Kersti Taal

    Index Scriptorium Estoniae

    Taal, Kersti, 1953-

    2008-01-01

    Fr. R. Kreutzwaldi osatähtsusest Õpetatud Eesti Seltsi ja Peterburi eestlaste ühendamisel. Kreutzwaldi reisist Peterburi. Philipp Karellist, Gustav Hirschist, Friedrich Enghoffist, Jakob Johnsonist, Johann Kölerist, Nikolai Mühlbergist, Cornelius Laalandist ja Nižni-Novgorodis elanud Joseph Kirnbachist

  11. Ostame maja! / Kersti Pikk, Aet Piel, Piret Tali

    Index Scriptorium Estoniae

    Pikk, Kersti

    2007-01-01

    Võrreldakse kolme eramut - Pirital, Viimsis (Arhitektuuriagentuur OÜ - arhitektid Inga Raukas, Toomas Tammis, Karli Luik ja Renee Puusepp) ja Harku vallas Vatslas. Lk. Oberhausi kinnisvaraspetsialisti Ene Arro kommentaar

  12. Kampaania "Märka igat last" / Kersti Puhm

    Index Scriptorium Estoniae

    Puhm, Kersti

    2003-01-01

    RNC (Regional Network for Children) on UNICEF-i ja valitsusväliste organisatsioonide regionaalne koostöövõrgustik, mis ühendab lapse õiguste teadvustamisele, propageerimisele ja kaitsele keskendunud vabaühendusi Kesk- ja Ida-Euroopa, SRÜ ja Balti riikides

  13. Ülestõusmispühad barokkmeistrite suurteostega / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2006-01-01

    G. F. Händeli "Ülestõusmisoratooriumi" ettekandest 16. apr. Estonia kontserdisaalis. J. S. Bachi "Missa h-moll" ettekandest 13. apr. Jõhvi kontserdimajas, 14. apr. Estonia kontserdisaalis, 15. apr. Pärnu kontserdimajas

  14. Ladina terminite kasutamine karistusõiguse praktikas / Kersti Heide

    Index Scriptorium Estoniae

    Heide, Kersti, 1989-

    2013-01-01

    Ladinakeelsete terminite kasutamisest, kontekstilisest analüüsist ja terminikasutuse probleemidest Eesti karistusõiguse praktikas Riigikohtu ja ringkonnakohtute lahendite põhjal. Artikkel põhineb autori samanimelisel magistritööl, mis on kaitstud 2013. a. kevadel Tartu Ülikooli õigusteaduskonnas. Graafik

  15. Sulam Eesti ja Inglise vaimulikust muusikast / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2007-01-01

    Eesti Filharmoonia Kammerkoori ja inglise organisti ning helilooja Christopher Bowers-Broadbenti kontserdist 9. veebr. Haapsalu Toomkirikus ja 10. veebr. Tallinna Niguliste kirikus (ettekandel C. Bowers-Broadbenti sekvents orelile ja koorile "7Words" ja Cyrillus Kreegi "Reekviem" uues seades)

  16. Laulud armastusest ja sõjast / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2008-01-01

    Eesti Filharmoonia Kammerkoori ja Helsingi Barokkorkestri kontserdist Claudio Monteverdi loominguga 25. jaan. Rakvere Gümnaasiumis, 26. jaan. Tartu Jaani kirikus ja 27. jaan. Tallinnas Mustpeade majas

  17. BALTECHi konverents TTÜs / Kersti Vähi

    Index Scriptorium Estoniae

    Vähi, Kersti

    2005-01-01

    Põhjamaade ja Balti riikide kaheksat tehnikaülikooli ühendav konsortsium BALTECH korraldas 14.-15. aprillil Tallinna Tehnikaülikoolis konverentsi "Innovation and industry relations within education and research", kus käsitleti peamiselt teadusasutuste ja ettevõtete koostööd

  18. Olympic võitleb rasvasemate marginaalide saamise nimel / Kersti Saar

    Index Scriptorium Estoniae

    Saar, Kersti

    2008-01-01

    Järsk marginaali kahanemine põhjustas Olympicule 2007. a. neljandas kvartalis puhaskasumi vähenemise. Kogu aasta puhaskasumiks saadi 381,7 miljonit krooni. Diagramm: Aktsia hind. Tabel: Majandustulemused

  19. Laenaja ohud ja võimalused / Kersti Arro

    Index Scriptorium Estoniae

    Arro, Kersti

    2008-01-01

    Laenu võtmisega kaasnevatest probleemidest ja võimalustest. Ilmunud ka Harju Ekspress 20. juuni 2008, lk. 4 ; Narva Postiljon 21. juuni 2008, lk. 2 ; Virumaa Teataja 26. juuni 2008, lk. 7 ; Lääne Elu 28. juuni 2008, lk. 6 ; Põhjarannik 28. juuni 2008, lk. 4 ; Pärnu Postimees 2. juuli 2008, lk. 15 ; Koit 1. juuli 2008, lk. 6 ; Sakala 17. juuli 2008, lk. 2

  20. Pirita klooster tänasest ooperikires / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2006-01-01

    Birgitta Festivalist 11.-22. aug. Tallinnas Pirita kloostris. Astor Piazzolla tango-ooperist "Maria de Buenos Aires" (etendused 11. ja 12. aug. Pirita kloostri varemetes). Moskva Helikon Opera etendustest: 15. aug. Mozarti ooper "Tituse halastus" ja 17. aug. Shostakovitshi ooper "Mtsenski maakonna Lady Macbeth". Carl Orffi "Carmina Burana" 18. aug., Verdi "Reekviem" 19. aug. ja kontsert "Tuulatud Thule" 20. augustil

  1. Oodatuimad ja kirutuimad talurahvaseadused : 1816. aasta Eesti- ja 1819. aasta Liivimaa talurahvaseadus : historiograafiline skits / Kersti Lust

    Index Scriptorium Estoniae

    Lust, Kersti, 1976-

    2012-01-01

    1816. ja 1819. aasta talurahvaseaduste kohta käivatest akadeemilisest seisukohtadest baltisaksa käsitluses, Eesti ja Läti ajalookirjutuses kahe maailmasõja vahel, nõukogulikus käsitluses, Eesti ajalookirjutuses taasiseseisvumise järel, pilgust väljastpoolt

  2. Sõjageograafia aine ja Eestimaa sõjageograafia 1920. aastatel / Kersti Vennik

    Index Scriptorium Estoniae

    Vennik, Kersti, 1975-

    2003-01-01

    Autori arvates puudub praeguses ohvitseride väljaõppes kursus, kus selgitataks täpsemalt Eesti maastike omadusi, erinevate maastiku-komponentide omavahelist koosmõju ning maastiku mõju kaitsejõudude tegevusele. Polkovnik Nikolai Reegi (1890-1942) panusest Eesti geograafiateaduse ajalukku

  3. Hubane salongiõhtu täis flamenkomuusikat ja -tantsu / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2009-01-01

    Tallinnas Mustpeade maja Valges saalis 14. novembril toimuvast kontsertetendusest "Salong. Madrid 1895", esinejateks kitarrist Kristo Käo, flamenkotantsija Maria Rääk ning löökpillimängija ja laulja Riho Ridbeck

  4. Avaliku sektori kulutused keskkonnakaitsele, 2006 = Environmental protection expenditure of public sector, 2006 / Kersti Salu

    Index Scriptorium Estoniae

    Salu, Kersti

    2008-01-01

    Keskvalitsus kulutas 2006. aastal 2,2 miljardit krooni keskkonnakaitsele, kohalikud omavalitsused 339 miljonit krooni ning Keskkonnainvesteeringute Keskuse keskkonnaprojektide kogumaksumus oli 2006. aastal ligikaudu 600 miljonit krooni. Tabelid. Diagramm

  5. 5 head soovi Euroopa tulevikuks / Thomas Wipf, Stephanie Dietrich, Michael Beintker ; tõlk. Kersti Rist

    Index Scriptorium Estoniae

    Wipf, Thomas

    2007-01-01

    25. märtsil 1957 alla kirjutatud rahvusvahelistest dokumentidest, mida tuntakse Rooma lepingute nime all. Lepingutel on oluline roll Euroopa poliitilisel ühendamisel. Lisatud: [Euroopa Liit tähistas 25. märtsil Rooma lepingute allkirjastamise 50. aastapäeva] ; [Evangeelsete Kirikute Osadusse Euroopas kuulub 105 kirikut]. Vt. samas: Kilp, Alar. Euroopa ime

  6. Agricultural labourers and their wages in Estland in 1885-1913 / Kersti Lust

    Index Scriptorium Estoniae

    Lust, Kersti, 1976-

    2007-01-01

    Eesti maatööliste palgast ja selles "moderniseerumise" ajal toimunud muutustest Põhja-Eesti mõisatööliste näitel. Nihkeid maatööliste ostujõus on püütud hinnata rukki ja või hindade alusel konstrueeritud indeksi abil

  7. The Estonian Tax System is Under Attack / Craig Rawlings, Daria Sivovol, Kersti Harkmann

    Index Scriptorium Estoniae

    Rawlings, Craig

    2006-01-01

    Ameerika, Briti ja Rootsi Kaubanduskojad Eestis ning Prantsuse-Eesti Äriklubi korraldasid seminari, kus Eesti maksusüsteemi tuleviku üle arutasid 15 põhiesinejat ning üle saja osavõtja. Väljavõte sessioonist, kus vastajateks olid Meelis Atonen, Eiki Nestor, Tarmo Kriis ja Vahur Kraft. Lisa: Esinejate tutvustus

  8. Korruptsioonikonverents valitsuse ja kolmanda sektori koostöö heaks / Rait Kaarma, Kersti Kurre

    Index Scriptorium Estoniae

    Kaarma, Rait

    2004-01-01

    Eesti Maksumaksjate Liidu korraldatud rahvusvahelisest konverentsist "Korruptsioonivastane võitlus Eestis". Väljavõtted Avo Üpruse, Pille Kustovi, Bogdan Senschuki, Anne Schmidti ja Norman Aasa sõnavõttudest

  9. Organisatsiooni riskijuhtimise tulevikusuunad ja siseauditi roll / Iivi Maspanov, Kersti Käbin

    Index Scriptorium Estoniae

    Maspanov, Iivi, 1950-

    2004-01-01

    Autorite hinnangul on riskijuhtimise eesmärgiks kogu organisatsiooni tegevust ja eesmärkide täitmist ohustavate riskide määratlemine, hindamine ja maandamine. Siseauditi funktsioon on üha enam muutumas kontrollijast konsulteerijaks. Skeem

  10. "Ariel" avab juudi kultuuri väärtusi / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2007-01-01

    Hispaania gambamängija Jordi Savalli ja ansambli Hesperion XXI kontserdist programmiga "El Paradiso Perdido" ehk "Kadunud paradiis" juudi süvakultuuri festivali "Ariel" raames 17. nov. Estonia kontserdisaalis

  11. "Üksinduse võlud" kõlavad Cafe Grandis / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2008-01-01

    Agentuur Corelli Music avas Pärnu hotellis Victoria "Café Grand muusikasalongi", mis pakub kord kuus pühapäeviti matinée-kontserte. Barokkansambli Corelli Consort kontserdist kavaga "Üksinduse võlud" 15. juunil ja tshellokvarteti C-JAM kontserdist 13. juulil (vt. www.corelli.ee)

  12. Kuritegelikke ühendusi puudutavate kuritegude sanktsioonide omavaheline ebakõla / Kersti Heide

    Index Scriptorium Estoniae

    Heide, Kersti, 1989-

    2013-01-01

    Kuritegelikku ühendusse kuulumine kui kvalifikatsiooni loomise alus karistusseadustiku eriosas sisalduvate üldkoosseisude juurde. Kuritegeliku ühenduse ja grupi eristamine, sanktsioonide ebakõla. Tabel

  13. Uuenev Saaremaa kroonuküla (1841-1919) / Kersti Lust

    Index Scriptorium Estoniae

    Lust, Kersti, 1976-

    2003-01-01

    Ülevaade Saaremaa kroonumõisatest, maakorraldusest kroonukülas, vabadike maakasutusest ja seda reguleerinud korraldustest, raharendi sisseseadmisest ning seda reguleerinud õigusaktidest, talude päriseksostmist reguleerinud seadustest, talurahva maanõudmistest 1905. aastal, maaküsimusest aastatel 1917-1919

  14. Cafe Grandi muusikasalong pakub värvika barokikava / Kersti Inno

    Index Scriptorium Estoniae

    Inno, Kersti, 1954-

    2008-01-01

    Agentuur Corelli Music avas Pärnu hotellis Victoria "Café Grand muusikasalongi", mis pakub kord kuus pühapäeviti matinée-kontserte. Barokkansambli Corelli Consort kontserdist kavaga "Üksinduse võlud" 15. juunil (vt. www.corelli.ee)

  15. Liibüa tudeng kaitses magistrikraadi / Kersti Vähi

    Index Scriptorium Estoniae

    Vähi, Kersti

    2006-01-01

    5. juunil kaitses Tallinna Tehnikaülikoolis tehnikateaduste magistri kraadi Liibüa tudeng Mohamed D. Sidon. Töö teemal "Tuuleturbiinides kasutatava madalakiiruselise alalismagnetitega sünkroongeneraatori uurimus" kaitses ta elektrotehnika aluste ja elektrimasinate instituudis

  16. [Johan Eellend. Cultivating the Rural Citizen : Modernity, Agrarianism and Citizenship in Late Tsarist Estonia] / Kersti Lust

    Index Scriptorium Estoniae

    Lust, Kersti, 1976-

    2008-01-01

    Arvustus: Eellend, Johan. Cultivating the Rural Citizien : Modernity, Agrarianism and Citizenship in Late Tsarist Estonia. Stockholm : Stockholm Universty, 2007. Eesti agraarideoloogia kujunemist ja olemust käsitlevast dissertatsioonist. Tegemist on Eesti ühiskondliku mõtte voolude ja nende mõjuulatuse tavapärasest erineva nägemusega

  17. Peidetud mõte : Euroopa portselanfiguuride tähendusest / Kersti Kuldna-Türkson ; tõlk. Katrin Kivimaa

    Index Scriptorium Estoniae

    Kuldna-Türkson, Kersti

    2005-01-01

    Esemete funktsioonide ja sümboolsete tähenduste teisenemisest sõltuvalt elulaadist ja keskkonnast. 18.-20. saj. portselanfiguuridest Kadrioru Kunstimuuseumi ja Mikkeli muuseumi kogude põhjal - figuraalsed lauakaunistused, realistlikud kompositsioonid, sari "Venemaa rahvad", 20. saj. vene agitportselan. Portselanitööstus Euroopas

  18. 23. IX avasid Eesti Rahvusraamatukogu haldusdirektor Mati Kibin ja näituste osakonna juhataja Kersti Tiik...

    Index Scriptorium Estoniae

    2003-01-01

    Venemaa Riiklikus Raamatukogus Moskvas rändnäitus ""Kalevipoeg", üks ennemuistne eesti jutt", mis keskendub "Kalevipoja" eri väljaannete illustratsioonidele (autorid Kristjan Raud, Paul Luhtein, Alo Hoidre, Ott Kangilaski, Richard Sagrits, Eerik Haamer, Evald Okas) ja tõlgetele ning mida täiendab valik Günther Reindorffi illustratsioone F. R. Kreutzwaldi "Eesti rahva ennemuistsetele juttudele" jm.

  19. Tervise enesehinnangu sotsiaalmajanduslikud erinevused Eestis : Euroopa sotsiaaluuring 2004 / Ülle Sildever, Kersti Pärna, Inge Ringmets

    Index Scriptorium Estoniae

    Sildever, Ülle

    2008-01-01

    Euroopa sotsiaaluuringust, mis korraldati Eestis ajavahemikul novembrist 2004 kuni jaanuarini 2005 ja mille käigus uuriti 35-54aastaste täiskasvanute tervise enesehinnangu sotsiaal-majanduslikke erinevusi. Lisatud statistilised tabelid

  20. Näitused / Katrin Kurik

    Index Scriptorium Estoniae

    Kurik, Katrin

    1998-01-01

    Linnagalerii Tallinnas: Anna Pauli tekstiilid ja Andras Huberi skulptuurid (Ungari); Kullo lastegalerii: Heli Männi ja Tondiraba keskkooli kunstiklasside õpilaste "Veneetsia maskid"; Tammsaare majamuuseum: Kersti Karu keraamika

  1. Koolidirektor muretseb / Age Viil ; vahendas Sirje Tohver

    Index Scriptorium Estoniae

    Viil, Age

    1997-01-01

    Tallinna Humanitaarkeskkooli direktor Age Viil õpetaja palgaprobleemidest, riigieksamitest, kooli õppekavast, kommenteerivad Anneli Kommer, Ants Eglon, Hanno Isok, Toivo Sikk ja Kersti Kaldma Haridusministeeriumist

  2. Maa asendamise ja ostueesõigusega erastamise kord Tallinna linnas : [bakalaureusetöö] / Kersti Kägi ; Tartu Ülikool, õigusteaduskond ; juhendaja: Kalle Merusk

    Index Scriptorium Estoniae

    Kägi, Kersti

    1995-01-01

    Maade asendamine ja ostueesõigusega erastamine maareformi osana, õigusvastaselt võõrandatud maa asendamine, maa ostueesõigusega erastamine; maa asendamise kord Tallinna linnas, maa ostueesõigusega erastamise kord Tallinna linnas

  3. Põlisrahvuste taaseelistamise poliitika Balti liiduvabariikides? : Eestimaa Kommunistlik Partei pärast Teist maailmasõda / David Feest ; tõlk. Kersti Lust

    Index Scriptorium Estoniae

    Feest, David, 1969-

    2007-01-01

    Pärast Teist maailmasõda oli rahvuslikul põhimõttel silmanähtav osa NSV Liidu sisepoliitikas. Rahvuslikest kvootidest EKP juhtkonnas. 1950. aastate parteipuhastustest, mis tähistavad rahvuse taaseelistamise poliitika lõppu Eestis. Vastuoludest valla tasandil. Kollektiviseerimisest kui rahvuslike vastuolude haripunktist

  4. Kirjanduskriitikute suvemängud / Kärt Hellerma

    Index Scriptorium Estoniae

    Hellerma, Kärt, 1956-

    2007-01-01

    Arvustus: Lodge, David. Ühest kohast teise / tlk. Aet Varik. Tallinn : Varrak, 2005 ; Lodge, David. Väike maailm / tlk. Kersti Unt. Tallinn : Varrak, 1996 ; Lodge, David. Väärt töö / tlk. Kersti Unt. Tallinn : Varrak, 2006

  5. Iga otsus viib tagajärjeni, millest õppida / Ave Paavo

    Index Scriptorium Estoniae

    Paavo, Ave

    2005-01-01

    Erinevatest õpetlikest töösituatsioonidest oma kogemuse põhjal räägivad Ruutmeeter OÜ tegevjuht Jana Põim, AS-i Baltazar finantsdirektor Kersti Rekor, HansaWorld Estonia AS-i tegevjuht Kersti Renzer ja MAP Eesti AS-i juhataja Külli Meister

  6. Mitmekordsed rollimängud / Aita Kivi

    Index Scriptorium Estoniae

    Kivi, Aita, 1954-

    2000-01-01

    Sisu : Toomas Vint. Nädalavahetusel. Mängides; William Somerset Maugham. Jõulupuhkus; Meredith Rich. Parfüümi essents; Tordis ₍rjasaeter. Inimeste südamed : Sigrid Undset; C. David Heymann. Naine nimega Jackie; Heljo Jaik-Corradi. Mõtteid ei saa pidada; Jane Heller. Mõrvakatse merel

  7. Tõlkeküsimused

    Index Scriptorium Estoniae

    2005-01-01

    Tõlkimine ja tõlgendamine, õigussüsteemide erisused, udutamine, moodultõlge, metafoorse tähendusülekandega terminite tõlkimine, Euroopa Kohtus kasutatavaid termineid, Euroopa Liidu õigusaktide jaotuselemendid ja neile viitamine. - Kokkuvõte Hille Saluääre, Kristiina Rossi, Mari Suti, Heljo Kontsa, Helve Hennoste, Aime Vettiku, Madis Vunderi ja Ülle Raigi artiklitest

  8. Lastekirjandus 2008 kurja kriitiku pilgu läbi / Ilona Martson

    Index Scriptorium Estoniae

    Martson, Ilona, 1970-

    2009-01-01

    Ülevaade 2008. aasta eesti lastekirjandusest. Pikemalt käsitletakse järgmisi autoreid ja nende teoseid: Piret Raud "Printsess Luluu", Aino Pervik "Presidendilood", Kristiina Kass "Petra lood", Kätlin Vainola "Mia, Konrad ja avanevad uksed", Kerttu Soans "Külaline vannis", Wimberg "Härra Padakonn", Leelo Tungal "Seltsimees laps", Kadri Hinrikus "Miia ja Friida", Ivar Soopan "Kõik poisid ei saa suureks", Siiri Laidla "Raamatukogunõid Rosaalie", Siiri Laidla "Armas hunt", Reeli Reinaus "Saladuslik päevik", Tiia Selli "Neletriin ja Kapi-Kaarup", Markus Saksatamm "Võlur Sinku-Vinku ja nõiatrall", Evelin Samuel "Ükskord, kui sadas vihma", Mikä Keränen "Varastatud oranž jalgratas", Ivo Parbus "Draakon Rudolf", Urmas Nemvalts "Väikeste meeste lennumasinajutud", Lehte Hainsalu "Väike valge", Jaan Tangsoo "Mina ja minu pere", Aidi Vallik "Pints ja Tutsik", Heiki Vilep "Horlok ja Ürgvärava võti", Evelin Samuel "Hiigelsoojad pilvelambad", Sulev Oll "Hea tuju kuju", Paul-Eerik Rummo "Kui lähed teele koidu eel", Heljo Mänd "Suve suurmüük", Heljo Mänd "Sügise süda", Heljo Mänd "Kevade reklaam", Heljo Mänd "Talve Top", Ülo Pikkov. Presidendi torukübar

  9. Inimese mõõde II. Kuue- ja seitsmekümnendad : kirjanduslooline fragmentaarium 1960.-1970. aastail tegutsenud kirjanikest / Jaak Urmet

    Index Scriptorium Estoniae

    Urmet, Jaak, 1979-

    2015-01-01

    Katkendid intervjuudest ja vestlustest Leo Metsariga, Valda Rauaga, Mihkel Rauaga, Enn Vetemaaga, Andres Ehiniga, Väino Ilusaga, Ülo Tuulikuga, Villem Grossiga, Heljo Männiga, Maie Kaldaga, Jaan Isotammega, Vaapo Vaheriga, Jaan Kaplinskiga, Mati Undiga, Vaino Vahinguga, Lea Tormisega, Ralf Parvega, Oskar Kruusiga ja Toomas Vindiga

  10. Inimese mõõde II. Kuue- ja seitsmekümnendad : kirjanduslooline fragmentaarium 1960.-1970. aastail tegutsenud kirjanikest / Jaak Urmet

    Index Scriptorium Estoniae

    Urmet, Jaak, 1979-

    2011-01-01

    Katkendid intervjuudest ja vestlustest Leo Metsariga, Valda Rauaga, Mihkel Rauaga, Enn Vetemaaga, Andres Ehiniga, Väino Ilusaga, Ülo Tuulikuga, Villem Grossiga, Heljo Männiga, Maie Kaldaga, Jaan Isotammega, Vaapo Vaheriga, Jaan Kaplinskiga, Mati Undiga, Vaino Vahinguga, Lea Tormisega, Ralf Parvega, Oskar Kruusiga ja Toomas Vindiga

  11. "Rohkem naisest kui näitlejast..." / Meelis Kapstas

    Index Scriptorium Estoniae

    Kapstas, Meelis, 1963-

    2006-01-01

    Ilmus Ita Everi elulooraamat "Ita Ever. Elu suuruses". Näitlejannad Viire Valdma, Mari-Liis Lill, Ülle Kaljuste, Britta Vahur, Elina Reinold, Kersti Kreismann, Merle Palmiste ja Ülle Ulla avaldavad oma esmamulje raamatust

  12. USA väikesed sõbrad Valges Majas / Neeme Raud

    Index Scriptorium Estoniae

    Raud, Neeme, 1969-

    2018-01-01

    President Kersti Kaljulaid külastab Washingtoni ja kohtub USA riigipea Donald Trumpiga. Eesti presidentide eelmistest kohtumistest USA riigipeadega ning Eesti ja Ameerika Ühendriikide kaitsekoostööst

  13. Kena kingitus emale / Olivia Saar

    Index Scriptorium Estoniae

    Saar, Olivia

    2008-01-01

    Tutvustus: Laulud emast / [koostanud Olivia Saar]. Tallinn : TEA Kirjastus, 2007 ; Seitse paid : laulud emale / [Kalju Kangur, Ira Lember, Kersti Merilaas ... jt. ; koostanud Olivia Saar] ; pildid joonistanud Kirke Kangro. Tallinn : TEA Kirjastus, 2007

  14. PR-teenuse hind tõuseb 20% / Eda-Liis Kann

    Index Scriptorium Estoniae

    Kann, Eda-Liis, 1979-

    2004-01-01

    Suhtekorraldusfirmad prognoosivad aasta teiseks pooleks PR-teenuste 20protsendilist hinnatõusu. Kommenteerivad Kersti Luha, Maren Pärn, Ingrid Eha, Maria Raudsepp, Heidi Pihlak ja Rein Meripõld. Lisa: Väikefirmale on PR-teenus kallis

  15. Sügiskonverents "Kunst paguluses"...

    Index Scriptorium Estoniae

    2008-01-01

    28. VIII Kumu Kunstimuuseumi auditooriumis toimuva konverentsi kava. Esinevad Jaan Undusk, Piret Kruuspere, Avo Hirvesoo, Mara Lace, Osvaldas Daugelis, Piret Noorhani, Irja Bergström, Tiiu Talvistu ja Kersti Koll

  16. Viljandi mõisa aida kohandamine Eesti Pärimusmuusika Keskuseks = Renovation of the Viljandi manor's storehouse into the Estonian Traditional Music Centre / Margit Mutso

    Index Scriptorium Estoniae

    Mutso, Margit, 1966-

    2009-01-01

    Hoone arhitektuuriajaloolised eritingimused koostas Anne Lass, arhitekt on Raivo Mämdmaa, sisearhitekt Kersti Leinbock, konstruktor Hans Priks, sepiste autor Heigo Jelle. Hoonel on klaasist juurdeehitis. Žürii hinnang kultuurkapitali aastapreemiale esitatud sisekujundusele

  17. Süütust näpates : Tanel Veenre fotoseeria teatrikostüümidest Draamateatri laval / Tanel Veenre, Hanna Tiidus, Margit Soosaar...[jt.

    Index Scriptorium Estoniae

    2007-01-01

    Stilist: Hanna Tiidus. Naine: Merle Palmiste. Poiss: Joonas (MJ-Models). Kostüümid etendustest "Rohuvoodi" (Aime Unt), "Rehepapp", "Tõeline inspektor koer" (Ene-Liis Semper), "Liilia" (Lilja Blumenfeld), "Mort" (Kersti Varrak), "Potilaadale" (Reet Aus), "Amadeus" (Krista Tool)

  18. Eesti filmitegijad tõid Rjazanist preemiaid

    Index Scriptorium Estoniae

    2002-01-01

    Rjazanis 22.-31. maini toimunud festivalil "Zolotoi Vitjaz" said eesti filmitegijad kaks eriauhinda : Inglismaal elav Kersti Uibo filmi "Kitsas on värav" eest ja Andrei Tantsõrev filmi "Lend kanepipõllu kohal" eest

  19. Brian Frieli illusioonidele rajatud konservatism / Valle-Sten Maiste

    Index Scriptorium Estoniae

    Maiste, Valle-Sten, 1972-

    2006-01-01

    Brian Friel "Kodukoht" - Eesti Draamateatri etendus Keila Joa mõisas, lavastaja Priit Pedajas, kunstnik Pille Jänes. Brian Friel "Järelmäng" Eesti Draamateatri Maalisaalis, lavastanud ja mängivad Kersti Kreismann ja Martin Veinmann

  20. Moodne aeg käib alla / Valner Valme

    Index Scriptorium Estoniae

    Valme, Valner, 1970-

    2008-01-01

    Arvustus: Beigbeder, Frédéric. Armastus kestab kolm aastat : romaan / prantsuse keelest tõlkinud Anti Saar. Tallinn : Varrak, 2008 ; Cusk, Rachel. Arlington Park / tõlkinud Kersti Unt. Tallinn : Varrak, 2007

  1. Tunnustame tõenduspõhise õendusabi edendajaid / Ester Öpik, Ilme Aro

    Index Scriptorium Estoniae

    Öpik, Ester

    2014-01-01

    Tunnustati meditsiiniõdesid Tiina Freimanni, Reet Urbanit, Marika Asbergi, Tiina Tõemetsa, Kersti Viitkarit ja Ireen Bruusi Eesti Õdede Liidu poolt 2011. aastani kaitstud õendusteaduslike uurimistööde eest

  2. 23. august 1989: Balti kett / koostanud Vesta Reest, Kadi Tarand

    Index Scriptorium Estoniae

    2013-01-01

    Balti riikide ühist protestiavaldust Molotovi-Ribbentropi pakti sõlmimise 50. aastapäeval meenutavad kunstnik Heinz Valk, Euroopa Kontrollikoja liige Kersti Kaljulaid ja Euroopa Parlamendi saadik Vilja Savisaar-Toomast

  3. Õppetöö = Studies

    Index Scriptorium Estoniae

    2008-01-01

    Uue vastuvõtueeskirja kohaselt saab õpinguid doktorantuuris alustada aastaringselt; lihtsustub erivajadustega tudengite vastuvõtt. 2007. a. parimad õppejõud: Inga Kuznetsova (humaniora), Kristel Ruutmets (socialia), Sirje Mäeorg (realia et naturalia), Kersti Kokk (medicina)

  4. Emergency preparedness and its enhancement in Japan: From perspectives of infrastructure preparation, and exercise enhancement

    International Nuclear Information System (INIS)

    Funahashi, T.

    2010-01-01

    The organizational structure, procedures and infrastructures for the nuclear emergency response were established in Japan in the aftermath of the JCO accident and have been improved through exercises, drills and training. This paper overviews the infrastructure for the emergency response prepared by JNES and exercises implemented or supported by JNES for nuclear emergency preparedness. Approaches to feeding back exercise results are also addressed. (author)

  5. Ühine vara, eraldi võlad: võlausaldajate nõuete rahuldamine abikaasade ühisvara arvel / Kai Kullerkupp, Triin Uusen-Nacke, Kersti Kerstna-Vaks

    Index Scriptorium Estoniae

    Kullerkupp, Kai, 1975-

    2016-01-01

    Ühisvara mõistest Eesti perekonnaseaduses. Abikaasade võlausaldajate huvide kaitsest, võlausaldajate nõuete rahuldamisest ühisvara arvelt ning selle tagamisest täitemenetluses ja pankrotimenetluses. Sisaldab asjakohast kohtupraktikat

  6. Harvesting an experiment: observations of bushy landrace winter rye in a small scale experimental slah-and-burn field in Estonia / Kersti Kihno, Liisi Jääts, Mati Laane

    Index Scriptorium Estoniae

    Kihno, Kersti, 1963-

    2015-01-01

    13. sajandi alguseks kujunes talirukis Eesti ala tähtsaimaks toiduteraviljaks ning oli 13. - 18. sajandini ka peamine ekspordiartikkel. Alepõllul kasvatatud puhmasrukis andis suuri saake, kuid oli nõudlik maa viljakuse suhtes. Eksperiment toimus Tartumaal. Eksperimendi tulemused kinnitasid ajalooallikate kirjeldusi - soodsates tingimustes on puhmasrukis väga saagikas. Kuigi väiksemõõtmelise eksperimendi tulemusi ei saa käsitleda kui suure alepõllu täpset mudelit, annab see siiski olulist materjali talirukki maasordi kohta, mis on siiani saanud teenimatult vähe tähelepanu

  7. Tõde pensionide kojukande kohta / Marika Tuus

    Index Scriptorium Estoniae

    Tuus, Marika, 1951-

    2008-01-01

    Pensionide kojukande muudatustest ning vastuseks 28. oktoobri ajalehes ilmunud Heljo Pikhofi artiklile "Pensioniraha jõuab igaüheni". Ilmunud ka Harju Ekspress 7. nov. 2008, lk. 9 ; Põhjarannik 6. nov. 2008, lk. 2 ; Võrumaa Teataja 8. nov. 2008, lk. 2 ; Pärnu Postimees 6. nov. 2008, lk. 11 ; Vooremaa 13. nov. 2008, lk. 2 ; Virumaa Teataja 21. nov. 2008, lk. 11, pealkiri kujul: veel pensionide kojukandest ; Sõnumitooja 12. nov. 2008, lk. 2

  8. Development of infrastructure for the regulatory authority to implement risk-informed regulation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    It is important to assure the technical adequacy of probabilistic risk assessment (PRA) to implement risk-informed regulation of nuclear power plants (NPPs). JNES has been conducting various activities, such as development of PRA model, method, and data base, in order to assure the technical adequacy of PRA as development of the infrastructure for the regulatory authority to implement risk-informed regulation. In 2012, JNES updated the reliability data base used in PRA and improved PRA models to enhance the technical bases of PRA. In addition, JNES has been establishing the PRA model for fuel damage in the spent fuel storage pool in NPPs. As for improvement of PRA model for core damage in reactor, JNES conducted the study including feasibility of a simplified reliability model for digital I and C system developed by the digital I and C task group of OECD/NEA CSNI WGRISK by reproducing the sample calculation, and improvement of PRA models of individual NPPs in Japan. JNES is making effort to develop the procedures of internal fire PRA and internal flooding PRA. To improve the internal fire PRA, JNES is participating in OECD/NEA FIRE project to obtain the latest information and to validate and improve the fire propagation analysis codes and the parameters. JNES is establishing a method for analyzing internal influence due to flooding in NPPs, and this method is the base to develop the procedure of internal flooding PRA. (author)

  9. Investigation and evaluation for environmental impact at Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    2012-01-01

    In 2012, JNES investigated the weather data and the environmental monitoring data and constructed the method to specify contribution of the environmental impact from each plant based on the dose analysis result at Unit 1-3 of Fukushima Daiichi NPP accident. JNES calculated the dose rate in an accident early stage based on analysis of a monitoring data. Moreover, JNES evaluated the dose by additional release of the radioactive material in case of assuming the loss of coolant injection to a nuclear reactor by the request of NISA. (author)

  10. Collection and accumulation of seismic safety research findings, and considerations for information dissemination

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Seismic Safety Division of JNES is collecting and analyzing the findings of seismic safety research, and is developing a system to organize and disseminate the information internally and internationally. These tasks have been conducted in response to the lessons learned from Fukushima Daiichi NPP accident. The overview of the tasks is as follows; 1) Collection of the knowledge and findings from seismic safety research. JNES collects information on seismic safety researches including the 2011 off the Pacific coast of Tohoku Earthquake. The information is analyzed whether it is important for regulation to increase seismic safety of NPP. 2) Constructing database of seismic safety research. JNES collects information based on documents published by committee and constructs database of active faults around NPP sites in order to incorporate in the seismic safety review. 3) Dissemination of information related to seismic safety. JNES disseminates outcomes of own researches internally and internationally. (author)

  11. Collection and accumulation of seismic safety research findings, and considerations for information dissemination

    International Nuclear Information System (INIS)

    2013-01-01

    Seismic Safety Division of JNES is collecting and analyzing the findings of seismic safety research, and is developing a system to organize and disseminate the information internally and internationally. These tasks have been conducted in response to the lessons learned from Fukushima Daiichi NPP accident. The overview of the tasks is as follows; 1) Collection of the knowledge and findings from seismic safety research. JNES collects information on seismic safety researches including the 2011 off the Pacific coast of Tohoku Earthquake. The information is analyzed whether it is important for regulation to increase seismic safety of NPP. 2) Constructing database of seismic safety research. JNES collects information based on documents published by committee and constructs database of active faults around NPP sites in order to incorporate in the seismic safety review. 3) Dissemination of information related to seismic safety. JNES disseminates outcomes of own researches internally and internationally. (author)

  12. Safety technical investigation activities for shipment of damaged spent fuels from Fukushima Daiichi Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Japan Nuclear Energy Safety Organization(JNES) carries out the investigation for damaged fuel transportation from Fukushima Daiichi Nuclear Power Station(1F) under safety condition to support Nuclear Regulation Authority (NRA). In 2012 fiscal year, JNES carried out the investigation of spent fuel condition in unit 4 of 1F and actual result of leak fuel transport in domestic /other countries. From this result, Package containing damaged fuel from unit 4 in 1F were considered. (author)

  13. Improvement of infrastructure for risk-informed regulation

    International Nuclear Information System (INIS)

    Muta, Hitoshi; Tanji, Junichi; Kondo, Keisuke; Uchida, Tsuyoshi; Ito, Tomomichi

    2011-01-01

    Improvement of the infrastructure of probabilistic safety assessment (PSA) is essential to the risk-informed regulation for nuclear power plants. JNES conducted update of initiating event frequency and improvement of method for uncertainty analysis to enhance the technology bases of PSA in 2010. Furthermore, JNES improved human reliability assessment method and reliability assessment method for digital reactor protection systems. JNES estimated initiating event frequencies both for power and shutdown operation based on the recent operating experiences in NPPs of Japan using hierarchical Bayesian method. As for improvement of uncertainty analysis method, JNES conducted trial analysis using SOKC (State-Of-Knowledge Correlation) for representative PWR and BWR of Japan. The study on the advanced HRA method with operator cognitive action model was conducted. The study on reliability analysis method for digital reactor protection systems using Bayesian Network Method was conducted. In order to ensure the quality of PSA, JNES studied requirements and methods for PSA peer review via the preparation of peer review for PSA of a representative Japanese BWR plant conducted by JNES. As an effort to develop the procedures of internal fire PSA and internal flooding PSA, trial analyses were conducted to grasp the risk level cause by fire and flooding in nuclear power plants. JNES participated in OECD/NEA PRISME and FIRE project to obtain the latest information and data to validate and improve the fire propagation analysis codes and the parameters for fire PSA. Furthermore, JNES studies schemes for endorsement and application in risk-informed regulation of PSA standards established by Atomic Energy Society of Japan. (author)

  14. Eesti teatri aastaauhinnad 2001

    Index Scriptorium Estoniae

    2002-01-01

    Lavastajaauhind Hendrik Toompere, meesnäitleja Mait Malmsten, naisnäitleja Kersti Kreismann, meeskõrvalosatäitja Sulev Teppart, naiskõrvalosatäitja Kersti Tombak, kunstnikupreemia Ene-Liis Semper, eriauhind Marko Matvere, tantsulavastuse auhind Age Oks, Toomas Edur, Katrin Essenson, kriitikuauhind Reet Neimar ja Lea Tormis, Ants Lauteri preemia Katariina Lauk-Tamm ja Andres Raag, Salme Reegi auhind VAT Teater, Priit Põldroosi preemia Ingo Normet, Aleksander Kurtna preemia Tõnu Oja ja Villu Kangur, Georg Otsa preemia Pille Lill, muusikalavastuse auhind Mati Palm, muusikalavastuse eriauhind Teo Maiste

  15. Improvement of infrastructure for risk-informed regulation

    International Nuclear Information System (INIS)

    2012-01-01

    Improvement of the infrastructure of probabilistic safety assessment (PSA) is essential to the risk-informed regulation for nuclear power plants. JNES conducted update of initiating event frequencies and improvement of the method for uncertainty analysis to enhance the technology bases of PSA in 2011. Furthermore, JNES improved the human reliability analysis method and the reliability analysis method for digital reactor protection systems. JNES estimated initiating event frequencies both for power and shutdown operation based on the recent operating experiences in Nuclear Power Plants (NPPs) of Japan using the hierarchical Bayesian method. As for improvement of the uncertainty analysis method, JNES conducted trial analyses using SOKC (State-Of-Knowledge Correlation) for the representative PWR plant and BWR plant of Japan. The study on the advanced HRA method with operator cognitive action model was conducted to improve a quality of HRA. The study on analyses of 'defense in depth' and 'diversity' for introducing digital instrumentation and control (I and C) systems was conducted. In order to ensure the quality of PSA, JNES conducted a peer review of a representative Japanese BWR plant PSA by the professional PSA engineers from the U.S. in order to extract to improve quality of PSA, and made an effort to develop the procedures of internal fire PSA. JNES participated in OECD/NEA PRISME and FIRE project to obtain the latest information and data to validate and improve the fire propagation analysis codes and the parameters for fire PSA as well. Furthermore, JNES studied schemes for the endorsement and application in the risk-informed regulation of PSA standards established by Atomic Energy Society of Japan. (author)

  16. Algab sari "Kontserdid Kunstihoones". Bachi "Jõuluoratoorium" Jaani kirikutes

    Index Scriptorium Estoniae

    2008-01-01

    Soprani Kersti-Ala Murri ja akordionisti Jaak Lutsoja kontserdist Eesti Interpreetide Liidu korraldatava kontserdisarja "Kontserdid Kunstihoones" raames 21. dets. Tallinna Kunstihoone suures saalis. J. S. Bachi "Jõuluoratooriumi" ettekandest 28. dets. Tartu Jaani kirikus ja 29. dets. Tallinna Jaani kirikus (esinevad kammerkoor Voices Musicales solistidega ja Corelli Barokkorkester, dirigent Risto Joost)

  17. Two Close Ones / Tiina Sarapu

    Index Scriptorium Estoniae

    Sarapu, Tiina

    2006-01-01

    Tallinna IV tarbekunstitriennaalist "Kaks lähedast" Eesti Tarbekunsti- ja Disainimuuseumis 18.03-21.05.2006. Esimese preemia said Kersti Laanmaa ja Tiit Rammul rühmitusest MUKI, teise preemia Caro Bärtling ja Piret Valk. Aukülaliseks inglise ehtekunstnik Wendy Ramshaw oma ehtesarjaga "Picasso's Ladies". Näituse kujundas 3+1 Arhitektid

  18. Eesti film - needusega? / Margot Visnap

    Index Scriptorium Estoniae

    Visnap, Margot, 1959-

    2006-01-01

    Mängufilm "Libahundi needus" : stsenaristid Margus Kasterpalu, Ilmar Raag ja Rainer Sarnet : režissöör Rainer Sarnet : osades Katariina Lauk, Rene Reinumägi, Raine Loo, Kersti Kreismann, Marje Metsur, Tiit Lilleorg : Shop of Dreams - Eesti Televisioon 2005

  19. Uuendusi vangistusest tingimisi ennetähtaegsel vabastamisel / Anne Rannaveski-Poola, Anne Kruusement ; kommenteerinud Kadri Kelder, ... [jt.

    Index Scriptorium Estoniae

    Rannaveski-Poola, Anne

    2007-01-01

    Alates 1. jaan. 2007 hakatakse ennetähtaegselt vanglast vabastamisel kasutama elektroonilist valvet. Lisatud: mida toovad muudatused kinnipeetavate ennetähtaegsel vabastamisel kaasa kriminaalhooldajale? Küsimusele vastavad Tartu Maakohtu kriminaalhooldusosakonna juhataja Kadri Kelder, Harju Maakohtu kriminaalhooldusosakonna juhataja Kersti Kask, käitumiskontrolli II talituse juhataja Livia Silvet ja Viru Maakohtu kriminaalhooldusosakonna kriminaahooldusametnikud Gaidi Kasu ja Anton Gontsharov

  20. Pargikultuurist Eestis, Versailles', Peterhofi ja Pekingi vahel / Jüri Kuuskemaa

    Index Scriptorium Estoniae

    Kuuskemaa, Jüri, 1942-

    2000-01-01

    Eesti mõisaparkidest (Laiuse, Vääna, Sangaste, Palmse), eesti ajaloolisest pargikunstist, Riia linnaaedniku Georg Kuphaldti tegevusest Toila-Oru, Õisu ja Kadrioru pargis, Kadrioru pargi ajaloost ja taastamisest pargiarhitekt Kersti Lootuse projekti järgi

  1. Ela ja sära - setu pitsist ekvaatorireisini / Andres Keil

    Index Scriptorium Estoniae

    Keil, Andres, 1974-

    2004-01-01

    Eesti Kultuurkapitali "Ela ja sära" stipendiumi laureaadid kirjanik Eeva Park, kunstnik Kai Kaljo, sporditeadlane Joe Noormets, näitleja Kersti Kreismann, pitsikunstnik Ulve Kangro, režissöör Marko Raat, disainer Tarmo Luisk ja helilooja Urmas Sisask oma loomingulistest plaanidest

  2. Ametlik: Trump on Eesti pingutusi märganud

    Index Scriptorium Estoniae

    2017-01-01

    Ameerika Ühendriikide president Donald Trump saatis riigipeale Kersti Kaljulaidile Eesti iseseisvuse 99. sünnipäeva puhul õnnitluskirja, milles nimetas Eestit heaks liitlaseks ja sõbraks. USA president peab oluliseks, et Eesti kulutab 2 protsenti SKTst riigikaitsele ja on seega NATO-le väärtuslik liitlane

  3. Goskontrol : võplatõ za zagrjaznenije ne pobuzhdajut predprijatija sokratit võbrossõ / Külli Kriis

    Index Scriptorium Estoniae

    Kriis, Külli, 1961-

    2008-01-01

    Riigikontrolli hinnangul ei ole saastetasud üldjuhul välisõhu saastamist ja jäätmete tekitamist vähendanud, kuna oluliselt odavam on saastamine kinni maksta kui keskkonnasõbralikku tehnoloogiasse investeerida. Kommenteerivad ASi VKG tehnikadirektor Meelis Eldermann ja OÜ Kiviõli Keemiatööstus keskkonnakaitse peaspetsialist Kersti Salulaid

  4. Jaan Poska maja rekonstrueerimine = Renovation of Jaan Poska's House / Margit Mutso

    Index Scriptorium Estoniae

    Mutso, Margit, 1966-

    2009-01-01

    Tallinnas J. Poska 8 asuv hoone võeti kasutusele Tallinna linnavalitsuse residentsina, veranda osa Jaan Poska muuseumina. Muinsuskaitse eritingimused koostasid Robert Nerman ja Andres Sildre, arhitekt Illar Kannelmäe, sisearhitektid Maile Grünberg ja Eliina Grünberg, maastikuarhitekt Kersti Lootus. Žürii hinnang kultuurkapitali aastapreemiale esitatud hoonele

  5. Süütust näpates

    Index Scriptorium Estoniae

    2007-01-01

    Tanel Veenre fotoseeria teatrikostüümidest Draamateatri laval. Stilist: Hanna Tiidus. Naine: Merle Palmiste. Poiss: Joonas (MJ-Models). Jumestus: Margit Soosaar. Juuksed: Jelena Radtsenkova. Kostüümid etendustest "Rohuvoodi" (Aime Unt), "Rehepapp", "Tõeline inspektor koer" (Ene-Liis Semper), "Liilia" (Lilja Blumenfeld), "Mort" (Kersti Varrak), "Potilaadale" (Reet Aus), "Amadeus" (Krista Tool)

  6. Glotok svezhego vozduhha / Andrei Babin

    Index Scriptorium Estoniae

    Babin, Andrei

    2002-01-01

    Rjazanis 22.-31. maini toimunud festivalil "Zolotoi Vitjaz" said eesti filmitegijad kaks eriauhinda : Inglismaal elav Kersti Uibo filmi "Kitsas on värav" eest ja Andrei Tantsõrev filmi "Lend kanepipõllu kohal" eest. A. Tantsõrev filmifestivalil nähtust

  7. [Communication in the early modern Baltic Sea region = Kommunikatsioon varauusaegses Läänemereruumis] / Ulrike Plath

    Index Scriptorium Estoniae

    Plath, Ulrike, 1972-

    2011-01-01

    Arvustus: Communication in the early modern Baltic Sea region = Kommunikatsioon varauusaegses Läänemereruumis. Hrsg. von Enn Küng, Mati Laur, Kersti Lust. Ajalooline Ajakiri. The Estonian Historical Journal 2009. Nr. 3/4 (129/130). (Tartu 2010)

  8. TÜ nõukogu nimetas neli uut professorit ja emeriitdotsendi

    Index Scriptorium Estoniae

    2012-01-01

    TÜ nõukogu valis 2011.a. detsembri istugil professoriteks Helle Karro (sünnitusabi ja günekoloogia alal), Jaak Vilo (bioinformaatika alal), Varmo Vene (programmeerimiskeelte semantika alal), Marlon Dumas (tarkvaratehnika alal) ja emeriitdotsendiks majandusõppejõud Kersti Meiesaar

  9. Kas võidab teater või sihikindel needus ? / Matis Song

    Index Scriptorium Estoniae

    Song, Matis, 1978-

    2006-01-01

    Mängufilm "Libahundi needus" : stsenaristid Margus Kasterpalu, Ilmar Raag ja Rainer Sarnet : režissöör Rainer Sarnet : osades Katariina Lauk, Rene Reinumägi, Raine Loo, Kersti Kreismann, Marje Metsur, Tiit Lilleorg : Shop of Dreams - Eesti Televisioon 2005

  10. Parimad Eesti modellid / Mari-Liis Helvik

    Index Scriptorium Estoniae

    Helvik, Mari-Liis

    2008-01-01

    Kersti Pedanik, Martin Merimaa agentuurist Living Models Agency; Olga Serova, Anett Griffel agentuurist EMA Model Management; Triin Villemsaar, Kertu-Maria Nurk agentuurist Beatrice MASS Modelnet; Karmen Pedaru, Carolina Bergstein agentuurist MJ-Models. Kommenteerivad Evelyn Mikomägi, Katrin Rannaväli, Beatrice, Margit Jõgger

  11. Adamson-Eric 100 : XX sajandi kunsti- ja kultuurilugu ühe inimsaatuse kaudu / Ülle Kruus

    Index Scriptorium Estoniae

    Kruus, Ülle

    2002-01-01

    Näitus "Adamson-Eric 100" Eesti Kunstimuuseumi Rüütelkonna hoones ja Adamson-Ericu muuseumis. Koostajad Ülle Kruus, Kersti Koll, Hanno Soans, kujundajad Leonhard Lapin (EKM), Jaak Soans (Adamson-Ericu muuseum). Adamson-Ericu teosed väljaspool Eestit ja Eestisse tagasi jõudnud tööd

  12. Eesti Maaülikooli uus üliõpilasesindus astus ametisse / Silver Kuusik

    Index Scriptorium Estoniae

    Kuusik, Silver

    2008-01-01

    Maaülikooli üliõpilasesinduse üldistest ja konkreetsetest eesmärkidest. Küsimusele, mida vast valitud esinduse liikmed kooli heaks teha saavad, vastasid Kersti Pärtelpoeg, Veikko Kiis, Anni Haavakats, Julia Koltsova, Maarja Sõrmus, Rainer Zirnask, Gerlin Järvela, Iiris Rausk, Marili Köster, Christina Birnbaum ja Siim Lokko

  13. Kriminaalne Hiinamaa / Mart Juur

    Index Scriptorium Estoniae

    Juur, Mart, 1964-

    2006-01-01

    Arvustus: Gulik, Robert van. Hiina järvemõrvad : kohtunik Di lahendab kolm juhtumit : [romaan] / inglise keelest tõlkinud Kersti Unt ; illustreeritud kaheteistkümne hiinapärase graafilise lehega autorilt. [Tallinn] : Tänapäev, 2006. (Kohtunik Di mõrvamüsteerium)

  14. Kired ja mõrvad Vana-Hiina moodi / Ave Randviir

    Index Scriptorium Estoniae

    Randviir, Ave, 1981-

    2006-01-01

    Arvustus: Gulik, Robert van. Hiina järvemõrvad : kohtunik Di lahendab kolm juhtumit : [romaan] / inglise keelest tõlkinud Kersti Unt ; illustreeritud kaheteistkümne hiinapärase graafilise lehega autorilt. [Tallinn] : Tänapäev, 2006. (Kohtunik Di mõrvamüsteerium)

  15. Ärimehed tõid kuu ja päikese Narva-Jõesuusse

    Index Scriptorium Estoniae

    2009-01-01

    2008. a. avatud Meresuu spaa-hotellist, mis ehitati nõukogudeaegse lõpetamata rajatise peale. Arhitektuurse lahenduse autor Andres Põime ja sisekujunduse autor Reet Põime arhitektuuribüroost Studio 3. Wellness-korruse sisekujundaja Liisi Murula. Purskkaevud-lillepeenrad kavandas Kersti Lootus. Omanikud: Aare Kööp, Rene Kuulmann

  16. Neli kulda juunioride MM-ilt. Mis saab edasi? / Märt Roosna

    Index Scriptorium Estoniae

    Roosna, Märt

    2006-01-01

    Juunioride kergejõustiku MM-il Pekingis võitsid eestlased neli kuldmedalit: Kaire Leibak kolmikhüppes, Marek Niit 200 m jooksus, Margus Hunt kuulitõukes ja kettaheites. Lisaks vestlus Kaire Leibaku treeneri Kersti Viruga, Marek Niiduga ja Margus Hundiga

  17. Format zhurnalnogo lista

    Index Scriptorium Estoniae

    2003-01-01

    Vene Kunstnike Ühenduse korraldatud näitusest Vene Draamateatri galeriis: osaleb 24 kunstnikku 2-3 tööga omal valikul. Ühenduse tuumikuna mainitakse kunstnikke Valeri Laur, Slava Semerikov, Anatoli Strahhov, Vladimir Baciu, Vera ja Vladislav Stanishevskid, uustulnukana - eesti keraamikut Kersti Karu. Sveta Aleksejeva on illustreerinud ühe viiest 2002.aasta kaunimast lasteraamatust

  18. Kolmest Tallinna Ülikooli Humboldti stipendiaadist / Tiina Tamkivi

    Index Scriptorium Estoniae

    Tamkivi, Tiina

    2014-01-01

    Tallinna Ülikooli külastas jaanuaris teadlasi toetava fondi Alexander von Humboldt Stiftung president ja Berliini Tehnikaülikooli keemiaprofessor Helmut Schwarz. Tallinna Ülikoolist on Humboldti stipendiumi pälvinud kolm teadlast - professor Peeter Järvelaid, ajaloolane Juhan Kreem ja kunstiajaloolane Kersti Markus, kes lisavad artiklis ka omapoolsed selgitused

  19. The Estonian president: the Baltics are not afraid of migrants or Russians / Sten Hankewitz

    Index Scriptorium Estoniae

    Hankewitz, Sten A., 1979-

    2016-01-01

    President Kersti Kaljulaidi avalikust vastusest EurActivis ilmunud James Crispi artiklile "The Brief: Europe’s elites rush to hide behind Mutti’s skirts" http://www.euractiv.com/section/all/news/the-brief-europes-elites-rush-to-hide-behind-muttis-skirts/

  20. Trumpi sõnul on Eesti väärtuslik liitlane ja sõber

    Index Scriptorium Estoniae

    2017-01-01

    Ameerika Ühendriikide president Donald Trump saatis riigipeale Kersti Kaljulaidile Eesti iseseisvuse 99. sünnipäeva puhul õnnitluskirja, milles nimetas Eestit väärtuslikuks liitlaseks ja sõbraks. USA president nimetab Eestit NATO liitlase musternäidiseks, sest Eesti kulutab kaks protsenti SKTst riigikaitsele ja osaleb NATO sõjalistel välismissioonidel

  1. Ühest sotsiaalutoopilisest eksperimendist Vene impeeriumi linnades 19. sajandi esimesel poolel = About a Social-Utopian Experiment in the Cities of the Russian Empire in the First Half of the 19th Century / Epi Tohvri ; tõlk. Kersti Meinart

    Index Scriptorium Estoniae

    Tohvri, Epi

    2003-01-01

    1809. a. Vene impeeriumi linnades kehtestatud tüüpfassaadide kohustusest eraehitusele, millist sõnumit kandsid 1809.-1812. a. tüüpfassaadid tolleaegses elukeskkonnas. Jaotused: Valgustusideed ja arhitektuur. C.-N. Ledoux laadis sotsiaalutoopia teostumine Vene impeeriumis. Klassitsistliku ehituskunsti suundumused Eesti linnades Tartu ehitiste näidete varal. Sisaldab bibliogr. 17 ill

  2. Development and trial application of risk information

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    JNES has been doing various activities to stimulate the introduction of Risk Informed Regulation (RIR) to the safety regulation of nuclear power plants (NPPs) in Japan. Some applications are already incorporated, such as the regulatory review of Maintenance Programs and Safety Significance Evaluation for Inspection Findings. In consideration with the experience of the accident in Fukushima Daiichi Nuclear Power Station, JNES addressed development of regulatory guidelines, evaluation of the current condition of Fukushima Daiichi Nuclear Power Station, evaluation of effectiveness of severe accident management measures with the backgrounds of insights and experiences on probabilistic risk assessment (PRA) and RIR. Especially, the experiences were applied to the development of the methodologies for evaluation of effectiveness of severe accident managements. As for inspection and operation of NPPs, JNES enhanced the PRA scope applied to the importance analysis for Maintenance Program, SDP and RI-ISI in consideration with the insights of RIR in Japan and other countries. (author)

  3. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear Regulation Authority (NRA: which controls the regulations for Spent Fuel Interim Storage Facilities). In 2012 fiscal year, JNES carried out dynamic test of spent fuel to examine the integrity of spent fuel under cask drop accidents, and preparation for PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. Some of these tests will be also carried out in 2013 fiscal year and after. (author)

  4. Study of dose evaluation method

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    In 2012 fiscal year, JNES participated in the working team for the new regulatory standards of the nuclear power plant by the Nuclear Regulation Authority, and discussed the basic requirements and details of the requirements in new regulatory standards (design basis event and severe accident). (author)

  5. Validation study of core analysis methods for full MOX BWR

    International Nuclear Information System (INIS)

    2013-01-01

    JNES has been developing a technical database used in reviewing validation of core analysis methods of LWRs in the coming occasions: (1) confirming the core safety parameters of the initial core (one-third MOX core) through a full MOX core in Oma Nuclear Power Plant, which is under the construction, (2) licensing high-burnup MOX cores in the future and (3) reviewing topical reports on core analysis codes for safety design and evaluation. Based on the technical database, JNES will issue a guide of reviewing the core analysis methods used for safety design and evaluation of LWRs. The database will be also used for validation and improving of core analysis codes developed by JNES. JNES has progressed with the projects: (1) improving a Doppler reactivity analysis model in a Monte Carlo calculation code MVP, (2) sensitivity study of nuclear cross section date on reactivity calculation of experimental cores composed of UO 2 and MOX fuel rods, (3) analysis of isotopic composition data for UO 2 and MOX fuels and (4) the guide of reviewing the core analysis codes and others. (author)

  6. Investigation of evaluation method for marine radiological impact during an accident

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    In 2012, JNES carried out to investigate the measurement information of radionuclide released to the ocean at Fukushima Daiichi NPP accident, the foreign regulation for marine radiological impact, and the evaluation method for release and diffusion to the ocean at the accident inside and outside Japan. (author)

  7. Validation study of core analysis methods for full MOX BWR

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    JNES has been developing a technical database used in reviewing validation of core analysis methods of LWRs in the coming occasions: (1) confirming the core safety parameters of the initial core (one-third MOX core) through a full MOX core in Oma Nuclear Power Plant, which is under the construction, (2) licensing high-burnup MOX cores in the future and (3) reviewing topical reports on core analysis codes for safety design and evaluation. Based on the technical database, JNES will issue a guide of reviewing the core analysis methods used for safety design and evaluation of LWRs. The database will be also used for validation and improving of core analysis codes developed by JNES. JNES has progressed with the projects: (1) improving a Doppler reactivity analysis model in a Monte Carlo calculation code MVP, (2) sensitivity study of nuclear cross section date on reactivity calculation of experimental cores composed of UO{sub 2} and MOX fuel rods, (3) analysis of isotopic composition data for UO{sub 2} and MOX fuels and (4) the guide of reviewing the core analysis codes and others. (author)

  8. Safety evaluation for the prototype Fast Breeder Reactor MONJU as a Japanese TSO

    International Nuclear Information System (INIS)

    Endo, Hiroshi

    2010-01-01

    In the safety field of fast breeder reactors (FBRs), JNES is conducting an evaluation work of the safety regulation by Nuclear and Industry Safety Agency (NISA) for the re-start of a prototype FBR MONJU. MONJU has been stopped over 14 years since 1995 due to a sodium leakage accident at a secondary heat transport system, and is now reached to the criticality on 8th of May, 2010. JNES is supporting the safety regulation work conducted by NISA based on the following activities: i) Support of the technical evaluation of the application for the establishment license prepared by Japan Atomic Energy Agency (JAEA), ii) Support of the description of the safety review report by NISA based on independent safety analyses for the major accident events such as unprotected loss-of-flow (ULOF) by employing the latest findings on the study of core disruptive accidents (CDAs) independently conducted by JNES, iii) Support of the risk-informed-regulation (RIR) such as an accident management (AM) review, iv), and Consideration on the safety regulation policy from the points of severe accidents and source-term behaviors including the cesium (Cs). The objective of this paper is to introduce the major activities of JNES in the safety domain of MONJU regulations. (author)

  9. Annual safety research report, JFY 2010

    International Nuclear Information System (INIS)

    2011-09-01

    In the safety infrastructure research working group report, 'the effective conducting of nuclear safety infrastructure research', published by METI in March 2010, the roles of regulatory agencies and JNES and their cooperation, and the research road map for nuclear safety regulation researches were summarized. As for the regulatory issues the governments or JNES considered necessary, JNES had compiled' safety research plan' in respective research areas necessary for solving the regulatory issues (safety research needs) and was conducting safety research to obtain the results, etc. Safety research areas, subjects and research projects were as follows: design review of nuclear power plant (4 subjects and each subject having several research projects totaled 19), control management of nuclear power plant (3 subjects and each subject having several research projects totaled 11), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 5), nuclear fuel cycle backend (2 subjects and each subject having several research projects totaled 6), nuclear emergency preparedness and response (3 subjects and each subject having several research projects totaled 5) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 7). In JFY 2010, JNES worked on the 53 research projects of 17 subjects in 6 areas as safety researches. This annual safety research report summarized respective achievements and stage of regulatory tools necessary for solving regulatory issues according to the safety research plan, JFY 2010 Edition as well as the situation of the reflection for the safety regulations. (T. Tanaka)

  10. 77 FR 58420 - Advisory Committee On Reactor Safeguards; Notice of Meeting

    Science.gov (United States)

    2012-09-20

    ... Pike, Rockville, Maryland. Thursday, October 4, 2012, Conference Room T2-B1, 11545 Rockville Pike....: Safety Evaluation Report (SER) Associated with WCAP-16793-NP, Revision 2, ``Evaluation of Long-Term..., ``Evaluation of JNES Equipment Fragility Tests for Use in Seismic Probabilistic Risk Assessments for U.S...

  11. 77 FR 51580 - Advisory Committee on Reactor Safeguards; Notice of Meeting

    Science.gov (United States)

    2012-08-24

    ... Pike, Rockville, Maryland. Thursday, September 6, 2012, Conference Room T2-B1, 11545 Rockville Pike... p.m.-3:15 p.m.: Selected Chapters of the Safety Evaluation Reports (SERs) with Open Items Associated... and Peach Bottom,'' and (2) NUREG/CR-7040, ``Evaluation of JNES Equipment Fragility Tests for Use in...

  12. Eesti disain / Silvia Pärmann

    Index Scriptorium Estoniae

    Pärmann, Silvia

    2014-01-01

    Ahti Grünbergi ja Tõnis Kalve mööbliseeria Derelict. Maile Grünbergi disainitud toolid ja laud Madis. Taniel Kolpakovi kaubamärgile Rough Bloom disainitud köögimööbel. Kaubamärgi Varm Country uus kollektsioon Basic no 2. Kersti Laanmaa keraamilised teekannud Kiviaeg ja Jänes kapsas. Tiina Mangi kavandatud diivan Sik-Sak. Tõnis Vellama valgustimudel AET27

  13. Uus esinduskodu : Poska maja Kadriorus = A New Reception Home - Poska House, Kadriorg / Triin Ojari

    Index Scriptorium Estoniae

    Ojari, Triin, 1974-

    2008-01-01

    Tallinnas J. Poska t. 8 auva Jaan Poska maja (arhitekt Nikolai Thamm vanem, 1875) taastamine. Projekteerija: OÜ Heino Uuetalu. Arhitekt Illar Kannelmäe. Sisekujundus: Maile Grünberg (linnavalitsuse residents), Anne Tamverk (Poska muuseum). Haljastus: Kersti Lootus. Ehitaja: Tarrest Ehitus OÜ. Projekt: 2005-2007, valmis: 2007. I korruse plaan, 2 värv. välis- ja 4 sisevaadet. Bibliograafia lk. 66

  14. 2. XII möödus 20 aastat Adamson-Ericu muuseumi avamisest Eesti Kunstimuuseumi filiaalina ning 35 aastat Adamson-Ericu (1902-1968) surmast

    Index Scriptorium Estoniae

    2003-01-01

    Muuseumi ajaloost, põhikogust, Adamson-Ericu teoste põhiekspositsioonist, kunstinäitustest. 3. XII tutvustab Kersti Koll Adamson-Ericu ja läti kunstniku Ludolfs Libertsi näitust. 5. XII ekspositsioonis ringkäik "Meistri töövõtetest ning erinevatest materjalidest restauraatori pilgu läbi" Alar Nurkse juhtimisel, ekskursioon Ülle Kruusi juhtimisel. 10. XII algab projekti "Avatud muuseum" raames haridusprogramm "Noor kunstidetektiiv"

  15. Mõtteid Eesti Kultuurkapitali arhitektuuripreemiatest = Thoughts about the Cultural Endowment of Estonia's prizes for architecture / Epp Lankots

    Index Scriptorium Estoniae

    Lankots, Epp, 1976-

    2012-01-01

    Arhitektuuriaastast 2011. Eesti Kultuurkapitali aastapreemia - Juta Lember (Peterburi Jaani kirik). Arhitektuuri sihtkapitali maastikuarhitektuuri preemia - Kersti Lootus, Kiur Lootus, Siim Lootus, Katri Soonberg, Heidi Viilop (Pärnu Vallikääru park), restaureerimispreemia - Nele Rohtla (Kiltsi mõis), arhitektuuripreemia - Maarja Kask, Ralf Lõoke, Karli Luik, Ene-Liis Semper, Pelle-Sten Viiburg (NO99 Põhuteater), tegevuspreemia - Margit Argus, Margit Aule, Maarin Ektermann, Ingrid Ruudi (festivali "LIFT11" kuraatorid)

  16. Eesti Rahva Muuseumis avati võimatud ruumid / Keiu Virro

    Index Scriptorium Estoniae

    Virro, Keiu, 1987-

    2017-01-01

    Lavastuskunstnike näitus "1:10 / võimatud ruumid" ERMis 5.-30. septembrini. Fotodel Kersti Prosa "Sada aastat üksildust / Hundred Years of Solitude", Marge Martini "Raamatud lünkadest / The books of blanks", Mare Raidma "Ruum meie kätes / Space in our hands", Inga Varese "Ta istub su laua taga ja ootab / They sit behind Your table and wait", Tuulikki Tolli "88 ruumi / 88 rooms", Rosita Raua "Tempus non fugit"

  17. 27. ja 28. IX toimus Narvas VII Eesti muuseumide näituste festival ja seminar

    Index Scriptorium Estoniae

    2004-01-01

    I koha pälvis ERMi ja Adamson-Ericu muuseumi koostööprojekt "Viinapuuväät. Maasikakiri II" (kontseptsiooni ja haridusprogrammi autorid Vaike Reemann, Ülle Kruus, Kersti Koll ja Kai Tuvik, kujundaja Denes Farkas, monteerija Vahur Puik), II - Tartu Kunstimuuseumi näitus "Muuseum muuseumis" (kontseptsiooni autorid ja teostajad Ahti Seppet, Hannes Varblane), III - Viljandi muuseumi näitus "Rõõmud lumel ja jääl" (idee autor Herki Helves)

  18. Arhitektuuriaasta 2007 = The year 2007 in architecture / Liina Jänes

    Index Scriptorium Estoniae

    Jänes, Liina, 1977-

    2008-01-01

    Eesti Kultuurkapitali 2007. a. arhitektuuri valdkonna peapreemia pälvis Vello Asi. Arhitektuuri sihtkapital: tegevuspremia - Kalle Komissarov, arhitektuuripreemia - Kalle Vellevoog (pansionaat Pärnus Seedri t. 4), arhitektuuri- ja sisearhitektuuri preemia - Lembit-Kaur Stöör, Tõnis Kimmel, Raili Paling ja Liis Lindvere (Tallinna sünagoog), restaureerimispreemia - Aivar Roosaar (Tartu Athena kino ja konverentsikeskus), uurimistöö preemia - Silja Konsa, Urve Sinijärv, Olev Abner, Kersti Lootus, Ants Hein (teatmeteos "Eesti pargid. 1")

  19. Lakewoodi Eesti Majas New Jersey osariigis... / Enn Lillemets

    Index Scriptorium Estoniae

    Lillemets, Enn

    2004-01-01

    9. X tuletati meelde eesti graafikut ja maalijat Eduard Rüga (1903-1997), kelle loomingust oli välja pandud näitus Ameerika erakogudest. Õhtust võtsid osa E. Rüga abikaasa Leida Rüga, tütred Silja Melts ja Kersti Raimondo. Enn Lillemetsa ettekandest. Vaadati Andres Söödi telefilmi "Eduard Rüga" (1993)

  20. Triennaalist ja preemiatest : tarbekunst / Lesley Jackson ; tõlk. Kai Lobjakas

    Index Scriptorium Estoniae

    Jackson, Lesley

    2006-01-01

    Inglise disainiajaloolane, auhinnažürii liige Eesti Tarbekunsti- ja Disainimuuseumis avatud IV Tallinna rakenduskunsti triennaalist "Kaks lähedast" ja preemia saanud töödest. Näituse kujundus: 3+1 Arhitektid. I preemia: Kersti Laanmaa ja Tiit Rammuli (rühmitus Muki) töö "Loomaarmastus", kaks teist preemiat: Piret Valk "Maa vägi", Caro Bärtling "Salvrätt-kraed"

  1. Annual safety research report, JFY 2012

    International Nuclear Information System (INIS)

    2013-08-01

    As for the regulatory issues the governments or JNES considered necessary, JNES had compiled 'safety research plan' in respective research areas necessary for solving the regulatory issues (safety research needs) and was conducting safety research to obtain the results, etc. Safety research areas, subjects and research projects were as follows: design review of nuclear power plant (5 subjects and each subject having several research projects totaled 20), control management of nuclear power plant (3 subjects and each subject having several research projects totaled 6), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 4), nuclear fuel cycle backend (2 subjects and each subject having several research projects totaled 6), nuclear emergency preparedness and response (3 subjects and each subject having several research projects totaled 7) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 6). In addition to these 49 research projects of 18 subjects in 6 areas, JNES worked on 19 research projects of 7 subjects in added areas (specific research projects on of the disaster at Fukushima Daiichi NPP accident and other challenges JNES considered necessary) in JFY 2012. This annual safety research report summarized respective achievements and state of regulatory tools necessary for solving regulatory issues according to the safety research plan, JFY 2012 Edition as well as the situation of the reflection for the safety regulations, and also described 16 research projects of 4 subjects: examination for new safety regulation (8 research projects), development of newly necessary evaluation methods (one research project), evaluation of the validity for the work for convergence at Fukushima Daiichi NPP accident (4 research project) and horizontal development to other nuclear power plants (3 research projects), and 3 research projects of 3 subjects as other challenges. A list of JNES

  2. Project of integrity assessment of flawed components with structural discontinuity (IAF). Data book for residual stress analysis in weld joint. Analysis model of dissimilar metal weld joint applied post weld heat treatment (PWHT)

    International Nuclear Information System (INIS)

    2012-12-01

    The project of Integrity Assessment of Flawed Components with Structural Discontinuity (IAF) was entrusted to Japan Power Engineering and Inspection Corporation (JAPEIC) from Nuclear and Industrial Safety Agency (NISA) and started from FY 2001. And then, it was taken over to Japan Nuclear Energy Safety Organization (JNES) which was established in October 2003 and carried out until FY 2007. In the IAF project, weld joints between nickel based alloys and low alloy steels around penetrations in reactor vessel, safe-end of nozzles and shroud supports were selected from among components and pipe arrangements in nuclear power plants, where high residual stresses were generated due to welding and complex structure. Residual stresses around of the weld joints were estimated by finite element analysis method (FEM) with a general modeling method, then the reasonability and the conservativeness was evaluated. In addition, for postulated surface crack of stress corrosion cracking (SCC), a simple calculation method of stress intensity factor (K) required to estimate the crack growth was proposed and the effectiveness was confirmed. JNES compiled results of the IAF project into Data Books of Residual Stress Analysis of Weld Joint, and Data Book of Simplified Stress Intensity Factor Calculation for Penetration of Reactor as typical Structure Discontinuity, respectively. Data Books of Residual Stress Analysis in Weld Joint. 1. Butt Weld Joint of Small Diameter Cylinder (4B Sch40) (JNES-RE-2012-0005), 2. Dissimilar Metal Weld Joint in Safe End (One-Side Groove Joint (JNES-RE-2012-0006), 3. Dissimilar Metal Weld Joint in Safe End (Large Diameter Both-Side Groove Joint) (JNES-RE-2012-0007), 4. Weld Joint around Penetrations in Reactor Vessel (Insert Joint) (JNES-RE-2012-0008), 5. Weld Joint in Shroud Support (H8, H9, H10 and H11 Welds) (JNES-RE-2012-0009), 6. Analysis Model of Dissimilar Metal Weld Joint Applied Post Weld Heat Treatment (PWHT) (JNES-RE-2012-0010). Data Book of

  3. Project of integrity assessment of flawed components with structural discontinuity (IAF). Data book for estimation stress intensity factor. Surface crack on ICM housing for penetration in reactor vessel

    International Nuclear Information System (INIS)

    2012-12-01

    The project of Integrity Assessment of Flawed Components with Structural Discontinuity (IAF) was entrusted to Japan Power Engineering and Inspection Corporation (JAPEIC) from Nuclear and Industrial Safety Agency (NISA) and started from FY 2001. And then, it was taken over to Japan Nuclear Energy Safety Organization (JNES) which was established in October 2003 and carried out until FY 2007. In the IAF project, weld joints between nickel based alloys and low alloy steels around penetrations in reactor vessel, safe-end of nozzles and shroud supports were selected from among components and pipe arrangements in nuclear power plants, where high residual stresses were generated due to welding and complex structure. Residual stresses around of the weld joints were estimated by finite element analysis method (FEM) with a general modeling method, then the reasonability and the conservativeness was evaluated. In addition, for postulated surface crack of stress corrosion cracking (SCC), a simple calculation method of stress intensity factor (K) required to estimate the crack growth was proposed and the effectiveness was confirmed. JNES compiled results of the IAF project into Data Books of Residual Stress Analysis of Weld Joint, and Data Book of Simplified Stress Intensity Factor Calculation for Penetration of Reactor as typical Structure Discontinuity, respectively. Data Books of Residual Stress Analysis in Weld Joint. 1. Butt Weld Joint of Small Diameter Cylinder (4B Sch40) (JNES-RE-2012-0005), 2. Dissimilar Metal Weld Joint in Safe End (One-Side Groove Joint (JNES-RE-2012-0006), 3. Dissimilar Metal Weld Joint in Safe End (Large Diameter Both-Side Groove Joint) (JNES-RE-2012-0007), 4. Weld Joint around Penetrations in Reactor Vessel (Insert Joint) (JNES-RE-2012-0008), 5. Weld Joint in Shroud Support (H8, H9, H10 and H11 Welds) (JNES-RE-2012-0009), 6. Analysis Model of Dissimilar Metal Weld Joint Applied Post Weld Heat Treatment (PWHT) (JNES-RE-2012-0010). Data Book of

  4. Investigation of exposure dose of residents and standards for the interim storage of wastes from the restricted area

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Remediation in the restricted area around the Fukushima Daiichi Nuclear Power Plant is being planned. JNES conducted the investigation to support controlling the exposure pathway for exposure of residents. Prototype dose evaluation tool for the residents in the restricted area was developed. Residents would be externally and internally exposed. Monitoring data of concentration of radioactive material in the air, soil, water, agricultural products and fish, and exposure scenario were compiled to be used in the dose evaluation tool. Upon requests from the Local Nuclear Emergency Response Headquarters (LNERH), JNES has conducted investigations of the exposure dose for local residents, car mechanics, drivers, fire fighters, workers of incineration plant, seawage plant and final disposal of waste in their activities. Preliminary investigation of the safety of interim storage for wastes from decontamination was also conducted. (author)

  5. Construction of System for Seismic Observation in Deep Borehole (SODB) - Overview and Achievement Status of the Project

    International Nuclear Information System (INIS)

    Kobayashi, Genyu

    2014-01-01

    The seismic responses of each unit at the Kashiwazaki-Kariwa NPP differed greatly during the 2007 Niigata-ken Chuetsu-oki Earthquake; the deep sedimentary structure around the site greatly affected these differences. To clarify underground structure and to evaluate ground motion amplification and attenuation effects more accurately in accordance with deep sedimentary structure, JNES initiated the SODB project. Deployment of a vertical seismometer array in a 3000-meter deep borehole was completed in June 2012 on the premises of NIIT. Horizontal arrays were also placed on the ground surface. Experiences and achievements in the JNES project were introduced, including development of seismic observation technology in deep boreholes, site amplification measurements from logging data, application of borehole observation data to maintenance of nuclear power plant safety, and so on. Afterwards, the relationships of other presentations in this WS, were explained. (authors)

  6. External exposure dose of car mechanics during the maintenance of the cars from the risk cautionary area

    International Nuclear Information System (INIS)

    Kawakami, Hiroto; Yamada, Norikazu; Sasaki, Satoru; Kawasaki, Satoru

    2011-12-01

    At the request of the Local Nuclear Emergency Response Headquarters, JNES has estimated the effective external exposure dose of car mechanics during the maintenance of the cars from the risk cautionary area. JNES investigated the contamination of the cars from the risk cautionary area and of the average cars at Fukushima city cooperated by the Japan Automobile Dealers Association. Data of screed cars by the Local Nuclear Emergency Response Headquarters is also considered in. Effective external exposure dose of car mechanics treating the cars screened with the emergency situation screening level is estimated to be less than 1 mSv/y under the conservative conditions. This result shows that particular health concern isn't necessary for them. (author)

  7. Investigation of evaluation method for marine radiological impact during an accident

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    In 2012, JNES investigated the evaluation method, long-term seawater and marine deposition for release and diffusion to the ocean at the accident, and marine impact assessment code, in Japan and overseas. Also, the foreign regulations for marine radiological impact (direct release to ocean from the facilities and fallout on marine, etc.) were investigated. Furthermore, the index (e.g., intervention level) at emergency control in USA and Europe were investigated. (author)

  8. Investigation of evaluation method for marine radiological impact during an accident

    International Nuclear Information System (INIS)

    2013-01-01

    In 2012, JNES investigated the evaluation method, long-term seawater and marine deposition for release and diffusion to the ocean at the accident, and marine impact assessment code, in Japan and overseas. Also, the foreign regulations for marine radiological impact (direct release to ocean from the facilities and fallout on marine, etc.) were investigated. Furthermore, the index (e.g., intervention level) at emergency control in USA and Europe were investigated. (author)

  9. Development and Examination of Real-time Automatic Scram System Using Deep Vertical Array Seismic Observation System

    International Nuclear Information System (INIS)

    Sugaya, Katsunori

    2014-01-01

    In Japan, observed seismic motions in reactor buildings are currently used for seismic scram, but installing a seismometer at a great depth at the site may possibly shorten scram initiation time. JNES proposed a scram system with a seismometer set at a depth of 3,000 m on the premises of the Niigata Institute of Technology based on preliminary results for a scenario earthquake and is now planning quantitative evaluation. (authors)

  10. ERKÜ valimiste tulemused

    Index Scriptorium Estoniae

    2006-01-01

    8. aprilli koosolekul kinnitas valimiste peakomitee XIX Esinduskogu liikmed: Mati Kõiva, Ylo Anson, Juhan Simonson, Airi Vaga, Gilda M. Karu, Taavo Virkhaus, Marju Rink-Abel, Markus Vaga, Eric Suuberg, Endel Reinpõld, Jaak Juhansoo, Ülle Ederma, Lya Karm, Heino Jõgis, Kersti Linask, Jaak Rakfeldt, Erik Puskar, Jüri Linask, Viiu Vanderer, Andres Kurrik, Mati Valdek Laan, Ilmar Vanderer, Henno Uus, Jüri Tults, Urmas Wompa, Astrid Jaanson, Jüri Virkus, Lilian G. G. Bein, Tiina Harris, Tõnu Vanderer

  11. Pariisi maailmanäitus 1937 : oluline tähis Eesti kultuuriloos / Ants Juske

    Index Scriptorium Estoniae

    Juske, Ants, 1956-2016

    2007-01-01

    Väljapanek "70 aastat Pariisi maailmanäitusest aastal 1937" Adamson-Ericu muuseumis (kuni 7.10.2007) tutvustab Eesti kunstnikkonna II maailmasõja eelset menukat esinemist Pariisis rahvusvahelisel suurüritusel, mille teemaks oli "Kunst ja tehnika moodsas elus". Koostajad Ülle Kruus ja Kersti Koll. Balti riikide ühispaviljoni peaarhitekt oli Aleksander Nürnberg. Eestit esindas maailmanäitusel valdavalt Rakenduskunsti Ühingu liikmete looming, fotokunst ja raamatud ning käsitöö

  12. [Määramised

    Index Scriptorium Estoniae

    2010-01-01

    Ametisse määramised: Kaitseväe peainspektor (alates 18.09.2010) kolonel Jüri Järveläinen ; Meditsiiniteenistuse ülem, kaitseväe peaarst (alates 01.09.2009) kolonelleitnant Kersti Lea ; 1. jalaväebrigaadi staabiülem (alates 18.09.2010) kolonelleitnant Toomas Möls ; Kuperjanovi jalaväepataljoni ülem (alates 01.07.2010) major Maidu Allikas ; Mereväe Miinilaevade Divisjoni ülem (alates 06.08.2010) kaptenmajor Johan-Elias Seljamaa ; Lääne Kaitseringkonna ülem (alates 18.09.2010) major Margus Rebane

  13. Nobelistid : süütuse rebestus ja üllatus / Vaapo Vaher

    Index Scriptorium Estoniae

    Vaher, Vaapo, 1945-

    2008-01-01

    Tutvustatakse 2008. a. eesti keeles ilmunud Nobeli kirjandusauhinna laureaatide jt. teoseid: Faulkner, William. Absalom, Absalom! / tlk. Kersti Unt. Tallinn : Tänapäev, 2008 ; Dostojevski, Fjodor. Alandatud ja solvatud / tlk. Leopold Kenn. Tallinn : Eesti Raamat, 2008 ; Böll, Heinrich. Ametisõidu lõpp / tlk. Mati Sirkel. Tallinn : Varrak, 2008 ; Morrison, Toni. Dzhäss / tlk. Udo Uibo ja Krista Kaer. Tallinn : Varrak, 2008 ; Laxness, Halld̤r. Islandi kell / tlk. Arvo Alas ja Askur Alas. Tallinn : Varrak, 2008 ; Bunin, Ivan. Armastuse grammatika : [novellid] / koost. Rein Põder ; tlk. Jüri Pärni. Tallinn : Eesti Raamat, 2008

  14. Improvement of numerical simulation methods on safety assessment of the spent fuel storage facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Improvement of numerical simulation methods on safety assessment of the spent fuel storage facility is one of main objectives of JNES activities. For the thermal and structural analyses, the radiative heat transfer analysis code S-FOKS has been developed to reduce computing time and to avoid using large memory area. In order to simulate the specular reflection, a new model (called 'model-2') is planned to install to S-FOKS code. The theoretical values with the specular reflection in simple geometry were lead to verify S-FOKS model-2. (author)

  15. Research program on conditions to failure of high burnup fuel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Regarding the power ramp test to verify the out-of-pile test results on hydrogen-induced cladding failure, situation of the shipping port restoration after the earthquake disaster was investigated for the overseas transportation of test fuel rods which had been interrupted. Its reopening schedule was still currently uncertain and the power ramp test plan also remained suspended. The information about the fuel irradiation performance obtained from JNES projects and international projects, etc. is prepared as database, and based on the recent findings, the fuel irradiation performance models and analysis codes are developed and/or improved. (author)

  16. Setting of cesium residual ratio of molten solidified waste produced in Japan Atomic Power Company Tokai and Tokai No.2 Power Stations

    International Nuclear Information System (INIS)

    2013-02-01

    JNES investigated the appropriateness of a view of the Japan Nuclear Fuel Co. on cesium residual content and the radioactivity measurement precision regarding the molten solidified (with lowered inorganic salt used) radioactive wastes which were produced from Japan Atomic Power Company Tokai and Tokai No. 2 Power Stations. Based on the written performance report from the request and past disposal confirmation experience, a view of the JNFC is confirmed as appropriate that setting of 15% cesium residual ratio for molten solidified with volume ratio larger than 4% and less than 10% cases. (S. Ohno)

  17. Experimental investigation on multidisciplinary geophysical characterization of deep underground structure using multi-scale, multi-mode seismic profiling for the evaluation of ground motion and seismic model building

    International Nuclear Information System (INIS)

    Abe, Susumu

    2014-01-01

    Recent advancements in data acquisition and velocity estimation for multi-mode, multiscale seismic exploration were explained along with the basic concept of strategic geophysical surveys for NPP siting assessment. Then, as a case study using this concept, multidisciplinary geophysical characterization results pertaining to the deep underground structure beneath the JNES Kashiwazaki Center were explained in detail. At the site, reflection/refraction surveys and magnetotelluric/gravity surveys were also conducted. It was shown that these surveys can be used complementary because at the upsurge part, where clear images cannot be obtained by reflection/refraction surveys, magnetotelluric /gravity surveys can be used to obtain clear images. (author)

  18. Application of Seismic Observation Data in Borehole for the Development of Attenuation Equation of Response Spectra on Bedrock

    International Nuclear Information System (INIS)

    Si, Hongjun

    2014-01-01

    Ground motion data on seismic bedrock is important, but it is very difficult to obtain such data directly. The data from KiK-net and JNES/SODB is valuable and very useful in developing the attenuation relationship of response spectra on seismic bedrock. NIED has approximately 200 observation points on seismic bedrock with S-wave velocity of more than 2000 m/s in Japan. Using data from observation at these points, a Ground Motion Prediction Equation (GMPE) is under development. (author)

  19. Evaluation of near-surface attenuation of S-waves based on PS logging and vertical array seismic observation

    International Nuclear Information System (INIS)

    Kobayashi, Genyu

    2014-01-01

    As a result of the lessons learned from the experience of Kashiwazaki-Kariwa NPP due to the 2007 Niigata Chuetsu Oki Earthquake, it has become clear that a rational method of near-surface attenuation characteristics covering a depth range from engineering bedrock to seismic bedrock urgently needs to be established. JNES performed PS logging and vertical array seismic ground motion observation at a soil ground site (SODB 1. site), sedimentary rock site, and an igneous rock site (SODB 2. site), and proposed an evaluation method of attenuation characteristics (site characteristics) for the deep underground. (author)

  20. The evaluation outline to 'root cause analysis report (revision) of the event which the penetration hole generated by the main exhaust pipe duct of the reprocessing plant' reported by Japan Atomic Energy Agency

    International Nuclear Information System (INIS)

    2013-06-01

    JNES evaluated the report which JAEA presented in October 2012 at the Nuclear Regulation Authority on the root cause analysis regarding the penetration hole on the main exhaust pipe duct in the JAEA reprocessing plant. The evaluation of the root cause analysis was done based on the guideline of the Regulation Authority evaluating the root cause analysis carried out by the enterprise side and concluded that the evaluation extending as to JAEA's organizational system was effective as a countermeasure for a recurrence, the present report representing the outline of the evaluation. (S. Ohno)

  1. Status of the support researches for the regulation of nuclear facilities decommissioning in Japan

    International Nuclear Information System (INIS)

    Masuda, Yusuke; Iguchi, Yukihiro; Kawasaki, Satoru; Kato, Masami

    2011-01-01

    In Japan, 4 nuclear power stations are under decommissioning and some nuclear fuel cycle facilities are expected to be decommissioned in the future. On the other hand, the safety regulation of decommissioning of nuclear facilities was changed by amending act in 2005. An approval system after review process of decommissioning plan was adopted and applied to the power stations above. In this situation, based on the experiences of the new regulatory system, the system should be well established and moreover, it should be improved and enhanced in the future. Nuclear Industry and Safety Agency (NISA) is in charge of regulation of commercial nuclear facilities in Japan and decommissioning of them is included. Japan Nuclear Energy Safety Organization (JNES) is in charge of technical supports for NISA as a TSO (Technical Support Organization) also in this field. As for decommissioning, based on regulatory needs, JNES has been continuing research activities from October 2003, when JNES has been established. Considering the 'Prioritized Nuclear Safety Research Plan (August 2009)' of the Nuclear Safety Commission of Japan and the situation of operators facilities, 'Regulatory Support Research Plan between FY 2010-2014' was established in November 2009, which shows the present regulatory needs and a research program. This program consists of researches for 1. review process of decommissioning plan of power reactors, 2. review process of decommissioning plan of nuclear fuel cycle facilities, 3. termination of license at the end of decommissioning and 4. management of decommissioning waste. For the item 1, JNES studied safety assessment methods of dismantling, e.g. obtaining data and analysis of behavior of dust diffusion and risk assessment during decommissioning, which are useful findings for the review process. For the item 2, safety requirements for the decommissioning of nuclear fuel cycle facilities was compiled, which will be used in the future review. For the item 3

  2. Avaliku võimu ja kodanikualgatuse partnerlus : koostööd mõjutavad tegurid / Krista Hinno, Tanel Vallimäe

    Index Scriptorium Estoniae

    Hinno, Krista

    2007-01-01

    Artiklis esitatakse kokkuvõte Tallinna Ülikooli Eesti Humanitaarinstituudi Kodanikeühiskonna Uurimis- ja Arenduskeskuse uurimuse "Avaliku võimu ja kodanikualgatuse komplementaarsed suhted" peamistest tulemustest. Raporti autorite hulka kuulusid Erle Rikmann, Krista Hinno, Aigi Bremse, Kersti Kollom, Mari Sepp ja Tanel Vallimäe. Toetudes uuringutele väidavad autorid, et Eesti ametnikkond on soodsalt meelestatud koostööle kodanikuühendustega, takistuseks võivad saada kodanikeühenduste erinev tööstiil, vajalike ressursside puudus, sh ka ajanappus, ametnike kaadrivoolavus ja teatavate vanusegruppide vähene avatus. Diagrammid: Koostöö jaotumine asutuseliikide vahel; Ametnike hinnang ühistegevuse sisukusele seoses koostöö algatamisega; Ametnike hinnang omaduse vajalikkusele oma töös (vastajate osakaal, kes peavad antud omadust oma töös väga vajalikuks)

  3. Accumulation and preparation of nondestructive inspection data for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    In recent years, flaws due to stress corrosion cracking (SCC) in stainless steel piping and nickel based alloy welds were detected at nuclear power plants in Japan. Weld Overlay (WOL) has been developed as a repairing method for piping items without removing flaws. Since the inspection techniques for WOL pipes and nickel based alloy welds are not verified enough in Japan, Japan Nuclear Energy Safety Organization (JNES) has been carrying out a six year research project entitled 'Accumulation and Preparation of Nondestructive Inspection Data for Nuclear Power Plants' regarding nondestructive inspection since FY2007. In this research project, detection and sizing capability of SCC by Ultrasonic Testing (UT) are evaluated using mockup tests. In addition, the results of this project and past nondestructive inspection data performed by JNES projects are gathered, and inputted into the database of NDT information. In FY2012, followings were conducted. 1) Analysis for UT measurement results of nickel based alloy weld simulating safe end of reactor vessel outlet nozzle. 2) Analysis for UT measurement results of cast stainless steel piping. 3) Development of interface of UT simulation. 4) Development of nondestructive testing guideline. (author)

  4. Tsunami deposits

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The NSC (the Nuclear Safety Commission of Japan) demand to survey on tsunami deposits by use of various technical methods (Dec. 2011), because tsunami deposits have useful information on tsunami activity, tsunami source etc. However, there are no guidelines on tsunami deposit survey in JAPAN. In order to prepare the guideline of tsunami deposits survey and evaluation and to develop the method of tsunami source estimation on the basis of tsunami deposits, JNES carried out the following issues; (1) organizing information of paleoseismological record and tsunami deposit by literature research, (2) field survey on tsunami deposit, and (3) designing the analysis code of sediment transport due to tsunami. As to (1), we organize the information gained about tsunami deposits in the database. As to (2), we consolidate methods for surveying and identifying tsunami deposits in the lake based on results of the field survey in Fukui Pref., carried out by JNES. In addition, as to (3), we design the experimental instrument for hydraulic experiment on sediment transport and sedimentation due to tsunamis. These results are reflected in the guideline on the tsunami deposits survey and evaluation. (author)

  5. Study on information dissemination for effective nuclear risk communication

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The aim of this study are to develop an information system and guideline for nuclear risk communication between expert and citizens as well as between both experts in terms of lessons learned from serious disaster such as Fukushima Dai-ich NPP accident. Technical standards for disseminating a result and process of seismic/tsunami PRA (Probabilistic Risk Assessment) of nuclear facility as well as nuclear risk information in an emergency, and risk communication in normal times are needed. Tins study examines the framework, contents, and technical basis for developing an information system for nuclear risk communication. In addition, this study identifies the communication issues of nuclear risk communication concerning the seismic/tsunami PRA through the testing information systems in areas around nuclear facilities and by providing effective implementation guidelines. JNES has developed the information system specified as Protection of Nuclear Power Plants against Tsunamis and Post Earthquake considerations in the External Zone (TiPEEZ) as part of IAEA International Seismic Safety Centre (ISSC) Extra Budgetary Programme (EBP). The EBP is currently preparing technical documents (TECDOC) regarding the implementation of the TiPEEZ. After the Fukushima accident, there has been increasing demand for disaster mitigation systems to share risk information between nuclear organizations and local municipalities. JNES and Niigata Institute of Technology conduct implementation of TiPEEZ for the practical use based on the corroborative works with Kashiwazaki city and citizens. (author)

  6. Consecutive collection of new finding and knowledge on science and technology to be reflected to seismic safety assessment for nuclear facilities

    International Nuclear Information System (INIS)

    Tsutsumi, Hideaki; Iijima, Toru

    2013-05-01

    JNES had been collecting and analyzing new finding and knowledge on science and technology to be reflected to seismic safety assessment for nuclear facilities, which was updated so as to develop a system to organize and disseminate such information in response to Nuclear Regulation Authority (NRA)'s policy on new safety regulations requesting enhanced protective measures against extreme natural hazards. The tasks were as follows; (1) collection of new finding and knowledge from seismic safety research of JNES, (2) constructing database of seismic safety research from documents published by committees and including the Great East Japan Earthquake and (3) dissemination of information related to seismic research. As for JFY 2012 activities, collecting and analyzing new finding and knowledge were on three areas such as active fault, seismic source/ground motion and tsunami. 4 theme related with the Great East Japan Earthquake, 7 items not related with the Great East Japan Earthquake and one item on external event were collected and analyzed whether incorporating in seismic safety research important for regulation to increase seismic safety of nuclear facilities, with no such theme confirmed. (T. Tanaka)

  7. Research items regarding seismic residual risk evaluation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    After learning the Fukushima Dai-ichi NPP severe accidents in 2011, the government investigation committee proposed the effective use of probabilistic safety assessment (PSA), and now it is required to establish new safety rules reflecting the results of probabilistic risk assessment (PRA) and proposed severe accident measures. Since the Seismic Design Guide has been revised on September 19, 2006, JNES has been discussing seismic PRA (Levels 1-3) methods to review licensees' residual risk assessment while preparing seismic PRA models. Meanwhile, new safety standards for light water reactors are to be issued and enforced on July 2013, which require the residual risk of tsunami, in addition to earthquakes, should be lowered as much as possible. The Fukushima accidents raised the problems related to risk assessment, e.g. approaches based on multi-hazard (earthquake and tsunami), multi-unit, multi-site, and equipment's common cause failure. This fiscal year, while performing seismic and/or tsunami PRA to work on these problems, JNES picked up the equipment whose failure greatly contribute to core damage, surveyed accident management measures on those equipment as well as effectiveness to reduce core damage probability. (author)

  8. Development of tsunami hazard analysis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    The NSC (the Nuclear Safety Commission of Japan) demand to survey on tsunami deposits by use of various technical methods (Dec. 2011), because tsunami deposits have useful information on tsunami activity, tsunami source etc. However, there are no guidebooks on tsunami deposit survey in JAPAN. In order to prepare the guidebook of tsunami deposits survey and to develop the method of tsunami source estimation on the basis of tsunami deposits, JNES carried out the following issues; (1) organizing information of paleoseismological record and tsunami deposit by literature research, and (2) field survey on tsunami deposit to prepare the guidebook. As to (1), we especially gear to tsunami deposits distributed in the Pacific coast of Tohoku region, and organize the information gained about tsunami deposits in the database. In addition, as to (2), we consolidate methods for surveying and identifying tsunami deposits in the lake based on results of the field survey in Fukui Pref., carried out by JNES. These results are reflected in the guidebook on the tsunami deposits in the lake as needed. (author)

  9. Study of applicable methods on safety verification of disposal facilities and waste packages

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Three subjects about safety verification on the disposal of low level radioactive waste were investigated in FY. 2012. For radioactive waste disposal facilities, specs and construction techniques of covering with soil to prevent possible destruction caused by natural events (e.g. earthquake) were studied to consider verification methods for those specs. For waste packages subject to near surface pit disposal, settings of scaling factor and average radioactivity concentration (hereafter referred to as ''SF'') on container-filled and solidified waste packages generated from Kashiwazaki Kariwa Nuclear Power Station Unit 1-5, setting of cesium residual ratio of molten solidified waste generated from Tokai and Tokai No.2 Power Stations, etc. were studied. Those results were finalized in consideration of the opinion from advisory panel, and publicly opened as JNES-EV reports. In FY 2012, five JNES reports were published and these have been used as standards of safety verification on waste packages. The verification method of radioactive wastes subject to near-surface trench disposal and intermediate depth disposal were also studied. For radioactive wastes which will be returned from overseas, determination methods of radioactive concentration, heat rate and hydrogen generation rate of CSD-C were established. Determination methods of radioactive concentration and heat rate of CSD-B were also established. These results will be referred to verification manuals. (author)

  10. Study on disaster waste around Fukushima Daiichi NPS

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    Extreme difficulties exists in Fukushima Prefecture in disposing of waste generated from the tsunami disaster (hereinafter referred to as disaster waste) and contaminated with radioactive material released from the crippled Fukushima Daiichi Nuclear Power Station. Although the waste should be treated according to the level of radioactivity, there were only air dose rates and radionuclide analyses of soil due to monitoring around the Fukushima Daiichi Nuclear Power Station and there had been no information on the radioactivity concentration of the disaster waste. The radioactivity concentration of the disaster waste was investigated by sampling measurement and in-situ Ge measurement at 20 temporary disaster waste storages in Fukushima Prefecture excluding the evacuation zone and 'deliberate evacuation zone.' JNES carried out tins investigation upon a request from die Nuclear and Industrial Safety Agency. The investigation revealed that the measured radioactivity concentrations of the disaster waste lumps were enveloped within the soil monitoring readings in Fukushima Prefecture and also within a correlated curve between the air dose rates obtained from air dose rate readings around the disaster waste and the radioactivity concentrations of it. Based on the results of this study, JNES compiled a manual on measurement technique for contaminated disaster waste. (author)

  11. On development and improvement of evaluation techniques for strong ground motion

    International Nuclear Information System (INIS)

    Tsutsumi, Hideaki; Wu, Changjiang; Kobayashi, Genyu; Mamada, Yutaka

    2011-01-01

    The NSC regulatory guide for reviewing seismic design, revised in September 2006 requires revision of evaluation method for design seismic ground motion. The new design seismic ground motion must be evaluated based on not only response spectra method but also fault model method. In the case of evaluation method using fault model, factors which affect ground motion (heterogeneous fault rupture, frequency dependence of radiation pattern on seismic waves and high-frequency reduction on observed spectrum (fmax)) were studied in order to apply the models to actual phenomenon. In the case of response spectra, attenuation relationships for earthquake response spectra on seismic basement, considering the earthquake source types (e.g. inter-plate, intra-plate and crustal types), were developed. In addition, in coping with the problems on evaluating ground motion amplification and attenuation in deep underground, JNES drills 3000 m deep boring and acquires the data for verification of new evaluation methods at deep borehole locating on sedimentary rock site in the Niigata Institute of Technology. Moreover JNES develops borehole seismometer enduring high temperature and high pressure and enabling multi-depth seismic observation system to perform vertical seismic array observation. (author)

  12. A study on items necessary to develop the requirements for the management of serious accidents postulated in fuel fabrication, enrichment and reprocessing facilities

    International Nuclear Information System (INIS)

    Takanashi, Mitsuhiro; Yamate, Kazuki; Asada, Kazuo; Yamada, Takashi; Endo, Shigeki

    2013-05-01

    The purpose of this study is to supply the points to discuss on new rules of fuel fabrication, enrichment and reprocessing facilities (hereinafter referred to as 'fuel cycle facilities') conducted by Nuclear Regulation Authority. Requirements for management of serious accidents in the fuel cycle facilities were summarized in this study. Taking into account the lessons learned from the accident of TEPCO Fukushima Daiichi Nuclear Power Plant in Mar. 2011, Act for the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors was amended in June 2012. The main items of the amendment were as follows: Preparation for the management of serious accidents, Introduction of evaluation system for safety improvement, Application of new standards to existing nuclear facilities (back-fitting). Japan Nuclear Energy Safety organization (JNES) conducted a fundamental study on serious accidents and their management in the fuel cycle facilities and made a report. In the report, the concept of Defense in Depth and the definition of serious accidents for the fuel cycle facilities were discussed. Those discussions were conducted by reference to new regulation rules (draft) for power reactors and from the view of features of the fuel cycle facilities. However, further detailed studies are necessary in order to clarify some issues in it. It was also reflected opinions from experts in JNES technical meetings on accident management of the fuel cycle facilities to brush up this report. (author)

  13. Development of tsunami hazard analysis

    International Nuclear Information System (INIS)

    2012-01-01

    The NSC (the Nuclear Safety Commission of Japan) demand to survey on tsunami deposits by use of various technical methods (Dec. 2011), because tsunami deposits have useful information on tsunami activity, tsunami source etc. However, there are no guidebooks on tsunami deposit survey in JAPAN. In order to prepare the guidebook of tsunami deposits survey and to develop the method of tsunami source estimation on the basis of tsunami deposits, JNES carried out the following issues; (1) organizing information of paleoseismological record and tsunami deposit by literature research, and (2) field survey on tsunami deposit to prepare the guidebook. As to (1), we especially gear to tsunami deposits distributed in the Pacific coast of Tohoku region, and organize the information gained about tsunami deposits in the database. In addition, as to (2), we consolidate methods for surveying and identifying tsunami deposits in the lake based on results of the field survey in Fukui Pref., carried out by JNES. These results are reflected in the guidebook on the tsunami deposits in the lake as needed. (author)

  14. Tsunami deposits

    International Nuclear Information System (INIS)

    2013-01-01

    The NSC (the Nuclear Safety Commission of Japan) demand to survey on tsunami deposits by use of various technical methods (Dec. 2011), because tsunami deposits have useful information on tsunami activity, tsunami source etc. However, there are no guidelines on tsunami deposit survey in JAPAN. In order to prepare the guideline of tsunami deposits survey and evaluation and to develop the method of tsunami source estimation on the basis of tsunami deposits, JNES carried out the following issues; (1) organizing information of paleoseismological record and tsunami deposit by literature research, (2) field survey on tsunami deposit, and (3) designing the analysis code of sediment transport due to tsunami. As to (1), we organize the information gained about tsunami deposits in the database. As to (2), we consolidate methods for surveying and identifying tsunami deposits in the lake based on results of the field survey in Fukui Pref., carried out by JNES. In addition, as to (3), we design the experimental instrument for hydraulic experiment on sediment transport and sedimentation due to tsunamis. These results are reflected in the guideline on the tsunami deposits survey and evaluation. (author)

  15. Study on information dissemination for effective nuclear risk communication

    International Nuclear Information System (INIS)

    2013-01-01

    The aim of this study are to develop an information system and guideline for nuclear risk communication between expert and citizens as well as between both experts in terms of lessons learned from serious disaster such as Fukushima Dai-ich NPP accident. Technical standards for disseminating a result and process of seismic/tsunami PRA (Probabilistic Risk Assessment) of nuclear facility as well as nuclear risk information in an emergency, and risk communication in normal times are needed. Tins study examines the framework, contents, and technical basis for developing an information system for nuclear risk communication. In addition, this study identifies the communication issues of nuclear risk communication concerning the seismic/tsunami PRA through the testing information systems in areas around nuclear facilities and by providing effective implementation guidelines. JNES has developed the information system specified as Protection of Nuclear Power Plants against Tsunamis and Post Earthquake considerations in the External Zone (TiPEEZ) as part of IAEA International Seismic Safety Centre (ISSC) Extra Budgetary Programme (EBP). The EBP is currently preparing technical documents (TECDOC) regarding the implementation of the TiPEEZ. After the Fukushima accident, there has been increasing demand for disaster mitigation systems to share risk information between nuclear organizations and local municipalities. JNES and Niigata Institute of Technology conduct implementation of TiPEEZ for the practical use based on the corroborative works with Kashiwazaki city and citizens. (author)

  16. Study on disaster waste around Fukushima Daiichi NPS

    International Nuclear Information System (INIS)

    2012-01-01

    Extreme difficulties exists in Fukushima Prefecture in disposing of waste generated from the tsunami disaster (hereinafter referred to as disaster waste) and contaminated with radioactive material released from the crippled Fukushima Daiichi Nuclear Power Station. Although the waste should be treated according to the level of radioactivity, there were only air dose rates and radionuclide analyses of soil due to monitoring around the Fukushima Daiichi Nuclear Power Station and there had been no information on the radioactivity concentration of the disaster waste. The radioactivity concentration of the disaster waste was investigated by sampling measurement and in-situ Ge measurement at 20 temporary disaster waste storages in Fukushima Prefecture excluding the evacuation zone and 'deliberate evacuation zone.' JNES carried out tins investigation upon a request from die Nuclear and Industrial Safety Agency. The investigation revealed that the measured radioactivity concentrations of the disaster waste lumps were enveloped within the soil monitoring readings in Fukushima Prefecture and also within a correlated curve between the air dose rates obtained from air dose rate readings around the disaster waste and the radioactivity concentrations of it. Based on the results of this study, JNES compiled a manual on measurement technique for contaminated disaster waste. (author)

  17. Knowledge data base for severe accident management of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    For the safety enhancement of Nuclear Power Plants (NPPs), continuous efforts are very important to take in the up-to-date scientific and technical knowledge positively and to reflect them into the safety regulation. The purpose of the present study is to gather effectively the scientific and technical knowledge about the severe accident (SA) phenomena and the accident management (AM) for prevention and mitigation of SA, and to take in the experimental data by participating in the international cooperative experiments regarding the important SA phenomena and the effectiveness of AM. Based on those data and knowledge, JNES is developing and improving severe accident analysis models to maintain the SA analysis codes and the AM knowledge base for assessment of the NPPs in Japan. The activities in fiscal year 2012 are as follows; Analytical study on OECD/NEA projects such as MCCI, SERENA and SFP projects, and support in making regulation for SA. (author)

  18. Study on the hydrogen explosion risk at reactor building during a severe accident

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    JNES carried out analysis on the hydrogen mixing and explosion at reactor building with CFD code and explosion analysis code to evaluate what exactly has happened at the reactor buildings of the Fukushima Daiichi NPS. Based on the MELCOR severe accident analysis results of Fukushima Daiichi Unit 1 and Unit 3, sensitivity study using the CFD code FLUENT was carried out on the parameter of the release rate, total mass of hydrogen gas, the release path between reactor building and PCV, and so on. Then an analysis using AUTODYN code was carried out to investigate the explosion at the reactor building of Unit 4 as well as Unit 1 and, Unit 3. With those analysis results it became possible to estimate the leaked path and the total amount of leaked hydrogen gas from PCV to reactor building. (author)

  19. Preparation of the requirements for the safety regulation related to human and organizational factors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The outline of the project in the current fiscal year is to investigate and analyze issues associated with Human and Organizational Factors involved in incidents of nuclear facilities, and to study and develop evaluation methods of these countermeasures. The guideline to evaluate licensee's safety culture and root cause analysis (RCA) had been developed for further improving safety on nuclear power plants at 2007. These guidelines have been used at regulatory inspection since that time. Based on experience of using these existing guidelines, some activities for improving guidelines are now under investigation; these are selecting candidate quantitative indicators for safety culture evaluation and researching good practices for RCA issues. JNES implemented human factor analysis about 18 domestic events including the Fukushima Dai-ichi nuclear power plant accident. (author)

  20. Seismic assessment of air-cooled type emergency electric power supply system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    JNES initiated seismic assessment programs to develop seismic review criterions for the air-cooled system (diesel generator, gas turbine generator), which will be newly installed for enhancing the diversity of emergency electric power supply system. Five principal subjects are involved in the programs: two subjects for fiscal 2011 and three ones for fiscal 2012 and 2013. The summary of outcomes is as follows: 1) Past capacity test data and related technical issues (2011). Seismic capacity data obtained from past seismic shaking tests were investigated. 2) Test programs based on the investigation of system specification (2011). Design specifications for the air-cooled system were investigated. 3) Large Air Fin Cooler (AFC) one unit model seismic capacity test and quantitative seismic capacity evaluation. AFC one unit model seismic capacity tests were conducted and quantitative seismic capacities were evaluated. (author)

  1. Lessons learnt from the capacity building activities for Asian countries

    International Nuclear Information System (INIS)

    Nakagawa, Masaki

    2010-01-01

    Japan Nuclear Energy Safety Organization (JNES) has being providing much of cooperative activities for establishing the nuclear regulatory infrastructure to the several Asian countries like China, Indonesia, Thailand and particularly Vietnam which either started extended construction of nuclear power stations or are launching on new nuclear power programs. Our cooperation to these countries covers several different types like long-term training course, issue-specific training course and periodic safety seminar etc. Through these activities what we have learnt is that to help other countries is not an easy business. To fully recognize what are actually requested by the recipients' countries is not at all an easy business either. This paper will illustrate our experiences to have worked on the cooperative activities putting the emphasis on the lessons learnt through these experiences. (author)

  2. Seismic assessment of air-cooled type emergency electric power supply system

    International Nuclear Information System (INIS)

    2013-01-01

    JNES initiated seismic assessment programs to develop seismic review criterions for the air-cooled system (diesel generator, gas turbine generator), which will be newly installed for enhancing the diversity of emergency electric power supply system. Five principal subjects are involved in the programs: two subjects for fiscal 2011 and three ones for fiscal 2012 and 2013. The summary of outcomes is as follows: 1) Past capacity test data and related technical issues (2011). Seismic capacity data obtained from past seismic shaking tests were investigated. 2) Test programs based on the investigation of system specification (2011). Design specifications for the air-cooled system were investigated. 3) Large Air Fin Cooler (AFC) one unit model seismic capacity test and quantitative seismic capacity evaluation. AFC one unit model seismic capacity tests were conducted and quantitative seismic capacities were evaluated. (author)

  3. Enhancement of safety for reprocessing facilities

    International Nuclear Information System (INIS)

    2012-06-01

    The adequacy of the safety measures for utility loss accidents in nuclear fuel reprocessing facilities which have been formulated by the nuclear enterprises is investigated in JNES which organizes an advanced committee to specifically study this problem. The results are reviewed in the present report including the case of such severe accidents as in Fukushima Daiichi Nuclear Power Plant. The report also represents a tentative proposal for examination standards of such unimaginable severe accidents as 'station blackout,' urgent safety measures necessary for reoperation of nuclear power plants and requested by nuclear and industrial safety agency, and pointing out and clarification of the potential weakness from the safety point of view, and collective and composite evaluation of safety of the relevant facilities. Furthermore, the definition of accident management is given as of controlled condition and the authorized way of thinking for the cases of plural events happening at the same time and the cases when risks exist radioactivity emits with explosion. (S. Ohno)

  4. Current status of gas migration and swelling experiments using engineering scale model for immediate depth disposal in Japan

    International Nuclear Information System (INIS)

    Higashihara, Tomohiro; Ono, Makoto; Kawaragi, Chie; Saito, Shigeyuki

    2010-01-01

    In intermediate depth disposal facility of radioactive waste in Japan, waste is surrounded with bentonite layer to retard interaction of the waste and groundwater, because the bentonite layer saturated with the groundwater has very low hydraulic conductivity. On the other hand, it is important to confirm stability of barrier system for stress generated together with swelling of the bentonite and to understand effect of increase of gas pressure because of generation of hydrogen gas by corrosion of metallic waste. To understand and evaluate the swelling behavior of the bentonite layer, JNES carries out the experiment. In the experiments, we carry out the swelling experiment to examine the swelling behavior of the bentonite layer and the gas migration experiment to understand the gas migration behavior in the bentonite layer, using engineering scale model of the disposal facility. The swelling experiment has been in operation since June 2010. After this experiment, the gas migration experiment will start in July 2011. (orig.)

  5. Knowledge data base for severe accident management of nuclear power plants

    International Nuclear Information System (INIS)

    2013-01-01

    For the safety enhancement of Nuclear Power Plants (NPPs), continuous efforts are very important to take in the up-to-date scientific and technical knowledge positively and to reflect them into the safety regulation. The purpose of the present study is to gather effectively the scientific and technical knowledge about the severe accident (SA) phenomena and the accident management (AM) for prevention and mitigation of SA, and to take in the experimental data by participating in the international cooperative experiments regarding the important SA phenomena and the effectiveness of AM. Based on those data and knowledge, JNES is developing and improving severe accident analysis models to maintain the SA analysis codes and the AM knowledge base for assessment of the NPPs in Japan. The activities in fiscal year 2012 are as follows; Analytical study on OECD/NEA projects such as MCCI, SERENA and SFP projects, and support in making regulation for SA. (author)

  6. Overview of Fukushima accident and regulatory issues for FCFS after the accident

    International Nuclear Information System (INIS)

    Ueda, Y.

    2013-01-01

    In the first part of his presentation Yoshinori Ueda (JNES, Japan) gave an overview of the Fukushima accident and an outline of the emergency safety measures and response at the NPP site. The second part was focused on the regulatory issues for FCFs after the accident. The first issue was the emergency safety measures in case of total loss of AC power (loss capabilities of decay heat removal and hydrogen accumulation prevention) and tsunami in the reprocessing facilities and associated spent fuel storages at Tokai and Rokkasho plants. The second issue was the directions to the licensees of these facilities to secure the work environment in the main control rooms in case of complete loss of AC power, to secure communication within the facility in case of such emergency, and to secure material and equipment for radiation protection, and to deploy heavy tools for rubble removal. No paper has been made available for this presentation

  7. Continuous using of the scaling factors for radionuclide evaluation in the packaged solid wastes originated from the Japanese Nuclear Power Plants since 2003

    International Nuclear Information System (INIS)

    2005-03-01

    The amounts and concentration of the nuclides in the waste packages are estimated by measuring some key nuclides, mostly gamma emitters, from outside of the packages and by applying the scaling factor method (using the relationship between some easy to measure key nuclides and the other difficult to measure nuclides). The solid wastes are classified into two kinds of packages: homogeneous solid wastes made from concentrated liquid wastes and spent fuels solidified with cement asphalt, or plastics and heterogeneous solid wastes made of cutting metals, compacted or fused filters solidified with mortars. Japan Nuclear Energy Safety Organization (JNES) established in 2005 is in charge of the confirmation of the inside contents with radionuclide information and compliance with formalities for safety maintenance and control. (S. Ohno)

  8. The improvement of the fire protections system for nuclear cycle facilities. Formulation of a fire protection guideline for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    2012-04-01

    The private side Fire Protection Guideline was investigated with respect to the fire having taken place at the nuclear reactor site followed by the Chuetsu-Oki earthquake in Niigata Prefecture in 2007. To improve the fire protection system especially applicable to MOX fuel fabrication facilities, JNES (Japan Nuclear Energy Safety Organization) investigated private guidelines adopted in Japanese Light Water cooled Reactors, the standardized guidelines used in Nuclear Facilities in other countries including USA, and the standards in the chemical plants. The content of the guideline concerns the prevention of the fire breakout, the prevention of fire extension, the reduction of the fire effects, as well as the facility-characteristic protection countermeasures and the fire effect evaluations. (S. Ohno)

  9. CFD simulations of a turbulent flow in a T-junction

    Energy Technology Data Exchange (ETDEWEB)

    Morii, T. [Japan Nuclear Energy Safety Organization, Toranomon, Tokyo (Japan); Onishi, Y.; Hirakawa, K.; Nakamori, I. [AdvanceSoft Akasaka, Tokyo (Japan)

    2011-07-01

    Very careful T-junction tests are being performed at the Vattenfall Alkarleby Laboratory. Data from a recent test were used as the basis of an OECD/NEA blind benchmark exercise. JNES participated in this blind benchmark exercise. The present T-junction CFD simulation was performed as an incompressible fluid flow and buoyant effect was estimated by using the Boussinesq approximation. Four hexahedral grids (0.25M, 1M, 4M and 16M) were generated for grid size sensitivity study. The Large Eddy Simulation (LES) and the Reynolds Averaged Navier Stokes (RANS) turbulent models were used for a model sensitivity study. All calculation results of LES were closer to the experimental data than those of RANS. (author)

  10. Evaluation of Thermal Creep and Hydride Re-orientation Properties of High Burnup Spent Fuel Cladding under Long Term Dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Kamimura, K [JNES (Japan)

    2012-07-01

    In Japan, spent fuels will be reprocessed as recyclable energy source at a reprocessing plant. The first commercial plant is under-constructing and will start operation in 2008. It is necessary that spent fuels should be stored in the independent interim storage facilities (ISF) until reprocessing. Utilities plan the operation of the first ISF in 2010. JNES has a mission to support the safety body by researching the data of technical standard and regulation. Investigating of spent fuel integrity during long term dry storage is one of them. The objectives are: 1) Evaluation of the effects of material design changes on creep properties of high burnup spent fuel cladding; 2) Evaluation of the effects of alloy elements and texture of irradiated Zircaloy on hydride re-orientation properties and the effects of radial hydrides on cladding mechanical properties; 3) Evaluation of the effects of temperature on irradiation hardening recovery.

  11. Testing of Metal Cask and Concrete Cask

    International Nuclear Information System (INIS)

    Shirai, K.; Wataru, M.; Takeda, H.; Tani, J.; Arai, T.; Saegusa, T.

    2015-01-01

    In Japan, the first interim spent fuel storage facility (ISF) outside of nuclear power plant site in use of dual-purpose metal cask is being planned to start its commercial operation in 2012 in Mutsu city, Aomori prefecture. The CRIEPI (Central Research Institute of Electric Power Industry) has executed several study programs on demonstrative testing for interim storage of spent fuel, mainly related to metal cask and concrete cask storage technology to reflect in Japanese safety requirements for dry casks issued by NISA/METI (Nuclear and Industrial Safety Agency, Ministry of Economy and Trade Industry). On top of that, the Japan Nuclear Energy Safety Organization (JNES) has executed study programs on spent fuel integrity, etc. This paper introduces the summary of these research programs. (author)

  12. Calculation of pellet radial power distributions with a Monte Carlo burnup code

    International Nuclear Information System (INIS)

    Suzuki, Motomu; Yamamoto, Toru; Nakata, Tetsuo

    2010-01-01

    The Japan Nuclear Energy Safety Organization (JNES) has been working on an irradiation test program of high-burnup MOX fuel at Halden Boiling Water Reactor (HBWR). MOX and UO 2 fuel rods had been irradiated up to about 64 GWd/t (rod avg.) as a Japanese utilities research program (1st phase), and using those fuel rods, in-situ measurement of fuel pellet centerline temperature was done during the 2nd phase of irradiation as the JNES test program. As part of analysis of the temperature data, power distributions in a pellet radial direction were analyzed by using a Monte Carlo burnup code MVP-BURN. In addition, the calculated results of deterministic burnup codes SRAC and PLUTON for the same problem were compared with those of MVP-BURN to evaluate their accuracy. Burnup calculations with an assembly model were performed by using MVP-BURN and those with a pin cell model by using SRAC and PLUTON. The cell pitch and, therefore, fuel to moderator ratio in the pin cell calculation was determined from the comparison of neutron energy spectra with those of MVP-BURN. The fuel pellet radial distributions of burnup and fission reaction rates at the end of the 1st phase irradiation were compared between the three codes. The MVP-BURN calculation results show a large peaking in the burnup and fission rates in the pellet outer region for the UO 2 and MOX pellets. The SRAC calculations give very close results to those of the MVP-BURN. On the other hand, the PLUTON calculations show larger burnup for the UO 2 and lower burnup for the MOX pellets in the pellet outer region than those of MVP-BURN, which lead to larger fission rates for the UO 2 and lower fission rates for the MOX pellets, respectively. (author)

  13. Safety research plan, JFY 2013 edition

    International Nuclear Information System (INIS)

    2013-09-01

    As for the regulatory issues the governments or JNES considered necessary, JNES had updated every year 'safety research plan' in respective research areas necessary for solving the regulatory issues (safety research needs) and was conducting safety research to obtain the results, etc. 'Safety research plan, JFY 2013 Edition' was compiled aiming at promotion of appropriate reflection and flexible application of research achievements for tacking the regulatory issues taking account of importance and urgency dependent on trend of nuclear safety regulations as well as collective management of safety research and safety survey. 5 new research projects were established with 4 unified research projects and 6 terminated research projects. Finally modified safety research areas, subjects and research projects, JFY 2013 Edition were as follows: design review of nuclear power plant (7 subjects and each subject having several research projects totaled 19), control management of nuclear power plant (one subject having 4 research projects), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 4), nuclear fuel cycle backend (2 subjects and each subject having several research projects totaled 5), nuclear emergency preparedness and response (3 subjects and each subject having several research projects totaled 7) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 6). Safety reviews consisted of 6 projects in 3 areas extracting the regulatory issues. As for urgent research projects on the basis of the disaster at Fukushima Daiichi NPP accident, 7 research projects in 4 urgent subjects were as follows: examination for new safety regulation (4 research projects generalized in the above research projects), development of newly necessary evaluation methods (one research project generalized in the above research project), evaluation of the validity for the work for convergence at Fukushima

  14. Ageing management and knowledge base for safe long-term operation of japanese light water reactors

    International Nuclear Information System (INIS)

    Sekimura, N.

    2008-01-01

    There are 55 operating commercial light water reactor plants (32 BWRs and 23 PWRs) in Japan. Twelve (12) plants have been operating for more than 30 years. Utility companies are required to perform an 'Ageing Management Technical Assessment' be-fore the end of 30 years operation of each plant. The assessments for each plant have been evaluated by the Nuclear and Industry Safety Agency (NISA) of the Ministry of Economy Trade and Industry (WTI) for these 12 plants. The Japan Nuclear Energy Safety Organisation (JNES) has compiled Technical Review Manuals for six major degradation phenomena for the evaluation of Ageing Management Technical Assessment. A 'Road-map for Ageing and Plant Life Management' was established in 2005 by the Special Committee in the Atomic Energy Society of Japan under the commission from the JNES. Within the framework of the road-map, the major research and development fields are divided into the following four categories: 1) engineering information systems; 2) research and development of technologies for inspection, evaluation and repair of the components and materials; 3) development of codes and standards; 4) synthesised maintenance engineering. Continuous revision of the 'Strategy Maps for Ageing Management and Safe Long-term Operation' has been performed under the Coordinating Committee of Ageing Management to promote research and development activities by industries, government and academia, effectively and efficiently. Systematic development of the information basis for database and knowledge-base has been undertaken in addition to the development of codes and standards by academic societies through intensive domestic safety research collaborations and international collaboration. (author)

  15. Kultuurkapital jagas tunnustust

    Index Scriptorium Estoniae

    2008-01-01

    Eesti Kultuurkapitali 2007. a. arhitektuuri valdkonna peapreemia pälvis Vello Asi, kujutava ja rakenduskunsti valdkonna peapreemia Jaan Toomik. Sihkapitalide preemiad: kujutav ja rakenduskunst - Evi Viires, Vano Allsalu ja Sally Stuudio (veebikeskkond kunstikeskus.ee), kunstnike rühmitus Non Grata, kunstiühing Pallas. Arhitektuur - Raili Paling, Liis Lindvere, Lembit-Kaur Stöör, Tõnis Kimmel (Tallinna sünagoog), Silja Konsa, Urve Sinijärv, Olev Abner, Kersti Lootus, Ants Hein (teatmeteos "Eesti pargid"), Kalle Vellevoog (pansionaat Seedri t. 4 Pärnus), Aivar Roosaar (Athena konverentsi- ja kultuurikeskuse renoveerimine), Kalle Komissarov. Rahvakultuur - Kadi Pajupuu, Reet Piiri, Tiia Toomet (Tartu Mänguasjamuuseumi rajamine). Preemiaid said ka filmi "Sügisball" loominguline kollektiiv koosseisus Veiko Õunpuu, Mart Taniel, Ülo Krigul, Katrin Kissa (audiovisuaalne kunst), Jaan Rääts (helikunst), Mare Tommingas (näitekunst), X noorte laulu- ja tantsupeo kunstilised juhid Aarne Saluveer ja Maido Saar (rahvakultuur). Lisaks sellele andsid sihtkapitalid välja oma aastapreemiad. Nimekiri

  16. Assessment guide for tornado effect on Nuclear Power Plants (draft) with its commentaries

    International Nuclear Information System (INIS)

    Inoue, Hiroto; Fukunishi, Shiro; Suzuki, Tetsuo

    2013-10-01

    In the context of a severe accident at the Fukushima Daiichi Nuclear Power Station (NPS) operated by the Tokyo Electric Power Company (TEPCO) due to the 2011 off the Pacific coast of Tohoku Earthquake and Tsunami, Nuclear Regulation Authority (NRA) was established on September 19, 2012 under the relevant law. After that NRA organized a task force for studying new regulatory standards for nuclear power plants (NPPs) in consideration of lessons learned from the severe accident at Fukushima. In the task force open meeting, through discussing about design basis external natural events which should be considered in the new regulatory standards, tornado was newly introduced into new regulatory standards as an external natural event. Based on the decision that tornado was newly introduced into new regulatory standards, the Secretariat of the Nuclear Regulation Authority (SNRA) commissioned the Japan Nuclear Energy Safety Organization (JNES) to study an assessment guide for tornado effect on NPPs intended to be used for an official safety review for a NPP construction. JNES organized Sectional Committee for Tornado Effect Assessment Guide consisting of experts in meteorology and wind engineering fields, discussing about assessment methods for tornado effect on NPPs, draft version of the assessment guide for tornado effect on NPPs was completed on April 4, 2013, and JNES submitted the draft guide to SNRA on the same date. After that NRA called for public comments for the draft version of the assessment guide, the draft version of the assessment guide was partly amended taking posted public comments account, and tornado effect assessment guide was officially released on June 19, 2013. Contents in this paper are as follows, assessment guide for tornado effect on NPPs (Draft version on April 4, 2013), supplementary documents, calculation examples, and future tasks for further improved reliability of tornado effect assessment on NPPs. This draft guide consists of six chapters

  17. Assessment guide for tornado effect on Nuclear Power Plants (draft) with its commentaries

    Energy Technology Data Exchange (ETDEWEB)

    Inoue, Hiroto; Fukunishi, Shiro; Suzuki, Tetsuo [Japan Nuclear Energy Safety Organization, Seismic Safety Department, Tokyo (Japan)

    2013-10-15

    In the context of a severe accident at the Fukushima Daiichi Nuclear Power Station (NPS) operated by the Tokyo Electric Power Company (TEPCO) due to the 2011 off the Pacific coast of Tohoku Earthquake and Tsunami, Nuclear Regulation Authority (NRA) was established on September 19, 2012 under the relevant law. After that NRA organized a task force for studying new regulatory standards for nuclear power plants (NPPs) in consideration of lessons learned from the severe accident at Fukushima. In the task force open meeting, through discussing about design basis external natural events which should be considered in the new regulatory standards, tornado was newly introduced into new regulatory standards as an external natural event. Based on the decision that tornado was newly introduced into new regulatory standards, the Secretariat of the Nuclear Regulation Authority (SNRA) commissioned the Japan Nuclear Energy Safety Organization (JNES) to study an assessment guide for tornado effect on NPPs intended to be used for an official safety review for a NPP construction. JNES organized Sectional Committee for Tornado Effect Assessment Guide consisting of experts in meteorology and wind engineering fields, discussing about assessment methods for tornado effect on NPPs, draft version of the assessment guide for tornado effect on NPPs was completed on April 4, 2013, and JNES submitted the draft guide to SNRA on the same date. After that NRA called for public comments for the draft version of the assessment guide, the draft version of the assessment guide was partly amended taking posted public comments account, and tornado effect assessment guide was officially released on June 19, 2013. Contents in this paper are as follows, assessment guide for tornado effect on NPPs (Draft version on April 4, 2013), supplementary documents, calculation examples, and future tasks for further improved reliability of tornado effect assessment on NPPs. This draft guide consists of six chapters

  18. Multi-scale analysis of deformation behavior at SCC crack tip (3) (Contract research)

    International Nuclear Information System (INIS)

    Kaji, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Hayakawa, Masao; Nagashima, Nobuo

    2008-08-01

    In recent years, incidents of the stress corrosion cracking (SCC) were frequently reported that occurred to the various components of domestic boiling water reactors (BWR), and the cause investigation and measure become the present important issue. By the Japan nuclear energy safety organization (JNES), a research project on the intergranular SCC (IGSCC) in nuclear grade stainless steels (henceforth, IGSCC project) is under enforcement from a point of view to secure safety and reliability of BWR, and SCC growth data of low carbon stainless steels are being accumulated for the weld part or the work-hardened region adjacent to the weld metal. In the project, it has been an important subject to guarantee the validity of accumulated SCC data. At a crack tip of SCC in compact tension (CT) type specimen used for the SCC propagation test, a macroscopic plastic region is formed where heterogeneity of microstructure developed by microscopic sliding and dislocations is observed. However, there is little quantitative information on the plastic region, and therefore, to assess the data of macroscopic SCC growth rate and the validity of propagation test method, it is essentially required to investigate the plastic region at the crack tip in detail from a microscopic viewpoint. This report describes a result of the research conducted by the Japan Atomic Energy Agency and the National Institute for Materials Science under contract with JNES that was concerned with a multi-scale analysis of plastic deformation behavior at the crack tip of SCC. The research was carried out to evaluate the validity of the SCC growth data acquired in the IGSCC project based on a mechanistic understanding of SCC. For the purpose, in this research, analyses of the plastic deformation behavior and microstructure around the crack tip were performed in a nano-order scale. The hardness measured in nano, meso and macro scales was employed as a common index of the strength, and the essential data necessary

  19. Tsunami hazard

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Tohoku Earthquake Tsunami on 11 March, 2011 has led the Fukushima Daiichi nuclear power plant to a serious accident, which highlighted a variety of technical issues such as a very low design tsunami height and insufficient preparations in case a tsunami exceeding the design tsunami height. Lessons such as to take measures to be able to maintain the important safety features of the facility for tsunamis exceeding design height and to implement risk management utilizing Probabilistic Safety Assessment are shown. In order to implement the safety assessment on nuclear power plants across Japan accordingly to the back-fit rule, Nuclear Regulatory Commission will promulgate/execute the New Safety Design Criteria in July 2013. JNES has positioned the 'enhancement of probabilistic tsunami hazard assessment' as highest priority issue and implemented in order to support technically the Nuclear Regulatory Authority in formulating the new Safety Design Criteria. Findings of the research had reflected in the 'Technical Review Guidelines for Assessing Design Tsunami Height based on tsunami hazards'. (author)

  20. Severe accident tests and development of domestic severe accident system codes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    According to lessons learned from Fukushima-Daiichi NPS accidents, the safety evaluation will be started based on the NRA's New Safety Standards. In parallel with this movement, reinforcement of Severe Accident (SA) Measures and Accident Managements (AMs) has been undertaken and establishments of relevant regulations and standards are recognized as urgent subjects. Strengthening responses against nuclear plant hazards, as well as realistic protection measures and their standardization is also recognized as urgent subjects. Furthermore, decommissioning of Fukushima-Daiichi Unit1 through Unit4 is promoted diligently. Taking into account JNES's mission with regard to these SA Measures, AMs and decommissioning, movement of improving SA evaluation methodologies inside and outside Japan, and prioritization of subjects based on analyses of sequences of Fukushima-Daiichi NPS accidents, three viewpoints was extracted. These viewpoints were substantiated as the following three groups of R and D subjects: (1) Obtaining near term experimental subjects: Containment venting, Seawater injection, Iodine behaviors. (2) Obtaining mid and long experimental subjects: Fuel damage behavior at early phase of core degradation, Core melting and debris formation. (3) Development of a macroscopic level SA code for plant system behaviors and a mechanistic level code for core melting and debris formation. (author)

  1. Evaluation of neutron irradiation effect on SCC crack growth behaviour for austenitic stainless steels

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Austenitic stainless steels are widely used as structural components in reactor pressure vessel internals because of their high strength, ductility, and fracture toughness. However, exposure to neutron irradiation results in changes in microstructure, mechanical properties and microchemistry of the steels. Irradiation assisted stress corrosion cracking (IASCC) caused by the effect of neutron irradiation during long term plant operation in high temperature water environments is considered to take the form of intergranular stress corrosion cracking (IGSCC) and the critical fluence level has been reported to be about 5x10{sup 24}n/m{sup 2} (E>1MeV) in Type 304 stainless steel in BWR environment. JNES had been conducting IASCC project during the JFY (2000) - JFY (2008) period, and prepared an engineering database on IASCC. However, the data of Crack Growth Rate (CGR) below the critical fluence level are not sufficient. So, this project was initiated to obtain the CGR data below the critical fluence level. Test specimens have been irradiated in the Halden reactor, operating by the OECD Halden Reactor Project, and the post irradiation examination (PIE) will be conducted from JFY (2011) to JFY (2013), finally the modified IASCC guide will be prepared in JFY (2013). (author)

  2. Preparation of safety regulatory requirements for new technology like digital system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The current regulatory requirements on digital instrumentation and control system have been reviewed by JNES, considering international trend discussed in DICWG of MDEP. MDEP DICWG held in OECD/NEA gives the opportunity to identify the convergence of applicable standards. The working group's activities include: identifying and prioritising the member countries' challenges, practices, and needs regarding standards and regulatory guidance on digital instrumentation and control; identifying areas of importance and needs for convergence of existing standards and guidance or development of new standards; sharing of information; and identifying common positions among the member countries for areas of particular importance and need. The DICWG drafted common positions on specific issues which are based on the existing standards, national regulatory guidance, best practices, and group inputs using an agreed process and framework. The following four general common positions have been discussed in this fiscal year. The Treatment of Common Cause Failure Resulting from Software within Digital Safety Systems, The Treatment of Hardware Description Language(HDL) Programmed Devices for Use in Nuclear Safety System, Factory Acceptance Test and Site Acceptance Test, The Use of Automatic Tests to Perform Surveilance for Digital Systems. (author)

  3. Severe accident tests and development of domestic severe accident system codes

    International Nuclear Information System (INIS)

    2013-01-01

    According to lessons learned from Fukushima-Daiichi NPS accidents, the safety evaluation will be started based on the NRA's New Safety Standards. In parallel with this movement, reinforcement of Severe Accident (SA) Measures and Accident Managements (AMs) has been undertaken and establishments of relevant regulations and standards are recognized as urgent subjects. Strengthening responses against nuclear plant hazards, as well as realistic protection measures and their standardization is also recognized as urgent subjects. Furthermore, decommissioning of Fukushima-Daiichi Unit1 through Unit4 is promoted diligently. Taking into account JNES's mission with regard to these SA Measures, AMs and decommissioning, movement of improving SA evaluation methodologies inside and outside Japan, and prioritization of subjects based on analyses of sequences of Fukushima-Daiichi NPS accidents, three viewpoints was extracted. These viewpoints were substantiated as the following three groups of R and D subjects: (1) Obtaining near term experimental subjects: Containment venting, Seawater injection, Iodine behaviors. (2) Obtaining mid and long experimental subjects: Fuel damage behavior at early phase of core degradation, Core melting and debris formation. (3) Development of a macroscopic level SA code for plant system behaviors and a mechanistic level code for core melting and debris formation. (author)

  4. Analysis of LWR Full MOX Core Physics Experiments with Major Nuclear Data Libraries

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, Toru [Japan Nuclear Energy Safety Organization, Tokyo (Japan)

    2007-07-01

    Nuclear Power Engineering Corporation (NUPEC) studied high moderation full MOX cores as a part of advanced LWR core concept studies from 1994 to 2003 supported by the Ministry of Economy, Trade and Industry. In order to obtain the major physics characteristics of such advanced MOX cores, NUPEC carried out core physics experimental programs called MISTRAL and BASALA from 1996 to 2002 in the EOLE critical facility of the Cadarache Center in collaboration with CEA. NUPEC also obtained a part of experimental data of the EPICURE program that CEA had conducted for 30 % Pu recycling in French PWRs. Japan Nuclear Energy Safety Organization(JNES) established in 2003 as an incorporated administrative agency took over the NUPEC's projects for nuclear regulation and has been implementing FUBILA program that is for high burn up BWR full MOX cores. This paper presents an outline of the programs and a summary of the analysis results of the criticality of those experimental cores with major nuclear data libraries.

  5. A guideline for comprehensive evaluation of a licensee's effort to cultivate safety culture

    International Nuclear Information System (INIS)

    Makino, Maomi; Ishii, Yoichi

    2009-01-01

    The nuclear industry in Japan had held excellent performance in safety in the world during 90's. However recent events stem from organizational factors and defects of safety culture are pointed out in their contexts. In order to reduce accidents caused by organizational factors, the Japanese Regulatory body NISA (Nuclear and Industrial Safety Agency) decided to evaluate a licensee's effort for the cultivation of safety culture, and to order all licensses to add the provision of cultivating safety culture to their safety preservation rules. The inspection for the new safety preservation rules started in December, 2007. For a measure of evaluation by resident inspectors, NISA and the Japan Nuclear Energy Safety Organization (JNES) prepared a guideline for the prevention of degradation of safety culture and organizational climate. In this guideline, 14 items were defined as the components of the safety culture or as the viewpoints to evaluate the effort made to prevent any degradation of safety culture and organizational climate in the daily safety preservation activities. The 14 items are also used to establish the method to comprehensively evaluate the effort to prevent degradation of safety culture and organizational climate. This method consists of 10 steps: two steps to taken prior to start of the evaluation, two steps to be taken during the evaluation period, 5 steps to be taken during a comprehensive evaluation period and a final step to be taken for comprehensive findings for safety culture. This paper mainly describes the viewpoints to evaluate comprehensively a licensee's effort for cultivation of safety culture. (author)

  6. Evaluation of neutron irradiation effect on SCC crack growth behaviour of austenitic stainless steel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    Austenitic stainless steels are widely used as structural materials alloy in reactor pressure vessel internal components because of their high strength, ductility and fracture toughness. However, exposure due to neutron irradiation results in changes in microstructure, mechanical properties and microchemistry of the material. Irradiation assisted stress corrosion cracking (IASCC) caused by the effect of neutron irradiation during long term operation in high temperature water environments in nuclear power plants is considered to take the form of intergranular stress corrosion cracking (IGSCC) and the critical fluence level has been reported to be about 5x10{sup 24}n/m{sup 2} (E>1MeV) for Type 304 SS in BWR environment. JNES had been conducting IASCC project during from JFY 2000 to JFY 2008, and prepared an engineering database on IASCC. However, the data of crack growth rate (CGR) below the critical fluence level are not sufficient. Therefore, evaluation of neutron irradiation effect project (ENI) was initiated to obtain the CGR data below the critical fluence level, and prepare the SCC growth rate diagram for life time evaluation of core shroud. Test specimens have been irradiated in the OECD/Halden reactor, and the post irradiation experiments (PIE) have been conducting during from JFY 2011 to JFY 2013, finally the modified IASCC guide will be prepared in JFY 2013. (author)

  7. Study on clearance system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    The clearance system is a legal system to release 'the radioactive waste not requiring treatment as radioactive waste' from the regulatory control. JNES supports Nuclear Regulatory Agency on approval and confirmation of clearance measurement and judgment developed by the operator. The objective of this study is to establish technical base of the validation method of the clearance measurement for various objects. In uranium processing facilities, simulation sources emitting alpha-rays is used in a validity confirmation examination of the measuring equipment. In this study, these sources were examined by measuring alpha and beta spectra to evaluate the applicability and problem of these sources. In addition, the measuring method detecting gamma-rays was examined. This method can be applied to complicated objects. As a part to develop a manual for unexpected incidents in clearance system, a quick method for measurement of Strontium 90 was examined. In addition, the measuring methods for the judgment of the influence of fallout and for NR (Non-Radioactive) confirmation were examined. (author)

  8. Enhancement of safety for reprocessing facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-08-15

    After the accident in Fukushima Daiichi Nuclear Power Station, eight emergency projects taking into account the accident were newly launched in JNES. This project for a reprocessing facility was one of them. Major items conducted in the project were as follows. (1) Researches, studies and evaluations etc. on various events under a total AC (alternating current) power loss condition Under this condition following subjects of the events were performed. a) An equipment with a removing function of decay heat and a time to reach a certain critical condition, e.g. a solution boiling, b) An equipment with a preventing function of accumulation of hydrogen gas and a time to reach a concentration of hydrogen gas to that of the lowest limit of combustion, c) Specifications of an alternative electric source and how to supply power. (2) Researches, studies and evaluations etc. on beyond design basis events. Following subjects on these events were performed. a) An event progression scenario, a consequence, a time period between an initiating event and a resultant accident or a certain critical condition, and draft inspection criteria, b) Draft inspection criteria for a stress test. (author)

  9. Seismic Capacity Estimation of Steel Piping Elbow under Low-cycle Fatigue Loading

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Bub Gyu; Kim, Sung Wan; Choi, Hyoung Suk; Kim, Nam Sik [Pusan National University, Busan (Korea, Republic of); Hahm, Dae Gi [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    In some cases, this large relative displacement can increase seismic risk of the isolated facility. Especially, a inelastic behavior of crossover piping system to connect base isolated building and fixed base building can caused by a large relative displacement. Therefore, seismic capacity estimation for isolated piping system is needed to increase safety of nuclear power plant under seismic condition. Dynamic behavior analysis of piping system under seismic condition using shake table tests was performed by Touboul et al in 1995. In accordance with their study, plastic behavior could be occurred at pipe elbow under seismic condition. Experimental researches for dynamic behavior of typical piping system in nuclear power plant have been performed for several years by JNES(Japan Nuclear Energy Safety Organization) and NUPEC(Nuclear Power Engineering Corporation). A low cycle ratcheting fatigue test was performed with scaled model of elbow which is a weakest component in piping system by Mizuno et al. In-plane cyclic loading tests under internal pressure condition were performed to evaluate the seismic capacity of the steel piping elbow. Leakage phenomenon occurred on and near the crown in piping elbow. Those cracks grew up in axial direction. The fatigue curve was estimated from test results. In the fatigue curve, loading amplitude exponentially decreased as the number of cycles increased. A FEM model of piping elbow was modified with test results. The relationships between displacement and force from tests and numerical analysis was well matched.

  10. A study on reactor core failure thresholds to safety operation of LMFBR

    International Nuclear Information System (INIS)

    Kazuo, Haga; Hiroshi, Endo; Tomoko, Ishizu; Yoshihisa, Shindo

    2006-01-01

    Japan Nuclear Safety Organization (JNES) has been developing the methodology and computer codes for applying level-1 PSA to LMFBR. Many of our efforts have been directed to the judging conditions of reactor core damage and the time allowed to initiate the accident management. Several candidates of the reactor core failure threshold were examined to a typical proto-type LMFBR with MOX fuel based on the plant thermal-hydraulic analyses to the actual progressions leading to the core damage. The results of the present study showed that the judging condition of coolant-boundary integrity failure, 750 degree-C of the boundary temperature, is enough as the threshold of core damage to PLOHS (protected loss-of-heat sink). High-temperature fuel cladding creep failure will not take place before the coolant-boundary reaches the judging temperature and sodium boiling will not occur due to the system pressure rise. In cases of ATWS (anticipated transient without scrum) the accident progression is so fast and the reactor core damage will be inevitable even a realistic negative reactivity insertion due to the temperature rise is considered. Only in the case of ULOHS (unprotected loss-of-heat sink) a relatively long time of 11 min will be allowed till the shut-down of the reactor before the core damage. (authors)

  11. Knowledge data base for severe accident management of nuclear power plants

    International Nuclear Information System (INIS)

    Ogino, Masao; Kawabe, Ryuhei; Nagasaka, Hideo; Sumida, Susumu; Fukasawa, Masanori; Muta, Hitoshi

    2011-01-01

    For the reinforcement of the safety of NPPs, the continuous efforts are very important to take in the up-to-date scientific and technical knowledge positively and to reflect them into the safety regulation. The purpose of this present study is to gather effectively the scientific and technical knowledge about the severe accident (SA) phenomena and the accident management (AM) for prevention and mitigation of severe accident, and to take in the experimental data by participating in the international cooperative experiments regarding the important SA phenomena and the effectiveness of accident management. Based on those data and knowledge, JNES is developing and improving severe accident analysis models to maintain the severe accident analysis codes and the accident management knowledge base for assessment of the NPPs in Japan. The activities in fiscal year 2010 are as follows; Experimental study on OECD/NEA projects such as MCCI, SERENA, SFP and international cooperative PSI-ARTIST project, and analytical study on accident management review of new plant and making regulation for severe accident. (author)

  12. Development of ISA procedure for uranium fuel fabrication and enrichment facilities: overview of ISA procedure and its application

    International Nuclear Information System (INIS)

    Yamate, Kazuki; Yamada, Takashi; Takanashi, Mitsuhiro; Sasaki, Noriaki

    2013-01-01

    Integrated Safety Analysis (ISA) procedure for uranium fuel fabrication and enrichment facilities has been developed for aiming at applying risk-informed regulation to these uranium facilities. The development has carried out referring to the ISA (NUREG-1520) by the Nuclear Regulatory Commission (NRC). The paper presents purpose, principles and activities for the development of the ISA procedure, including Risk Level (RL) matrix and grading evaluation method of IROFS (Items Relied on for Safety), as well as general description and features of the procedure. Also described in the paper is current status in application of risk information from the ISA. Japanese four licensees of the uranium facilities have been conducting ISA for their representative processes using the developed procedure as their voluntary safety activities. They have been accumulating experiences and knowledge on the ISA procedure and risk information through the field activities. NISA (Nuclear and Industrial Safety Agency) and JNES (Japan Nuclear Energy Safety Organization) are studying how to use such risk information for the safety regulation of the uranium facilities, taking into account the licensees' experiences and knowledge. (authors)

  13. Statistical safety evaluation of BWR turbine trip scenario using coupled neutron kinetics and thermal hydraulics analysis code SKETCH-INS/TRACE5.0

    International Nuclear Information System (INIS)

    Ichikawa, Ryoko; Masuhara, Yasuhiro; Kasahara, Fumio

    2012-01-01

    The Best Estimate Plus Uncertainty (BEPU) method has been prepared for the regulatory cross-check analysis at Japan Nuclear Energy Safety Organization (JNES) on base of the three-dimensional neutron-kinetics/thermal-hydraulics coupled code SKETCH-INS/TRACE5.0. In the preparation, TRACE5.0 is verified against the large-scale thermal-hydraulic tests carried out with NUPEC facility. These tests were focused on the pressure drop of steam-liquid two phase flow and void fraction distribution. From the comparison of the experimental data with other codes (RELAP5/MOD3.3 and TRAC-BF1), TRACE5.0 was judged better than other codes. It was confirmed that TRACE5.0 has high reliability for thermal hydraulics behavior and are used as a best-estimate code for the statistical safety evaluation. Next, the coupled code SKETCH-INS/TRACE5.0 was applied to turbine trip tests performed at the Peach Bottom-2 BWR4 Plant. The turbine trip event shows the rapid power peak due to the voids collapse with the pressure increase. The analyzed peak value of core power is better simulated than the previous version SKETCH-INS/TRAC-BF1. And the statistical safety evaluation using SKETCH-INS/TRACE5.0 was applied to the loss of load transient for examining the influence of the choice of sampling method. (author)

  14. Effective use of plant simulators and mock-up facilities for cultivation and training of younger regulators

    International Nuclear Information System (INIS)

    Tsuruga, Keisuke

    2010-01-01

    In order to achieve effective safety regulation, the staff members of a regulatory body who are engaged in regulatory work are requested to be well familiar with the characteristics, operations and maintenances of nuclear power plants at a practical level as far as possible. Although the regulators are not always required to have the same level of skills as those of plant designers or operators, the skills of the regulatory staff are essential elements to achieve high quality of the national nuclear safety regulation. Especially understanding of fundamentals such as operations, transient behaviors, trouble responses and plant inspections is indispensable not only to practical regulatory work but also to the establishment of the trust and confidence in safety regulation. To acquire these skills, the use of facilities such as plant simulators and inspection mock-up facilities is very effective to back up classroom lectures on theories and procedures. Practical training using these facilities under the guidance of well-experienced instructors inspires motivations and enhances capabilities of younger regulators. To support the countries newly embarking on nuclear power programs, JNES will continue to cooperate with those countries in cultivating and training younger regulators, by focusing on the training by veteran instructors using full-scale plant simulators and inspection mock-up facilities to give the trainees more practical skills and knowledge difficult to obtain through classroom lectures or textbooks. (author)

  15. Seismic Intensity Map Triggered by Observed Strong Motion Records Considering Site Amplification and its service based on Geo-spatial International Standard

    International Nuclear Information System (INIS)

    Matsuoka, Masashi

    2014-01-01

    Instrumental seismic intensity measurement is carried out at approximately 4,200 points in Japan, but the correct values at points without seismometers cannot always be provided because seismic motion depends on geologic and geomorphologic features. Quick provision of accurate information on seismic intensity distribution over wide areas is required for disaster mitigation. To estimate seismic intensity at specific points, it is important to prepare ground amplification characteristics for local areas beforehand and use an interpolation algorithm. The QuiQuake system (quick estimation system for earthquake maps triggered by using observation records from K-NET and KiK-net that have been released by the National Research Institute for Earth Science and Disaster Prevention), which uses these, was developed; it can be started up automatically using seismograms and can immediately display a seismic intensity distribution map. The calculation results are sent to IAEA and JNES in the form of strong motion evaluation maps with a mesh size of 250 x 250 m. These maps are also sent to the general public via social networking web sites. (author)

  16. Study on clearance system

    International Nuclear Information System (INIS)

    Onishi, Yuko; Miura, Hiroshi; Kawasaki, Satoru

    2011-01-01

    The clearance system is a legal system to release 'the radioactive waste not requiring treatment as radioactive waste' from the regulatory control. JNES supports NISA on approval and confirmation of clearance measurement and judgment developed by the operator. The objective of this study is to establish technical base of the validation method of the clearance measurement for various objects. In reactor facilities, the bulk measurement technique or the statistical sampling measurement technique may be applied to large scale objects or concrete walls. In this study, the criteria of those techniques were examined. In uranium processing facilities, it is important to confirm surface state of the object in case of detecting alpha rays. The result of the examination about the influence of the surface rust in the uranium clearance measurement by the alpha ray measurement showed that the pollution was distributed in rust layer uniformly. This result will be reflected to the revision of the Ministerial Ordinance on Clearance in 2011FY. To develop a manual for unexpected incidents, the response procedure for an unexpected incident was prepared, including a response system. (author)

  17. Development of PSA procedure for a criticality in reprocessing facilities

    International Nuclear Information System (INIS)

    Endo, Shigeki; Takanashi, Mitsuhiro; Ueda, Yoshinori

    2012-08-01

    Utilization of risk information for the nuclear safety regulation is being discussed in Japan. The development of probabilistic safety assessment (PSA) procedure is indispensable for the utilization of risk information. The Japan Nuclear Energy Safety Organization (JNES) has been conducting trial PSA to a model plant for major events, i.e. hydrogen explosion, solution boiling, rapid decomposition of TBP complexes, criticality, solvent fire, leakage of molten glass, leakage of high active concentrated liquid waste, loss of all AC electricity, drop of a fuel assembly, for the purpose of developing the PSA procedure for reprocessing facilities. For criticality events results of trial PSA were summarized as a report in which how to evaluate an amount of radioactive materials released from a facility and a health effect on the public were emphasized. Therefore, for criticality events the results of trial PSA were summarized in this report to emphasize procedures from making event progression scenarios to quantifying event sequences, which were not handled in the previous report, in a style of a document describing PSA procedures. (author)

  18. ISP-50 Specifications for a Direct Vessel Injection Line Break Test with the ATLAS

    International Nuclear Information System (INIS)

    Choi, Ki Yong; Baek, Won Pil; Kim, Yeon Sik; Park, Hyun Sik; Cho, Seok; Kang, Kyoung Ho; Choi, Nam Hyun; Min, Kyoung Ho

    2009-06-01

    An OECD/NEA International Standard Problem Exercise (ISP) focussing on a DVI line break simulation result with the ATLAS was approved by the NEA Committee on the Safety of Nuclear Installation (CSNI) meeting in December 2008 and was numbered by ISP-50. The ISP-50 program will be operated by an operating agency, KAERI for three years starting from the physical year 2009. Fourteen international organizations confirmed their participation in the ISP-50, including NRC (USA), JAEA, JNES (Japan), GRS (Germany), KFKI-AEKI (Hungary), EDO Gidropress (Russia), VTT, Fortum (Finland), NRI (Czech Republic), Univ. of Pisa (Italy), KINS, KNF, KOPEC, and KAERI (Korea). In addition, KTH in Sweden and HSE in UK are considering late participation. Recently, NPIC and CIAE in China hope to join the ISP-50. As for the safety analysis codes, nine codes are expected to be used for the ISP-50: MARS-3D, RELAP5- 3D, RELAP5, TRACE, CATHARE, APROS, ATHELET, TRAP, and KORSAR. It is the first ISP exercise in Korea in which a domestic test facility is utilized by international nuclear society and this exercise will contribute to extending our physical understanding on thermal hydraulic phenomena during the DVI line break accidents and to verifying the best-estimate thermal-hydraulic safety analysis codes. This report was prepared to define technical specifications of the ISP-50 exercise according the guideline provided by OECD/CSNI. It includes general objectives, phases, deliverables to participants, parameters required for comparison and the time table

  19. Research regarding evaluation of earthquake and tsunami that preceded it in nuclear reactors

    International Nuclear Information System (INIS)

    2012-01-01

    The 2011 off the Pacific coast of Tohoku Earthquake generated a series of large tsunami waves that struck the east coast of Japan. Several nuclear power facilities were affected by the large multiple tsunami waves. As the result, Fukushima Daiichi 1-4 has progressed to a serious accident. But, integrity evaluation of equipments for tsunami has not been established. Therefore, draft of the Guidelines for tsunami design were formulated with reference to this serious accident in JNES. The action item is as follows. I. Survey of damage caused by the earthquake and design information. To investigate the damage situation of nuclear power plants have been conducted. In addition, to organize the placement information of equipments pertaining to seawater cooling system and emergency power system. And to organize tsunami countermeasures of current nuclear power plants. II. The formation of draft of Guidelines for Tsunami Design. Design policy was formulated in Guidelines for Tsunami Design based on the investigation of survey results of I. (author)

  20. Tsunami hazard

    International Nuclear Information System (INIS)

    2013-01-01

    Tohoku Earthquake Tsunami on 11 March, 2011 has led the Fukushima Daiichi nuclear power plant to a serious accident, which highlighted a variety of technical issues such as a very low design tsunami height and insufficient preparations in case a tsunami exceeding the design tsunami height. Lessons such as to take measures to be able to maintain the important safety features of the facility for tsunamis exceeding design height and to implement risk management utilizing Probabilistic Safety Assessment are shown. In order to implement the safety assessment on nuclear power plants across Japan accordingly to the back-fit rule, Nuclear Regulatory Commission will promulgate/execute the New Safety Design Criteria in July 2013. JNES has positioned the 'enhancement of probabilistic tsunami hazard assessment' as highest priority issue and implemented in order to support technically the Nuclear Regulatory Authority in formulating the new Safety Design Criteria. Findings of the research had reflected in the 'Technical Review Guidelines for Assessing Design Tsunami Height based on tsunami hazards'. (author)

  1. Preparation of safety regulatory requirements for new technology like digital system

    International Nuclear Information System (INIS)

    Ito, Juichiro; Takita, Masami

    2011-01-01

    The current regulatory requirements on digital instrumentation and control system have been reviewed by JNES, considering international trend discussed in DICWG (Digital Instrumentation and Control Working Group) of MDEP (Multinational Design Evaluation Program). MDEP DICWG held in OECD/NEA (Organisation for Economic Co-operation and Development/Nuclear Energy Agency) gives the opportunity to identify the convergence of applicable standards. The working group's activities include: identifying and prioritising the member countries' challenges, practices, and needs regarding standards and regulatory guidance regarding digital instrumentation and control; identifying areas of importance and needs for convergence of existing standards and guidance or development of new standards; sharing of information; and identifying common positions among the member countries for areas of particular importance and need. The DICWG drafted common positions on specific issues which are based on the existing standards, national regulatory guidance, best practices, and group inputs using an agreed upon process and framework. Five general common positions are under discussion in this fiscal year. Simplicity in Design, Software Common Cause Failures, Software Tools, Data communication, Verification and Validation throughout the life cycle of safety systems using digital computers. In addition, the technical evaluation of standards of the Japan Electric Association about digital system for safety was made to support NISA (Nuclear and Industrial Safety Agency). (author)

  2. Study on post-earthquake plant evaluation and communication (Annual safety research report, JFY 2011)

    International Nuclear Information System (INIS)

    2012-01-01

    The aims of this study are to establish a post-earthquake plant evaluation method and to develop a communication system for the improving seismic safety regulations as well as encouraging public communication. The Miyagiken-oki earthquake in 2005, Onagawa Nuclear Power Plant shut down automatically. Subsequently, JNES started development of post-earthquake plant evaluation and communication system based on the experience of the cross-check analysis for Onagawa Nuclear Power Plant. The Niigata-ken Chuetsu-oki Earthquake in 2007, the plant situation was not transmitted promptly. The loss of information sharing between local community and related organizations caused the public anxiety. The importance of plant information transmission as well as seismic information gathering were recognized. The proposal for the solution of the information issues were performed by government committee, In this study the evaluation method for soundness of the main structure and equipment after earthquake event were updated. Moreover, information dissemination to the public and transparent communication methodology was examined by the Industry-Academia-Government cooperation in the Kashiwazaki-Kariwa region. (author)

  3. Study on post-earthquake plant evaluation and communication (Annual safety research report, JFY 2010)

    International Nuclear Information System (INIS)

    Iijima, Toru; Taoka, Hideto; Yamada, Hiroyuki; Sano, Kyoko

    2011-01-01

    The aims of this study are to establish a post-earthquake plant evaluation method and to develop a communication system for the improving seismic safety regulations as well as encouraging public communication. The Miyagiken-oki earthquake in 2005, Onagawa Nuclear Power Plant shut down automatically. Subsequently, JNES started development of post-earthquake plant evaluation and communication system based on the experience of the cross-check analysis for Onagawa Nuclear Power Plant. The Niigata-ken Chuetsu-oki Earthquake in 2007, the plant situation was not transmitted promptly. The loss of information sharing between local community and related organizations caused the public anxiety. The importance of plant information transmission as well as seismic information gathering were recognized. The proposal for the solution of the information issues were performed by government committee. In this study, the evaluation method for soundness of the main structure and equipment after earthquake event were updated. Moreover, procedure of the post-earthquake plant soundness evaluation and multi-functional seismic information system were developed. In addition, the implementation strategy of the easy-to -understand information dissemination to the public and transparent communication methodology was examined by the Industry-Academia-Government cooperation in the Kashiwazaki-Kariwa region. (author)

  4. Memo on Some Target of Previous Meeting in 2004 and Now

    International Nuclear Information System (INIS)

    Shibata, Heki

    2014-01-01

    The necessity of deep borehole observation was pointed out in a 2002 WS entitled 'Physics of Active Faults' organized by USGS and NIED, and discussion on the utilization of deep borehole observation for design basis ground motion development was then was deepened at the 2004 OECD/NEED Tsukuba WS. In addition to this study history, a series of WSs on Seismic Observation in Deep Boreholes and its Application organized by OECD, IAEA and JNES was planned. The author also explained that at the first SODB WS, he expected deep borehole observation to be used to observe the activity of specific faults with high accuracy, to detect the detailed structure of those specific faults, and to estimate the asperity distribution in order to establish a practical approach to design basis earthquakes for nuclear power plant design. Recently, however, he has come to think that SODB will help find hidden faults and help observe the conditions of old faults. He also mentioned that he believes that in the future SODB can be used for re-activity evaluation of tertiary faults and evaluation of the movement of local fracture zones

  5. Multi-scale analysis of deformation behavior at SCC crack tip (2). (Contract research)

    International Nuclear Information System (INIS)

    Kaji, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Hayakawa, Masao; Nagashima, Nobuo

    2007-03-01

    This report describes a result of the research conducted by the Japan Atomic Energy Agency and the National Institute for Materials Science under contract with Japan Nuclear Energy Safety Organization (JNES) that was concerned with a multi-scale analysis of plastic deformation behavior at the crack tip of stress corrosion cracking (SCC). The research was carried out to evaluate the validity of the SCC growth data acquired in the intergranular SCC (IGSCC) project based on a mechanistic understanding of SCC. For the purpose, in this research, analyses of the plastic deformation behavior and microstructure around the crack tip were performed in a nano-order scale. The hardness measured in nano, meso and macro scales was employed as a common index of the strength, and the essential data necessary to understand the SCC propagation behavior were acquired and analyzed that are mainly a size of plastic deformation region and a microstructural information in the region, e.g. data of crystallografy, microscopic deformation and dislocations at the inside of grains and grain boundaries. In this year, we analyzed the state of plastic deformation region at the crack tip of IGSCC under various conditions and investigated relationship between crack growth behavior and stress intensity factor. Especially, we investigated in detail about two different hardened specimens used in the SCC growth tests in the IGSCC project. (J.P.N.)

  6. Pursuit of new methodology on risk communication - Research assistance program by open application

    International Nuclear Information System (INIS)

    Konoa, N.; Takeshima, K.

    2004-01-01

    In the latter half of 1990s a series of incidents occurred in Japan such as MOX fuel inspection data falsification, Monju fast breeder reactor sodium leakage accident, Tokai nuclear fuel plant (JCO) criticality accident and so on. It is thought that existing measures based on nuclear technology are not well cope with those incidents and another countermeasure utilizing new methodology of cultural and social sciences was keenly felt by both administration agencies and nuclear industries. Above all, the technique such as risk communication to inform the influence of trouble correctly and convincingly to the residents and mass media and to prevent the harm due to rumor is obviously inevitable. Based on these circumstances, Japanese NISA (The Nuclear and Industrial Safety Agency) initiated in 2002FY new project by open application in the field of cultural and social sciences, and risk communication was one of the principal subject of study. Up to now, 6 risk communication studies are currently in progress. The project was taken over from NISA to JNES (Incorporated Administrative Agency Japan Nuclear Energy Safety Organization) since 2004FY. This paper shows the overall structure of the project and the outline of the running studies. (author)

  7. Preparation of safety regulatory requirements for new technology like digital system

    International Nuclear Information System (INIS)

    2012-01-01

    The current regulatory requirements on digital instrumentation and control system have been reviewed by JNES, considering international trend discussed in DICWG of MDEP. MDEP DICWG held in OECD/NEA gives the opportunity to identify the convergence of applicable standards. The working group's activities include: identifying and prioritising the member countries' challenges, practices, and needs regarding standards and regulatory guidance on digital instrumentation and control; identifying areas of importance and needs for convergence of existing standards and guidance or development of new standards; sharing of information; and identifying common positions among the member countries for areas of particular importance and need. The DICWG drafted common positions on specific issues which are based on the existing standards, national regulatory guidance, best practices, and group inputs using an agreed process and framework. The following two general common positions are discussed and to be issued in this fiscal year. Verification and Validation throughout the life cycle of safety systems using digital computers. The Impact of Cyber Security Features on Digital I and C Safety Systems. (author)

  8. Human retroviruses and AIDS 1997

    Energy Technology Data Exchange (ETDEWEB)

    Korber, B.; Foley, B.; Leitner, T. [eds.] [and others

    1997-12-01

    This compendium is the result of an effort to compile, organize, and rapidly publish as much relevant molecular data concerning the human immunodeficiency viruses (HIV) and related retroviruses as possible. The scope of the compendium and database is best summarized by the four parts that it comprises: (1) Nucleic Acid Alignments, (2) Amino Acid Alignments, (3) Reviews and Analyses, and (4) Related Sequences. Information within all the parts is updated throughout the year on the Web site, http://hiv-web.lanl.gov. This year we are not including floppy diskettes as the entire compendium is available both at our Web site and at our ftp site. If you need floppy diskettes please contact either Bette Korber (btk@t10.lanl.gov) or Kersti Rock (karm@t10.lanl.gov) by email or fax ((505) 665-4453). While this publication could take the form of a review or sequence monograph, it is not so conceived. Instead, the literature from which the database is derived has simply been summarized and some elementary computational analyses have been performed upon the data. Interpretation and commentary have been avoided insofar as possible so that the reader can form his or her own judgments concerning the complex information. The exception to this are reviews submitted by experts in areas deemed of particular and basic importance to research involving AIDS viral sequence information. These are included in Part III, and are contributed by scientists with particular expertise in the area of interest. In addition to the general descriptions below of the parts of the compendium, the user should read the individual introductions for each part.

  9. International Benchmark based on Pressurised Water Reactor Sub-channel and Bundle Tests. Volume III: Departure from Nucleate Boiling

    International Nuclear Information System (INIS)

    Rubin, Adam; Avramova, Maria; Velazquez-Lozada, Alexander

    2016-03-01

    This report summarised the second phase of the Nuclear Energy Agency (NEA) and the Nuclear Regulatory Commission (NRC) Benchmark Based on NUPEC PWR Sub-channel and Bundle Tests (PSBT), which was intended to provide data for the verification of Departure from Nucleate Boiling (DNB) prediction in existing thermal-hydraulics codes and provide direction in the development of future methods. This phase was composed of three exercises; Exercise 1: fluid temperature benchmark, Exercise 2: steady-state rod bundle benchmark and Exercise 3: transient rod bundle benchmark. The experimental data provided to the participants of this benchmark is from a series of void measurement tests using full-size mock-up tests for both BWRs and PWRs. These tests were performed from 1987 to 1995 by the Nuclear Power Engineering Corporation (NUPEC) in Japan and made available by the Japan Nuclear Energy Safety Organisation (JNES) for the purposes of this benchmark, which was organised by Pennsylvania State University. Nine institutions from seven countries participated in this benchmark. Nine different computer codes were used in Exercise 1, 2 and 3. Among the computer codes were porous media, sub-channel and systems thermal-hydraulic code. The improvement between FLICA-OVAP (sub-channel) and FLICA (sub-channel) was noticeable. The main difference between the two was that FLICA-OVAP implicitly assigned flow regime based on drift flux, while FLICA assumes single phase flows. In Exercises 2 and 3, the codes were generally able to predict the Departure from Nucleate Boiling (DNB) power as well as the axial location of the onset of DNB (for the steady-state cases) and the time of DNB (for the transient cases). It was noted that the codes that used the Electric-Power-Research- Institute (EPRI) Critical-Heat-Flux (CHF) correlation had the lowest mean error in Exercise 2 for the predicted DNB power

  10. Evaluation of durability of SSCs injected with seawater

    International Nuclear Information System (INIS)

    2012-01-01

    At the units 1 to 4 in the Fukushima Daiichi Nuclear Power Plant, seawater was injected into reactor pressure vessels and spent fuel pools in order to cool down nuclear fuel is after the disaster of the 2011 off the Pacific Coast of Tohoku Earthquake and Tsunami. Therefore, for fuel cladding tubes exposed to seawater and piping items to pour seawater into a nuclear reactor, it was necessary to evaluate structural integrity under the seawater environment. And then, JNES carried out the safety research of 'Evaluation of Durability of SSCs injected with Seawater' in FY2011. The contents and the results obtained from the search are as follows; (1) For the pipes and nuclear reactor containment vessels, corrosion tests under high temperature seawater at 50degC and 80degC were carried out for the carbon steel that corrosion resistance was less. The data of relationship between a dipping time upto 1,500h and a corrosion rate were obtained as parameters at chloride ion (CI - ) content and the temperature of the seawater. As the results, the corrosion rate was almost 0.1 mm/y for the carbon steel SGV480. No significant influence of CT - content and the temperature of the seawater was confirmed. (2) Corrosion tests were carried out to obtain the relations of time and corrosion under different CI - content conditions for the simulated fuel rod specimens in seawater at 90degC for durations upto 1,200h. As the results, very little corrosion was observed on Zry-2 cladding tube. Brown rust was slightly appeared on the nut made of stainless steel and the lower tie plate made of cast stainless steel. Thinning and corrosion pit were not observed. (author)

  11. Toward an integrated system concept for monitoring and evaluation of safety culture

    International Nuclear Information System (INIS)

    Makino, Maomi; Sakaue, Takeharu

    2004-01-01

    The concept of ''nuclear safety culture'' has been advocated and has been much discussed internationally by INSAG (The International Nuclear Safety Advisory Group) under IAEA (the International Atomic Energy Agency) and other institutions since Chernobyl accident. On the safety front, Japan had maintained an excellent track record in nuclear power operations throughout the 1990s. However, there have been a series of new type of problems strongly implying degradation of safety culture, e.g., Monju accident, fire and explosion accident at an Asphalt Solidification Process Facility at Tokai, falsification of annealing data at nuclear power plants (NPP), another data falsification for transport cask of spent fuel and JCO criticality accident. Then the TEPCO (Tokyo Electric Power Company) issue was revealed in 2002. Triggered by this issue, the Nuclear and Industrial Safety Agency (NISA) has been implementing a variety of improvements, one of which was the establishment of a study group in 2003, which invited experts from other fields as well as from nuclear-related industries, to study on how to implement safety culture sufficiently and possible recommendations. Subjects such as the followings piled in the study report will indicate leading keys in case it is going to realize such efforts: ''Foundation of safety culture is a quality management'' and ''Realistic and scientific technique is necessary for the evaluation of safety culture''. In order to respond to these requests, JNES have been advancing the development toward an Integrated System Concept for Monitoring and Evaluation of Safety Culture. This paper describes the outline of the study results reported by the study group and then introduces one of subsystems, SCEST, structuring the integrated system concept for Monitoring and Evaluation of Safety Culture. (author)

  12. Contamination of cars and exposure dose to drivers traveling through the Route 6 in the restricted area

    International Nuclear Information System (INIS)

    Kawakami, Hiroto; Sasaki, Satoru; Shimomura, Masanori; Takano, Hitoshi; Hayashi, Hiroki; Inoue, Ryo; Yamada, Norikazu

    2012-05-01

    Traffic on the Route 6 will increase after the revision of evacuation area and restricted area. At the request of the Local Nuclear Emergency Response Headquarters established in Fukushima Prefecture, Japan Nuclear Energy Safety Organization (JNES) has surveyed the effect on cars and drivers traveling through the Route 6 in the restricted area as listed bellow. (1) Investigation of contamination of cars traveling through the Route 6. (2) Investigation of exposure dose of drivers traveling through the Route 6. The maximum contamination at the surface of tires and tire-houses of cars traveling through the Route 6 is estimated to be 2 Bq/cm"2 (this concentration is correspond to 470 cpm). The external exposure dose of drivers will be about 4 μSv when they run through the restricted area at a pace of 40 km/h. The internal exposure dose will be small because of the low radioactive concentration in the air. It is important not to stay long in high radiation areas to prevent unnecessary exposure. The main source of the contamination is sand cloud thrown up by the wheels. Though, the radioactivity of the sand cloud is proportional to the surface concentration of roads and dose rate of each area, contamination level by the sand cloud will remain low level. Significant contamination is likely to be caused by running on the soil. So, it is important not to run on the soil on the local road around the Route 6 or road shoulder of the Route 6. It is recommended to wash tires and tire-houses when accidentally run on the soil. (author)

  13. A Sensitivity Study for an Evaluation of Input Parameters Effect on a Preliminary Probabilistic Tsunami Hazard Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Rhee, Hyun-Me; Kim, Min Kyu; Choi, In-Kil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Sheen, Dong-Hoon [Chonnam National University, Gwangju (Korea, Republic of)

    2014-10-15

    The tsunami hazard analysis has been based on the seismic hazard analysis. The seismic hazard analysis has been performed by using the deterministic method and the probabilistic method. To consider the uncertainties in hazard analysis, the probabilistic method has been regarded as attractive approach. The various parameters and their weight are considered by using the logic tree approach in the probabilistic method. The uncertainties of parameters should be suggested by analyzing the sensitivity because the various parameters are used in the hazard analysis. To apply the probabilistic tsunami hazard analysis, the preliminary study for the Ulchin NPP site had been performed. The information on the fault sources which was published by the Atomic Energy Society of Japan (AESJ) had been used in the preliminary study. The tsunami propagation was simulated by using the TSUNAMI{sub 1}.0 which was developed by Japan Nuclear Energy Safety Organization (JNES). The wave parameters have been estimated from the result of tsunami simulation. In this study, the sensitivity analysis for the fault sources which were selected in the previous studies has been performed. To analyze the effect of the parameters, the sensitivity analysis for the E3 fault source which was published by AESJ was performed. The effect of the recurrence interval, the potential maximum magnitude, and the beta were suggested by the sensitivity analysis results. Level of annual exceedance probability has been affected by the recurrence interval.. Wave heights have been influenced by the potential maximum magnitude and the beta. In the future, the sensitivity analysis for the all fault sources in the western part of Japan which were published AESJ would be performed.

  14. A test to evaluation non-linear soil structure interaction

    International Nuclear Information System (INIS)

    Hagiwara, T.; Kitada, Y.

    2005-01-01

    JNES is planning a new project to study non-linear soil-structure interaction (SSI) effect under large earthquake ground motions equivalent to and/or over a design earthquake ground motion of S2. Concerning the SSI test, it is pointed out that handling of the scale effect of the specimen taking into account the surrounding soil on the earthquake response evaluation to the actual structure is essential issue for the scaled model test. Thus, for the test, the largest specimen possible and the biggest input motion possible are necessary. Taking into account the above issues, new test methodology, which utilizes artificial earthquake ground motion, is considered desirable if it can be performed at a realistic cost. With this motivation, we have studied the test methodology which applying blasting power as for a big earthquake ground motion. The information from a coalmine company in the U.S.A. indicates that the works performed in the surface coalmine to blast a rock covering a coal layer generates a big artificial ground motion, which is similar to earthquake ground motion. Application of this artificial earthquake ground motion for the SSI test is considered very promising because the blasting work is carried out periodically for mining coal so that we can apply artificial motions generated by the work if we construct a building model at a closed point to the blasting work area. The major purposes of the test are to understand (a) basic earthquake response characteristics of a Nuclear Power Plant (NPP) reactor building when a large earthquake strikes the NPP site and (b) nonlinear characteristics of SSI phenomenon during a big earthquake. In the paper of ICONE-13, we will introduce the test method and basic characteristics of measured artificial ground motions generated by the blasting works on an actual site. (authors)

  15. Safety study of fire protection for nuclear fuel cycle facility

    International Nuclear Information System (INIS)

    2013-01-01

    Insufficiencies in the fire protection system of the nuclear reactor facilities were pointed out when the fire occurred due to the Niigata prefecture-Chuetsu-oki Earthquake in July, 2007. This prompted the revision of the fire protection safety examination guideline for nuclear reactors as well as commercial guidelines. The commercial guidelines have been endorsed by the regulatory body. Now commercial fire protection standards for nuclear facilities such as the design guideline and the management guideline for protecting fire in the Light Water Reactors (LWRs) are available, however, those to apply to the nuclear fuel cycle facilities such as mixed oxide fuel fabrication facility (MFFF) have not been established. For the improvement of fire protection system of the nuclear fuel cycle facilities, the development of a standard for the fire protection, corresponding to the commercial standard for LWRs were required. Thus, Japan Nuclear Energy Safety Organization (JNES) formulated a fire protection guidelines for nuclear fuel cycle facilities as a standard relevant to the fire protection of the nuclear fuel cycle facilities considering functions specific to the nuclear fuel cycle facilities. In formulating the guidelines, investigation has been conduced on the commercial guidelines for nuclear reactors in Japan and the standards relevant to the fire protection of nuclear facilities in USA and other countries as well as non-nuclear industrial fire protection standards. The guideline consists of two parts; Equipments and Management, as the commercial guidances of the nuclear reactor. In addition, the acquisition of fire evaluation data for a components (an electric cabinet, cable, oil etc.) targeted for spread of fire and the evaluation model of fire source were continued for the fire hazard analysis (FHA). (author)

  16. Seismic PRA of a BWR plant

    International Nuclear Information System (INIS)

    Nishio, Masahide; Fujimoto, Haruo

    2014-01-01

    Since the occurrence of nuclear power plant accidents in the Fukushima Daichi nuclear power station, the regulatory framework on severe accident (SA) has been discussed in Japan. The basic concept is to typify and identify the accident sequences leading to core/primary containment vessel (PCV) damage and to implement SA measures covering internal and external events extensively. As Japan is an earthquake-prone country and earthquakes and tsunami are important natural external events for nuclear safety of nuclear power plants, JNES performed the seismic probabilistic risk assessment (PRA) on a typical nuclear power plant and evaluated the dominant accident sequences leading to core/PCV damage to discuss dominant scenarios of severe accident (SA). The analytical models and the results of level-1 seismic PRA on a 1,100 MWe BWR-5 plant are shown here. Seismic PRA was performed for a typical BWR5 plant. Initiating events with large contribution to core damage frequency are the loss of all AC powers (station blackout) and the large LOCA. The top of dominant accident sequences is the simultaneous occurrence of station blackout and large LOCA. Important components to core damage frequency are electric power supply equipment. It needs to keep in mind that the results are influenced on site geologic characteristic to a greater or lesser. In the process of analysis, issues such as conservative assumptions related to damages of building or structure and success criteria for excessive LOCA are left to be resolved. These issues will be further studied including thermal hydric analysis in the future. (authors)

  17. Fatigue life evaluation method of austenitic stainless steel in PWR water

    International Nuclear Information System (INIS)

    Sakaguchi, Katsumi; Nomura, Yuichiro; Suzuki, Shigeki; Kanasaki, Hiroshi; Higuchi, Makoto

    2006-09-01

    It is known that the fatigue life in elevated temperature water is substantially reduced compared with that in the air. The fatigue life reduction has been investigated experimentally in EFT project of Japan Nuclear Energy Safety Organization (JNES) to evaluate the environmental effect on fatigue life. Many tests have been done for carbon, low alloy, stainless steels and nickel-based alloy under the various conditions. In this paper, the results of the stainless steel in simulated PWR water environments were reported. Fatigue life tests in simulated PWR environments were carried out and the effect of key parameters on fatigue life reduction was examined. The materials used in this study were base and weld metal of austenitic stainless steel SS316, weld metal of SS304 and the base and aged metal of the duplex stainless steel SCS14A. In order to evaluate the effects of stain amplitude, strain rate, strain ratio, temperature, aging, water flow rate and strain holding time, many fatigue tests were examined. In transient condition in an actual plant, however, such parameters as temperature and strain rate are not constant. In order to evaluate fatigue damage in actual plant on the basis of experimental results under constant temperature and strain rate condition, the modified rate approach method was developed. Various kinds of transient have to be taken into account of in actual plant fatigue evaluation, and stress cycle of several ranges of amplitude has to be considered in assessing damage from fatigue. Generally, cumulative usage factor is applied in this type of evaluation. In this study, in order to confirm the applicability of modified rate approach method together with cumulative usage factor, fatigue tests were carried out by combining stress cycle blocks of different strain amplitude levels, in which strain rate changes in response to temperature in a simulated PWR water environment. Consequently, fatigue life could be evaluated with an accuracy of factor of 3

  18. Working material. IAEA seismic safety of nuclear power plants. International workshop on lessons learned from strong earthquake

    International Nuclear Information System (INIS)

    2008-08-01

    The International Workshop on Lessons Learned from Strong Earthquake was held at Kashiwazaki civic plaza, Kashiwazaki, Niigata-prefecture, Japan, for three days in June 2008. Kashiwazaki-Kariwa NPP (KK-NPP) is located in the city of Kashiwazaki and the village of Kariwa, and owned and operated by Tokyo Electric Power Company Ltd. (TEPCO). After it experienced the Niigata-ken Chuetsu-oki earthquake in July 2007, IAEA dispatched experts' missions twice and held technical discussions with TEPCO. Through such activities, the IAEA secretariat and experts obtained up-dated information of plant integrity, geological and seismological evaluation and developments of the consultation in the regulatory framework of Japan. Some of the information has been shared with the member states through the reports on findings and lessons learned from the missions to Japan. The international workshop was held to discuss and share the information of lessons learned from strong earthquakes in member states' nuclear installations. It provided the opportunity for participants from abroad to share the information of the recent earthquake and experience in Japan and to visit KK-NPP. And for experts in Japan, the workshop provided the opportunity to share the international approach on seismic-safety-related measures and experiences. The workshop was organised by the IAEA as a part of an extra budgetary project, in cooperation with OECD/NEA, hosted by Japanese organisations including Nuclear and Industrial Safety Agency (NISA), Nuclear Safety Commission (NSC), and Japan Nuclear Energy Safety Organization (JNES). The number of the workshop participants was 70 experts from outside Japan, 27 countries and 2 international organisations, 154 Japanese experts and 81 audience and media personnel, totalling to 305 participants. The three-day workshop was open to the media including the site visit, and covered by NHK (the nation's public broadcasting corporation) and nation-wide and local television

  19. Report on the state of radiation contamination in disaster waste

    International Nuclear Information System (INIS)

    Onishi, Yuko; Sasaki, Satoru; Yamada, Norikazu; Kawasaki, Satoru

    2011-09-01

    Fukushima Prefecture faces extreme difficulties in disposing of waste generated from the tsunami disaster (hereinafter referred to as disaster waste) and contaminated with radioactive material released from the crippled Fukushima Dai-ichi Nuclear Power Station. Although the waste should be treated according to the level of radioactivity, there are only air dose rates and radionuclide analyses of soil due to monitoring around the Fukushima Dai-ichi Nuclear Power Station and there has been no information on the radioactivity concentration of the disaster waste. The radioactivity concentration of the disaster waste was investigated by sampling measurement and in-situ Ge measurement at 20 temporary disaster waste storages in Fukushima Prefecture excluding the evacuation zone and 'deliberate evacuation zone.' JNES carried out this investigation upon a request from the Nuclear and Industrial Safety Agency. The investigation revealed that the measured radioactivity concentrations of the disaster waste lumps were enveloped within the soil monitoring readings in Fukushima Prefecture and also within a correlated curve between the air dose rates obtained from air dose rate readings around the disaster waste and the radioactivity concentrations of it. With these correlation curves, the radioactivity concentration of the disaster waste is estimated to be less than 8,000 Bq/kg at almost all places in the affected area excluding the evacuation zone and 'deliberate evacuation zone.' Measurements by in-situ Ge showed that the radioactivity of the disaster waste which had been expected to be more than 8,000 Bq/kg was less than 8,000 Bq/kg. (author)

  20. A 3D analysis of spatial relationship between geological structure and groundwater profile around Kobe City, Japan: based on ARCGIS 3D Analyst.

    Science.gov (United States)

    Shibahara, A.; Tsukamoto, H.; Kazahaya, K.; Morikawa, N.; Takahashi, M.; Takahashi, H.; Yasuhara, M.; Ohwada, M.; Oyama, Y.; Inamura, A.; Handa, H.; Nakama, J.

    2008-12-01

    Kobe city is located on the northern side of Osaka sedimentary basin, Japan, containing 1,000-2,000 m thick Quaternary sediments. After the Hanshin-Awaji Earthquake (January 17, 1995), a number of geological and geophysical surveys were conducted in this region. Then high-temperature anomaly of groundwater accompanied with high Cl concentration was detected along fault systems in this area. In addition, dissolved He in groundwater showed nearly upper mantle-like 3He/4He ratio, although there were no Quaternary volcanic activities in this region. Some recent studies have assumed that these groundwater profiles are related with geological structure because some faults and joints can function as pathways for groundwater flow, and mantle-derived water can upwell through the fault system to the ground surface. To verify these hypotheses, we established 3D geological and hydrological model around Osaka sedimentary basin. Our primary goal is to analyze spatial relationship between geological structure and groundwater profile. In the study region, a number of geological and hydrological datasets, such as boring log data, seismic profiling data, groundwater chemical profile, were reported. We converted these datasets to meshed data on the GIS, and plotted in the three dimensional space to visualize spatial distribution. Furthermore, we projected seismic profiling data into three dimensional space and calculated distance between faults and sampling points, using Visual Basic for Applications (VBA) scripts. All 3D models are converted into VRML format, and can be used as a versatile dataset on personal computer. This research project has been conducted under the research contract with the Japan Nuclear Energy Safety Organization (JNES).

  1. Aging Depth Test of Rubber Blocks by Accelerated Thermal Oxidation Test

    International Nuclear Information System (INIS)

    Park, Junhee; Choun, Young-Sun; Kim, Min Kyu

    2015-01-01

    In this study, the accelerated thermal oxidation tests of rubber block were performed to investigate the aging depth of rubber bearing. From the tests, it was found the critical aging depth in rubber block. Also the property variation of rubber was investigated along the depth. The deterioration pattern from the aging depth tests was found from surface to inside and the critical aging depth was to be about 10 mm. The analytical model for rubber bearing with aging can be developed based on the relationship between the property variation and aging depth investigated from this study. The mechanical properties of rubber bearings were changed with time. Because the aging effect of rubber material was generally higher than that of other structure materials it is needed that the aging properties of seismically isolators should be evaluated to ensure the safety of seismically isolated nuclear power plants (NPPs) over the lifetime. NRC and ASCE required the tests of seismically isolators for investigating the aging properties. JNES also required the seismic response analysis for the seismically isolated NPPs when the properties of seismically isolators were extremely changed. If the aging properties of seismically isolators such as rubber bearings are evaluated by analysis the analytical model of seismically isolators should be developed considering aging effect of rubber material. From the previous research, it was reported that the behavior of aged rubber material mainly affected by temperature and oxidation. The material properties between surface and inside can be different by the oxidation of rubber. Therefore, the aging depth should be investigated for exactly evaluating the seismic behavior of aged rubber bearing. The aging depth of rubber baring was not influenced by the size of seismically isolators but environment condition. Therefore, the detail analysis considering aging depth was not required for NPPs with large seismically isolators. But the seismic response

  2. Executive Summary

    International Nuclear Information System (INIS)

    2014-01-01

    and JNES), Sweden (Studsvik Nuclear AB) and USA (SNL), independent experts acting on behalf of the safety regulatory body of Germany (BAM and TUV), operators from France (AREVA) and Germany (GNS), and of the IAEA. The papers discussed the impact of extending storage periods, operational and licensing experiences in storage facilities, results of experiments, and identified necessary R and D to confirm safety of fuel and cask during the long-term storage. For each session, a summary of each paper is given. This part of the proceedings ends with the General Conclusions and Recommendations derived from the workshop

  3. Imaging inhomogeneous seismic velocity structure in and around the fault plane of the 2008 Iwate-Miyagi, Japan, Nairiku Earthquake (M7.2) - spatial variation in depth of seismic-aseismic transition and possible high-T/overpressurized fluid distribution

    Science.gov (United States)

    Okada, T.; Umino, N.; Hasegawa, A.; 2008 Iwate-Miyagi Nairiku Earthquake, G. O.

    2008-12-01

    -velocity zones in the lower crust might be caused by high temperature upwelling flow of fluid originating from the mantle wedge. The present observation supports the hypothesis by Hasegawa et al. (2005) that anelastic deformation of the crust weakened by fluid forms the strain concentration zone and promotes the occurrence of large shallow inland earthquakes. We used data from JMA, Hi-net/NIED, NAO-Mizusawa and TITECH. We also used data from JNES. This work was conducted under the support of Grant-in-Aid for Special Purposes, MEXT, Japan. We thank Prof. Cliff Thurber and Dr. Haijiang Zhang for providing their programs and valuable discussions.

  4. The study on the non-linear soil structure interaction for nuclear power plants

    International Nuclear Information System (INIS)

    Tetsuya Hagiwara; Yoshio Kitada

    2005-01-01

    1. Introduction: JNES is planning a new project to study non-linear soil-structure interaction (SSI) effect under large earthquake ground motions equivalent to and/or over a design earthquake ground motion of S2(The extreme design earthquake). Concerning the SSI test, it is pointed out that handling of the scale effect of the specimen together with the surrounding soil on the earthquake response evaluation of the actual structure is essential issue for the scaled model test. Thus, for the test, the largest specimen possible and the biggest input motion possible are necessary. Taking into account the above issues, new test methodology, which utilizes artificial earthquake ground motion, is considered desirable if it can be performed at a realistic cost. Under this motivation, we have studied the test methodology which applying blasting power as for a big earthquake ground motion. The information from a coal mine company in the U.S.A. indicates that the works performed in the surface coal mine to blast a rock covering a coal layer generates a big artificial ground motion, which is similar to earthquake ground motion. Application of this artificial earthquake ground motion for the SSI test is considered very promising because the blasting work is carried out periodically for mining coal so that we can apply artificial motions generated by the work if we construct a building model at a closed point to the blasting work area. The major purposes of the test will be to understand (a) basic earthquake response characteristics of a Nuclear Power Plant (NPP) reactor building when a large earthquake strikes the NPP site and (b) nonlinear characteristics of SSI phenomenon during a big earthquake. In the paper, we introduce the test method and basic characteristics of measured artificial ground motions generated by the blasting works on an actual site. 2. Conclusion: It was confirmed that the artificial ground motions generated by blasting works have enough acceleration level

  5. An overview on development of safety culture of regulatory body in Korea

    International Nuclear Information System (INIS)

    Yoon, Myunghyun; Choi, Young Sung; Yi, Kyungjoo

    2015-01-01

    Fukushima accident revealed not only licensees but also regulatory bodies' (RBs) establishment of robust safety culture (SC) is crucial to implement effective safety regulation. Result of the IAEA IRRS held in 2011 required regulatory body in Korea to make improvement measure for the enhancement of safety culture of regulatory body (SCRB). Compared to works done to assess SC focused on working organizations of nuclear industry, not enough attention has been paid to assess the RBs. To achieve this goal, long-term comprehensive drive plan has to be made. The IAEA is putting great effort to establish and enhance SC in RBs. OECD/NEA CNRA is planning to produce Green Booklet on SCRB for regulatory guidance. SCRB is an organization's culture, RBs ultimately has to possess in order to assure secure use of nuclear energy. An organization's culture emerges from, and is manifested in, the interplay of its members' emotion, cognition, attitudes, behaviors and interaction patterns. As a result of this mechanism, organizational structures and culture influence individual's attitude and behavior when entered into a situation. Each organization has its strengths and weakness in SC. Safety culture defective components of the Fukushima accident was analyzed by JNES in 2012. According to the casual factors indicated in the investigation report, Nuclear Regulatory Organizations (NROs) of Korea also had weakness of the SCRB in terms of questioning attitude, continuous learning, issue identification and resolution and safety leadership. It doesn't have to be same but necessary for both NSSC and KINS to be consistent in building SC traits to carry out a coherent policy with synergy effect. NROs should communicated and convey consistent message to the stakeholders. Not limited to development of SCRB itself, influence of SCRB on licensee's SC is recommended for further study. Also, what behaviors are expected to make positive effects and whether they can

  6. Basic concept of fuel safety design and assessment for sodium-cooled fast reactor

    International Nuclear Information System (INIS)

    Nakae, Nobuo; Baba, Toshikazu; Kamimura, Katsuichiro

    2013-03-01

    'Philosophy in Safety Evaluation of Fast Breeder Reactors' was published as a guideline for safety design and safety evaluation of Sodium-Cooled Fast Reactor in Japan. This guideline points out that cladding creep and swelling due to internal pressure should be taken into account since the fuel is used under high temperature and high burnup, and that fuel assembly deformation and the prevention from coolant channel blockage should be taken into account in viewpoints of nuclear and thermal hydraulic design. However, the requirements including their criteria and evaluation items are not described. Two other domestic guidelines related to core design are applied for fuel design of fast reactor, but the description is considered to not be enough to practically use. In addition, technical standard for nuclear fuel used in power reactors is also applied for fuel inspection. Therefore, the technical standard and guideline for fuel design and safety evaluation are considered to be very important issue for nuclear safety regulation. This document has been developed according to the following steps: The guidelines and the technical standards, which are prepared in foreign countries and international organization, were reviewed. The technical background concerning fuel design and safety evaluation for fast reactor was collected and summarized in the world wide scale. The basic concept of fuel safety design and assessment for sodium-cooled fast reactor was developed by considering a wide range of views of the specialists in Japan. In order to discuss the content with foreign specialists IAEA Consultancy Meetings have been held on January, 2011 and January, 2012. The participants of the meeting came from USA, UK, EC, India, China and South Korea. The specialists of IAEA and JNES were also joined. Although this document is prepared for application to 'Monju'(prototype LMFR), it may be applied to experimental, demonstration and commercial types of LMFR after revising it by taking

  7. Level-1 seismic probabilistic risk assessment for a PWR plant

    International Nuclear Information System (INIS)

    Kondo, Keisuke; Nishio, Masahide; Fujimoto, Haruo; Ichitsuka, Akihiro

    2014-01-01

    In Japan, revised Seismic Design Guidelines for the domestic light water reactors was published on September 19, 2006. These new guidelines have introduced the purpose to confirm that residual risk resulting from earthquake that exceeds the design limit seismic ground motion (Ss) is sufficiently small, based on the probabilistic risk assessment (PRA) method, in addition to conventional deterministic design base methodology. In response to this situation, JNES had been working to improve seismic PRA (SPRA) models for individual domestic light water reactors. In case of PWR in Japan, total of 24 plants were grouped into 11 categories to develop individual SPRA model. The new regulatory rules against the Fukushima dai-ichi nuclear power plants' severe accidents occurred on March 11, 2011, are going to be enforced in July 2013 and utilities are necessary to implement additional safety measures to avoid and mitigate severe accident occurrence due to external events such as earthquake and tsunami, by referring to the results of severe accident study including SPRA. In this paper a SPRA model development for a domestic 3-loop PWR plant as part of the above-mentioned 11 categories is described. We paid special attention to how to categorize initiating events that are specific to seismic phenomena and how to confirm the effect of the simultaneous failure probability calculation model for the multiple components on the result of core damage frequency evaluation. Simultaneous failure probability for multiple components has been evaluated by power multiplier method. Then tentative level-1 seismic probabilistic risk assessment (SPRA) has been performed by the developed SPSA model with seismic hazard and fragility data. The base case was evaluated under the condition with calculated fragility data and conventional power multiplier. The difference in CDF between the case of conventional power multiplier and that of power multiplier=1 (complete dependence) was estimated to be

  8. International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests. Volume II: Benchmark Results of Phase I: Void Distribution

    International Nuclear Information System (INIS)

    Rubin, Adam; Avramova, Maria; Velazquez-Lozada, Alexander

    2016-03-01

    This report summarised the first phase of the Nuclear Energy Agency (NEA) and the US Nuclear Regulatory Commission Benchmark based on NUPEC PWR Sub-channel and Bundle Tests (PSBT), which was intended to provide data for the verification of void distribution models in participants' codes. This phase was composed of four exercises; Exercise 1: steady-state single sub-channel benchmark, Exercise 2: steady-state rod bundle benchmark, Exercise 3: transient rod bundle benchmark and Exercise 4: a pressure drop benchmark. The experimental data provided to the participants of this benchmark is from a series of void measurement tests using full-size mock-up tests for both Boiling Water Reactors (BWRs) and Pressurised Water Reactors (PWRs). These tests were performed from 1987 to 1995 by the Nuclear Power Engineering Corporation (NUPEC) in Japan and made available by the Japan Nuclear Energy Safety Organisation (JNES) for the purposes of this benchmark, which was organised by Pennsylvania State University. Twenty-one institutions from nine countries participated in this benchmark. Seventeen different computer codes were used in Exercises 1, 2, 3 and 4. Among the computer codes were porous media, sub-channel, systems thermal-hydraulic code and Computational Fluid Dynamics (CFD) codes. It was observed that the codes tended to overpredict the thermal equilibrium quality at lower elevations and under predict it at higher elevations. There was also a tendency to overpredict void fraction at lower elevations and underpredict it at high elevations for the bundle test cases. The overprediction of void fraction at low elevations is likely caused by the x-ray densitometer measurement method used. Under sub-cooled boiling conditions, the voids accumulate at heated surfaces (and are therefore not seen in the centre of the sub-channel, where the measurements are being taken), so the experimentally-determined void fractions will be lower than the actual void fraction. Some of the best

  9. Summary Record

    International Nuclear Information System (INIS)

    2008-01-01

    The first workshop of the OECD/NRC Benchmark based on NUPEC BWR Full-size Fine-mesh Bundle Tests (BFBT) was held on 4 October 2004. The workshop was hosted by the Japan Nuclear Energy Safety (JNES) Organization. The BFBT Benchmark is sponsored by the US Nuclear Regulatory Commission (NRC), the OECD, and the Nuclear Engineering Program (NEP) of the Pennsylvania State University. The experimental data was produced during a measurement campaign by the NUPEC, Japan, and sponsored by the Japan Ministry of Economy, Trade and Industry (METI). This international benchmark, based on the NUPEC database, encourages advancement in this un-investigated field of two-phase flow theory with very important relevance to the nuclear reactor's safety margins evaluation. Considering the immaturity of the theoretical approach, the benchmark specification is being designed so that it systematically assesses and compares the participants' numerical models on the prediction of detailed void distributions and critical powers. Furthermore, the following points are kept in mind while the benchmark specification is being established. As concerns the numerical model of void distributions, no sound theoretical approach that can be applied to a wide range of geometrical and operating conditions has been developed. In the past decade, experimental and computational technologies have improved tremendously through the study of the two-phase flow structure. Over the next decade, it can be expected that mechanistic approaches will be more widely applied to the complicated two-phase fluid phenomena inside fuel bundles. The development of truly mechanistic models for critical power prediction is currently underway. These models must include elementary processes such as void distributions, droplet deposit, liquid film entrainment, etc. The BFBT benchmark consists of two parts (phases), each part consisting of different exercises: - Phase 1 Void Distribution Benchmark: Exercise 1: Steady-state sub

  10. Improvement of human reliability analysis method for PRA

    International Nuclear Information System (INIS)

    Tanji, Junichi; Fujimoto, Haruo

    2013-09-01

    It is required to refine human reliability analysis (HRA) method by, for example, incorporating consideration for the cognitive process of operator into the evaluation of diagnosis errors and decision-making errors, as a part of the development and improvement of methods used in probabilistic risk assessments (PRAs). JNES has been developed a HRA method based on ATHENA which is suitable to handle the structured relationship among diagnosis errors, decision-making errors and operator cognition process. This report summarizes outcomes obtained from the improvement of HRA method, in which enhancement to evaluate how the plant degraded condition affects operator cognitive process and to evaluate human error probabilities (HEPs) which correspond to the contents of operator tasks is made. In addition, this report describes the results of case studies on the representative accident sequences to investigate the applicability of HRA method developed. HEPs of the same accident sequences are also estimated using THERP method, which is most popularly used HRA method, and comparisons of the results obtained using these two methods are made to depict the differences of these methods and issues to be solved. Important conclusions obtained are as follows: (1) Improvement of HRA method using operator cognitive action model. Clarification of factors to be considered in the evaluation of human errors, incorporation of degraded plant safety condition into HRA and investigation of HEPs which are affected by the contents of operator tasks were made to improve the HRA method which can integrate operator cognitive action model into ATHENA method. In addition, the detail of procedures of the improved method was delineated in the form of flowchart. (2) Case studies and comparison with the results evaluated by THERP method. Four operator actions modeled in the PRAs of representative BWR5 and 4-loop PWR plants were selected and evaluated as case studies. These cases were also evaluated using

  11. Thermal property change of MOX and UO{sub 2} irradiated up to high burnup of 74 GWd/t

    Energy Technology Data Exchange (ETDEWEB)

    Nakae, Nobuo, E-mail: nakae-nobuo@jnes.go.jp [Japan Nuclear Energy Safety Organization (JNES), Toranomon Towers Office, 4-1-28, Toranomon, Minato-ku, Tokyo 105-0001 (Japan); Akiyama, Hidetoshi; Miura, Hiromichi; Baba, Toshikazu; Kamimura, Katsuichiro [Japan Nuclear Energy Safety Organization (JNES), Toranomon Towers Office, 4-1-28, Toranomon, Minato-ku, Tokyo 105-0001 (Japan); Kurematsu, Shigeru; Kosaka, Yuji [Nuclear Development Corporation (NDC), 622-12, Funaishikawa, Tokai-mura, Ibaraki 319-1111 (Japan); Yoshino, Aya; Kitagawa, Takaaki [Mitsubishi Nuclear Fuel Co., LTD. (MNF), 12-1, Yurakucho 1-Chome, Chiyoda-ku, Tokyo 100-0006 (Japan)

    2013-09-15

    Thermal property is important because it controls fuel behavior under irradiation. The thermal property change at high burnup of more than 70 GWd/t is examined. Two kinds of MOX fuel rods, which were fabricated by MIMAS and SBR methods, and one referenced UO{sub 2} fuel rod were used in the experiment. These rods were taken from the pre-irradiated rods (IFA 609/626, of which irradiation test were carried out by Japanese PWR group) and re-fabricated and re-irradiated in HBWR as IFA 702 by JNES. The specification of fuel corresponds to that of 17 × 17 PWR type fuel and the axially averaged linear heat rates (LHR) of MOX rods are 25 kW/m (BOL of IFA 702) and 20 kW/m (EOL of IFA 702). The axial peak burnups achieved are about 74 GWd/t for both of MOX and UO{sub 2}. Centerline temperature and plenum gas pressure were measured in situ during irradiation. The measured centerline temperature is plotted against LHR at the position where thermocouples are fixed. The slopes of MOX are corresponded to each other, but that of UO{sub 2} is higher than those of MOX. This implies that the thermal conductivity of MOX is higher than that of UO{sub 2} at high burnup under the condition that the pellet–cladding gap is closed during irradiation. Gap closure is confirmed by the metallography of the postirradiation examinations. It is understood that thermal conductivity of MOX is lower than that of UO{sub 2} before irradiation since phonon scattering with plutonium in MOX becomes remarkable. A phonon scattering with plutonium decreases in MOX when burnup proceeds. Thus, thermal conductivity of MOX becomes close to that of UO{sub 2}. A reverse phenomenon is observed at high burnup region. The phonon scattering with fission products such as Nd and Zr causes a degradation of thermal conductivity of burnt fuel. It might be speculated that this scattering effect causes the phenomenon and the mechanism is discussed here.

  12. IAEA Issues Report on Mission to Review Japan's Nuclear Power Plant Safety Assessment Process

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: A team of international nuclear safety experts has delivered its report on a mission it conducted from 21-31 January 2012 to review Japan's process for assessing nuclear safety at the nation's nuclear power plants. International Atomic Energy Agency (IAEA) officials delivered the IAEA Mission Report to Japanese officials yesterday and made it publicly available today. Following the 11 March 2011 accident at TEPCO's Fukushima Daiichi Nuclear Power Station, Japan's Nuclear and Industrial Safety Agency (NISA) announced the development of a revised safety assessment process for the nation's nuclear power reactors. At the request of the Government of Japan, the IAEA organized a team of five IAEA and three international nuclear safety experts and visited Japan to review NISA's approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. A Preliminary Summary Report was issued on 31 January. 'The mission report provides additional information regarding the team's recommendations and overall finding that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, Director of the IAEA's Nuclear Installation Safety Division. National safety assessments and their peer review by the IAEA are a key component of the IAEA Action Plan on Nuclear Safety, which was approved by the Agency's Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. The IAEA safety review mission held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety Organization (JNES), and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. In its report delivered today

  13. Exposure doses received from a large scale fire in the restricted area

    International Nuclear Information System (INIS)

    Kawakami, Hiroto; Yamada, Norikazu; Shimomura, Masanori; Ichiki, Takahiko; Kajimoto, Mitsuhiro; Kasahara, Fumio; Tanemura, Munenori; Tsuchino, Susumu; Okubo, Atsushi

    2012-02-01

    At the request of the Local Nuclear Emergency Response Headquarters established in Fukushima Prefecture, Japan Nuclear Energy Safety Organization (JNES) has estimated exposure doses of a fireman and the public during a large scale fire in the restricted area. Data on the contamination of the area were compiled and contaminants deposited on combustible materials in forests were investigated. Estimated doses during a fire vary widely due to the uncertainties and variations in assessment methods, location of the fire (radioactivity in the area, amounts of combustible substance and so on), the scale of the fire (the area of fire spreading), weather conditions (wind direction, wind speed, turbulence type and so on), and the distances of the fireman and the public from the fire. In this reports, effects of these factors were integrated as fire-effect indexes. One can easily obtain exposure doses by multiplying these indexes to the results in each of the assessing conditions. In the severer conditions such as 20 hs of fire spreading area, a contaminant concentration of 6 MBq/m"2 in the area, external dose of a fireman working in the highest air contaminated zone in the vicinity of the fire for 1 hour is estimated to be 50 μSv. If he does not wear a front mask, the internal committed dose is estimated to be 430 μSv. Sum of these doses can rise up to 480 μSv. External and internal doses of the public at the severest location in the distance of 2 km from the fire for 1 hour is estimated to be 5 μSv and 45 μSv respectively, and the sum of these doses is 50 μSv. In the stable conditions where a plume of fire can reach to a longer distance without dispersion, external and internal doses of the public at the 20 km distance from the fire for 1 hour are estimated to be 0.5 μSv and 4.5 μSv respectively, and the sum of them is less than 5 μSv. Though the total exposure dose will not exceed 1 mSv even if the fire lingers for some days, monitoring of radiation is important in

  14. An overview on development of safety culture of regulatory body in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Myunghyun; Choi, Young Sung; Yi, Kyungjoo [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    Fukushima accident revealed not only licensees but also regulatory bodies' (RBs) establishment of robust safety culture (SC) is crucial to implement effective safety regulation. Result of the IAEA IRRS held in 2011 required regulatory body in Korea to make improvement measure for the enhancement of safety culture of regulatory body (SCRB). Compared to works done to assess SC focused on working organizations of nuclear industry, not enough attention has been paid to assess the RBs. To achieve this goal, long-term comprehensive drive plan has to be made. The IAEA is putting great effort to establish and enhance SC in RBs. OECD/NEA CNRA is planning to produce Green Booklet on SCRB for regulatory guidance. SCRB is an organization's culture, RBs ultimately has to possess in order to assure secure use of nuclear energy. An organization's culture emerges from, and is manifested in, the interplay of its members' emotion, cognition, attitudes, behaviors and interaction patterns. As a result of this mechanism, organizational structures and culture influence individual's attitude and behavior when entered into a situation. Each organization has its strengths and weakness in SC. Safety culture defective components of the Fukushima accident was analyzed by JNES in 2012. According to the casual factors indicated in the investigation report, Nuclear Regulatory Organizations (NROs) of Korea also had weakness of the SCRB in terms of questioning attitude, continuous learning, issue identification and resolution and safety leadership. It doesn't have to be same but necessary for both NSSC and KINS to be consistent in building SC traits to carry out a coherent policy with synergy effect. NROs should communicated and convey consistent message to the stakeholders. Not limited to development of SCRB itself, influence of SCRB on licensee's SC is recommended for further study. Also, what behaviors are expected to make positive effects and whether they can

  15. Seismic Observation in Deep Boreholes and Its Applications - Workshop Proceedings, Niigata Institute of Technology, Kashiwazaki, Japan

    International Nuclear Information System (INIS)

    2014-01-01

    4 was only 70% that of Unit 2 at the same site. Given these circumstances, JNES initiated the 'Observation and Evaluation Study of Ground Motion Amplification' project by drilling a three-kilometer deep borehole on the premises of the Niigata Institute of Technology, which is located near the Kashiwazaki site, and proposed a series of workshops related to deep underground seismic observation and ground motion evaluation to the Seismic Subgroup of the OECD/NEA/IAGE Group at the April 2010 meeting. The first was held from 24-26 November 2010 as part of the first Kashiwazaki International Symposium on seismic safety, and the second was held on 7 to 9 November 2012. In the second WS, 36 papers were presented by the participants from eight countries including two international organizations, and discussed in three sessions (i.e. observation technology, evaluation of the observed seismic motion and the multipurpose use). Regarding the observation technology session, useful lessons-learned in probe development, setup and maintenance under the challenging conditions posed by great depth were described. This information from SAFORD and Kashiwazaki was thought to be particularly valuable for the planning and operation of similar facilities. As for the seismic observations from a deep borehole, it was identified that such observations are very effective for investigation of the earthquake generating process and are important for detailed understanding of the three-dimensional underground structure. There is not yet much experience with observation and application of a deep borehole, and therefore future developments and achievements are expected. The importance of simple ground motion evaluation technology combined with geophysical exploration was also acknowledged. Examples of multipurpose utilization and the advantage of seismic observations in deep boreholes were discussed. Multipurpose use was discussed not only for seismic design and evaluation of nuclear installations

  16. NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark. Volume II: uncertainty and sensitivity analyses of void distribution and critical power - Specification

    International Nuclear Information System (INIS)

    Aydogan, F.; Hochreiter, L.; Ivanov, K.; Martin, M.; Utsuno, H.; Sartori, E.

    2010-01-01

    This report provides the specification for the uncertainty exercises of the international OECD/NEA, NRC and NUPEC BFBT benchmark problem including the elemental task. The specification was prepared jointly by Pennsylvania State University (PSU), USA and the Japan Nuclear Energy Safety (JNES) Organisation, in cooperation with the OECD/NEA and the Commissariat a l'energie atomique (CEA Saclay, France). The work is sponsored by the US NRC, METI-Japan, the OECD/NEA and the Nuclear Engineering Program (NEP) of Pennsylvania State University. This uncertainty specification covers the fourth exercise of Phase I (Exercise-I-4), and the third exercise of Phase II (Exercise II-3) as well as the elemental task. The OECD/NRC BFBT benchmark provides a very good opportunity to apply uncertainty analysis (UA) and sensitivity analysis (SA) techniques and to assess the accuracy of thermal-hydraulic models for two-phase flows in rod bundles. During the previous OECD benchmarks, participants usually carried out sensitivity analysis on their models for the specification (initial conditions, boundary conditions, etc.) to identify the most sensitive models or/and to improve the computed results. The comprehensive BFBT experimental database (NEA, 2006) leads us one step further in investigating modelling capabilities by taking into account the uncertainty analysis in the benchmark. The uncertainties in input data (boundary conditions) and geometry (provided in the benchmark specification) as well as the uncertainties in code models can be accounted for to produce results with calculational uncertainties and compare them with the measurement uncertainties. Therefore, uncertainty analysis exercises were defined for the void distribution and critical power phases of the BFBT benchmark. This specification is intended to provide definitions related to UA/SA methods, sensitivity/ uncertainty parameters, suggested probability distribution functions (PDF) of sensitivity parameters, and selected

  17. OECD/NRC Benchmark Based on NUPEC PWR Sub-channel and Bundle Test (PSBT). Volume I: Experimental Database and Final Problem Specifications

    International Nuclear Information System (INIS)

    Rubin, A.; Schoedel, A.; Avramova, M.; Utsuno, H.; Bajorek, S.; Velazquez-Lozada, A.

    2012-01-01

    microscopic data, which provide void distribution within a sub-channel. The NUPEC PSBT benchmark consists of two phases. Each phase consists of different exercises: Phase I - Void Distribution Benchmark: - Exercise 1 - Steady-state single sub-channel benchmark, - Exercise 2 - Steady-state bundle benchmark, - Exercise 3 - Transient bundle benchmark, - Exercise 4 - Pressure drop benchmark. Phase II - DNB Benchmark: - Exercise 1 - Steady-state fluid temperature benchmark, - Exercise 2 - Steady-state DNB benchmark, - Exercise 3 - Transient DNB benchmark. This report provides the specifications for the international OECD/NRC NUPEC PSBT benchmark problem. The specification report has been prepared jointly by the Pennsylvania State University (PSU), USA and the Japan Nuclear Energy Safety (JNES) Organisation, in co-operation with the US NRC and the NEA/OECD. The work is sponsored by the US NRC, METI-Japan, the NEA/OECD, and the Nuclear Engineering Programme (NEP) of Pennsylvania State University. The specifications cover the four exercises of Phase I, and the three exercises of Phase II

  18. IAEA Expert Team Completes Mission to Review Japan's Nuclear Power Plant Safety Assessment Process, 31 January 2012, Tokyo, Japan

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: A team of international nuclear safety experts today completed a review of Japan's two-stage process for assessing nuclear safety at the nation's nuclear power plants. The team began its work on 23 January and delivered a Preliminary Summary Report to Japanese officials today and plans to finish the final report by the end of February. National safety assessments and their peer review by the IAEA are a key component of the IAEA's Action Plan on Nuclear Safety, which was approved by the Agency's 152 Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. At the request of the Government of Japan, the International Atomic Energy Agency (IAEA) organized a 10-person team to review the Japanese Nuclear and Industrial Safety Agency's (NISA) approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. The IAEA safety review mission consisted of five IAEA and three international nuclear safety experts. To help its review, the team held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety (JNES) Organization, and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. 'We concluded that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, director of the IAEA's Nuclear Installation Safety Division. In its Preliminary Summary Report delivered today, the team highlighted a number of good practices and identified some improvements that would enhance the overall effectiveness of the Comprehensive Safety Assessment process. Good practices identified by the mission team include: Based on NISA instructions and commitments of the

  19. Preliminary findings and lessons learned from the 16 July 2007 earthquake at Kashiwazaki-Kariwa NPP - 'The Niigataken Chuetsu-Oki earthquake', Kashiwazaki-Kariwa NPP and Tokyo, Japan, 6-10 August 2007. Mission report. V. 2

    International Nuclear Information System (INIS)

    2007-01-01

    photographs are presented that give the impression of the way the mission was conducted and showing the atmosphere of the mission, such as the meetings and encounters with the media. The preparatory meeting held at the hotel in Nagaoke, upon arrival on Sunday, is portrayed in the first photograph. The arrival at Kashiwazaki-Kariwa NPP on Monday and the encounter with the media and the technical meetings at the plant are shown in the next three photographs. The interest of the media to this event is also shown in the next two photographs taken at the exit of the meetings in the plant and in Tokyo. In the last photograph the IAEA expert team is shown at the hotel after delivery of the draft mission report to Japanese authorities. Subsequently, Volume II is organized in the following way: 1. Part I: BACKGROUND. First of all, there is a significant amount of information provided by NISA, JNES and TEPCO as general background. This information mainly relates to Japanese regulations and general data about the Kashiwazaki-Kariwa NPP and does not pertain specifically to the 16 July 2007 event. All this information is presented under the title of 'Background' and it is not necessarily referenced to any particular discussion area of the mission. 2. Part II: INFORMATION SPECIFIC TO THE THREE AREAS COVERED BY THE MISSION AS SUPPLIED BY THE JAPANESE COUNTERPART. Secondly, there is information supplied by the Japanese counterpart as information specifically relevant to the purpose of the mission, that is, the 16 July 2007 Niigataken Chuetsu-oki earthquake and in general the plant response to this event. This information includes the presentations made by counterpart specialists at the beginning of the mission and also their response to the queries raised by the IAEA team members during the course of the mission. These presentations and the responses are presented under the three discussion areas A1, A2 and A3. If a presentation or response pertains to more than one area this is also

  20. Follow-up IAEA mission in relation to the findings and lessons learned from the 16 July 2007 earthquake at Kashiwazaki-Kariwa NPP - 'The Niigataken Chuetsu-oki earthquake', Tokyo and Kashiwazaki-Kariwa NPP, Japan, 28 January - 1 February 2008. Mission report. V. 1

    International Nuclear Information System (INIS)

    2008-01-01

    assessment - structures, systems and components response; and (3) fire safety. In general the preliminary findings and lessons learned that were reported in August 2007 were confirmed. Since August 2007 there has been a very significant amount of high quality work performed in all areas that were considered during the follow-up mission including the establishment of required regulations and the participation of recognized institutions in Japan in the area of earthquake engineering and nuclear safety. NISA, JNES, TEPCO and a large number of specialized institutions and universities as well as experts have performed activities relating to the evaluation, regulation and the review aspects of the situation of the plant after the earthquake. The participatory approach that has been chosen by NISA for the review framework provides for a transparent and consensus seeking process. The IAEA Safety Standards relating to seismic safety have already been very useful for the follow-up mission in identifying findings and lessons learned in the areas of the evaluation of seismic hazard and of the seismic response of structures, systems and components. The discussions with the Japanese counterpart confirmed that the IAEA Safety Standards can be used by NISA and TEPCO to address many of the specific findings that are detailed in Section 5 of this report. As example, in the area of seismic hazard evaluation making the adequate use of the IAEA Safety Standards will facilitate the process of integration and synthesis of the vast amount of available data. A change in the design ground motion to be used for the complete safety re-evaluation of the existing facility is to be expected after a strong earthquake that exceeds the original design basis. In that case it appears very important to properly evaluate the relevant capacity reserves of the plant systems, structures and components. That is possible through the use of realistic assumptions, methods, modelling and acceptance criteria in all

  1. Editorial

    Directory of Open Access Journals (Sweden)

    Zoran Velagić

    2015-06-01

    Full Text Available This issue of Libellarium features papers based on the presentations from the 2nd Publishing trends and contexts conference which took place in Pula, Croatia, on 8-9 December 2014. All papers were subject to evaluation and classification by two independent reviewers, according to the journal’s editorial policy. The conference gathered a group of experts from prominent European universities from England, France, Germany, Lithuania, Netherlands, Poland, Scotland, Sweden, Slovenia and Croatia–the details are available on the conference web site: http://epubconf.unizd.hr/hr/index.php. The papers published in this volume concentrate on four main problems: new possibilities for publishers, booksellers and authors caused by the introduction of digital technologies in the publishing processes, models used in the digital environment, teaching publishing at the university level, and finally, the status of publishing studies as an emerging scholarly discipline. The first part features five papers. Tom D. Wilson in E-books: the publishers’ dilemma reports on a study of publishers’ attitudes towards e-books in three countries: Sweden, Lithuania and Croatia, showing a great contrast between the rise of the e-book in English speaking countries and those of small languages. Elena Maceviciute, Birgitta Wallin and Kersti Nilsson (Book selling and e-books in Sweden address the issue of the understanding of the book-selling situation in Sweden, by answering three crucial questions: how Swedish booksellers see the impact of e-books on their business, how and why they adopt and develop e-book sales, and what they perceive as barriers to e-book selling. Interestingly, the results have shown that the Swedish booksellers do not feel their business is threatened by e-books. In E-book aggregators: new services in electronic publishing Tomislav Jakopec investigates e-book aggregators as new services in electronic publishing, showing that e-book aggregation exists