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Monday, July 27, 2020 | History

3 edition of Assessment study of RELAP5/MOD2 against IVO loop seal tests found in the catalog.

Assessment study of RELAP5/MOD2 against IVO loop seal tests

Assessment study of RELAP5/MOD2 against IVO loop seal tests

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Published by U.S. Nuclear Regulatory Commission, Supt. of Docs., U.S. G.P.O., [distributor], National Technical Information Service [distributor in Washington, DC, Springfield, VA .
Written in English

    Subjects:
  • Pressurized water reactors -- Safety measures -- Simulation methods.,
  • Pressurized water reactors -- Control.,
  • Nuclear power plants -- Finland.

  • Edition Notes

    Statementprepared by O. Kyma la inen.
    SeriesInternational agreement report -- NUREG/IA-0082.
    ContributionsImatran Voima Osakeyhtio ., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
    The Physical Object
    FormatMicroform
    Paginationvii, 25, 3 p.
    Number of Pages25
    ID Numbers
    Open LibraryOL14705421M

    Thermal-Hydraulic Phenomena - J   NENE Jamova cesta 39 SI Ljubljana Slovenia T: + 1 53 31 F: + 1 53 Its purpose was the assessment of aerosol retention in case of a core damage combined with a spontaneous or induced steam generator tube rupture. Long term station blackout analyses of two loop PWR using RELAP5/MOD Andrej Prošek, Leon Cizelj

      The inactive loop is assumed to have de-borated water in the loop seal having a volume consistent with the system geometry. This transient is representative of transients originated by the presence of boron in the primary loop (see also the SBLOCA-ATWS, below).   4. Probabilistic Safety Assessment as Part of an Environmental Impact Study for the NPP Borssele, EPZ Project Modifications Report , Rev. 0, September 5. Dodewaard PSA-2, KEMA & SAIC, restricted use 6. M. Khatib-Rahbar et al. A Regulatory Evaluation of the Mühleberg PSA, Part I: Level 1, ERI/HSK , HSK 11/, Volume I, April

      What have we been doing? Computer simulation is a method of performing experiments without costly hardware. To be in this business, you need to become a very good experimentalist. Always remember that your experiments are performed in virtual worlds where the physical laws may be close to those of the real world, but never really &  Web view.   October No SuDoc Number Title Year Item Number Internet Access; 1: Assessment study of RELAP5/MOD2 against 25 dryout experiments conducted at the Royal Institute of Technology / Assessment study of RELAP5/MOD2 cycle based on pressurizer safety and relief valve tests /


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Assessment study of RELAP5/MOD2 against IVO loop seal tests Download PDF EPUB FB2

Get this from a library. Assessment study of RELAP5/MOD2 against IVO loop seal tests. [O Kymäläinen; Imatran Voima Osakeyhtiö.; U.S. Nuclear Regulatory Commission. Office   RELAP5/MOD2 Assessment, OECD-LOFT Small Break Experiment LP-SB Prepared by S.

Guntay Paul Scherrer Institute CH Wurenlingen, Switzerland Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC April Prepared as part of The Agreement on Research Participation and Technical Exchange   @article{osti_, title = {RELAP5 assessment: LOFT large break L}, author = {Thompson, S L and Kmetyk, L N}, abstractNote = {RELAP5 is part of an effort to determine the ability of various systems codes to predict the detailed thermal/hydraulic response of LWRs during accident and off-normal conditions.

The RELAP5 code is being assessed at SNLA against test data from various Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera nuclear station / by: Arroyo, R., et al. Published: () Assessment of RELAP5-MOD Code for the IAEA SPE-4 Experiment.

the primary pressure fell slightl y A n e x i s ti n g R E L A P 5 / MOD2 model, COLLAPSED LEVEL IN HOT LEG ://   Home; Thermal reactor safety assessment; RELAP5/MOD2 analysis of LSTF SB-CL counterpart experiment scenario applied to NPP Krsko   @article{osti_, title = {Posttest RELAP5 simulations of the Semiscale S-UT series experiments.

[PWR]}, author = {Leonard, M T}, abstractNote = {The RELAP5/MOD1 computer code was used to perform posttest calculations, simulating six experiments, run in the Semiscale Mod-2A facility, investigating the effects of upper head injection on small break transient :// Assessment of RELAP5/MOD2 Against Critical Flow Data From Marviken Tests JIT 11 and CFT NUREG/IA Assessment Study of RELAP-5 MOD-2 Cycle Based on the DOEL-2 Steam Generator Tube Rupture Incident of June How do rom and rom chips used in refrigerator.

Why were knights willing to fight for their lords. Who is khalifa mother and wife name same. What are the Foolproof Module 14 Test Answers Generally, the applications of the FFTBM methodology are performed for 20–25 time trends.

In the present case 23 time trends were selected for accuracy quantification of BETHSY TC experiment (Hrvatin et al., ).Some trends are shown in Fig.

4 together with calculated average amplitudes to show relation between discrepancy and quantitative ://   studies of the tests used for uncertainty analyses are the third need for the assessment of safety.

Achievements from scaling studies Scaling has been an established subject in nuclear-reactor technology at the time of writing the current   NENE Jamova cesta 39 SI Ljubljana Slovenia T: + 1 53 02 contact the author(s) or refer to the Book of Abstracts for the correct version.

The content of abstracts is the responsibility of the authors concerned. This activity is included as a complementary study of the joint efforts of CNAT and ISIRYM in the study of the The PMK-2 experimental facility at the KFKI-AEKI, Budapest, is a full pressure, scaled down model of the primary and partly the secondary circuit of the Paks NPP, which is equipped with four VVER National Treasure: A Gates Family Mystery Changing Tides, Disney Book Group, Catherine Hapka, Disney Storybook Art Team The Application of Cathare 1 V to Lobi Small Break Loca Experiments and a Comparison with Relap5/Mod2 - Final Report, F.

D'Auria, G.M. Galassi Hity tygodnia dokupisz extra dodatki do zestawu dzieci gotują kuchnie świata. Polski film swiety interes sklep dziecięcy w Kłodawie Powiedziałam Ci, że sklep dla dzieci Eden na Nizinie Staropruskiej ma w asortymencie angry birds na słabsze telefony oraz RES Assessment Reports — — — — —, RPSB, “Containment/RCS Analysis of a Large-Break Loss-of-Coolant Accident in the AP Using RELAP5/MOD3,” August Regulatory Guides — — — — —, RG“Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized   Comparative study of current transients in HPHT and CVD diamond capacitor-sensors Review - Carrier lifetime spectroscopy for defect characterisation in semiconductor materials and devices Study of charge carrier transport in GaN sensors Study of neutron irradiated structures of ammonothermal GaN LMT-K   Web view.

Integral tests are carried out in scaled test facilities and provide data on the overall behavior of a simulated reactor system during an LOCA or transient. These tests are being used for code assessment purposes relating to overall reactor behavior.

A definition of sets of such tests (matrices) has been provided in OECD/NEA (). These This banner text can have markup.

web; books; video; audio; software; images; Toggle navigation    USNRC, "The Marviken Full Scale Critical Flow Tests, Summary Report," (Joint Reactor Safety Experiments in the Marviken Power Sta tion, Sweden), NUREG/CR, May M. Reocreux, "Contribution to the Study of Two-Phase  › 百度文库 › 互联网.

Study on Thermal Striping at UIS of Advanced Loop Type Fast Reactor: Water Experiment Using a 1/3 Scale 60 Degree Sector Model Jun Kobayashi, Nobuyuki Kimura, Akira Tobita, Hideki Kamide, Osamu Watanabe, Kazuhiro Ohyama  tk-i-mod2-z3 mod tk-s-cpsysop - system ferguson waterworks-muni 2" threaded gate valve 2" x 12" brass nipple fulkerson's plumbing co.

fire station 1 - clogg fullers tire inc. p/55r17 police tire p/55r17 tires g & k services mat rental uniform rental shop ?id=  Web view. B Assessment of Tests With Non-Critical Flow This section discusses the analytical predictions and test observations for the five assessed tests which were determined not to have critical flow.

Nitrogen is not injected into the test piping for Test Test does not run with this version of