Last edited by Vomi
Tuesday, November 17, 2020 | History

2 edition of Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6 found in the catalog.

Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6

Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6

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Published by Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Supt. of Docs., U.S. G.P.O. [distributor in Washington, DC .
Written in English

    Subjects:
  • Pressurized water reactors -- Loss of coolant -- Computer simulation.

  • Edition Notes

    Statementprepared by T.S. Choi ... [et al.].
    SeriesInternational agreement report -- NUREG/IA-0139.
    ContributionsChoi, T. S., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., Korea Nuclear Fuel Company., Hanʼguk Wŏnjaryŏk Anjŏn Kisurwŏn. Advanced Reactor Dept.
    The Physical Object
    FormatMicroform
    Paginationvi, 68, 38 p.
    Number of Pages68
    ID Numbers
    Open LibraryOL18132845M

    Share My Lesson is committed to bringing educators classroom resources aligned to state standards, the Common Core State Standards and Next Generation Science Standards.5/5. 4 Grade 4 Worksheets and Activities that assess every standard! English Assessments C o r e C o m m o n S t a n d a r d s. c o m English Standards Math Standards Common CoreFile Size: 2MB. RL Distinguish their own point of view from that of the narrator or those of the characters. Strategy/Lesson Suggestions Formative Assessment Suggestions Student Friendly Point of View ct students on the differences in first and third person point of view at the followingFile Size: KB. Large perspective differences between images Dense matching method must be insensitive Increased overlap is beneficial (at least 75% along & across flight) Changing ground sampling distance in oblique imagery Point cloud generation using correspondences from dense matching must take ground sampling and intersection angles into.


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Assessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6 Download PDF EPUB FB2

Assessment of RELAP5/MOD Using LOFT Large Break LOCA Test, LP- 6 Prepared by T S. Choi, J. Lee, B. Park, C. Cho, J.Y. Park/KNFC Y. Bang, S. W Seul, H. Kim/KINS Korea Nuclear Fuel Company DogJin-Dong Yusong Gu, Daejeon City Korea Korea Institute of Nuclear Safety Advanced Reactor Dept.

P.O. Box Yusung, Taejon   The LOFT experiment LP was simulated using the RELAP5/MOD code to assess its capability to predict the thermal-hydraulic phenomena in LBLOCA of the PWR.

The reactor vessel was modeled with two core channels and split downcomer for a base calculation. Get this from a library. Assessment of RELAP5/MOD using LOFT large break LOCA test, LP [T S Choi; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.; Korea Nuclear Fuel Company.; Han'guk Wŏnjaryŏk Anjŏn Kisurwŏn.

Advanced Reactor Department.;]. Get this from a library. Assessment of RELAP5/MOD using LOFT large break LOCA test, LP [T S Choi; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research,]. Assessment of RELAP5/MOD Using LOFT Large Break International Agreement Report NUREG/IA International Agreement Report Assessment of RELAP5/MOD Using LOFT Large Break LOCA Test, LP- 6 Prepared by T S.

Choi, J. Lee, B. Park, C. Cho, J.Y. Park/KNFC Y. Bang, S. W Seul, H. Kim/KINS Korea Nuclear Fuel Company DogJin-Dong Yusong Gu. @article{osti_, title = {Assessment of RELAP5/MOD using loft L, L, L, LP, and LP-LB-1}, author = {Ban, Chang-Hwan and Chung, Bub-Dong and Hwang, Sun-Tack}, abstractNote = {The capability of RELAP5/MOD to predict overall loss-of-coolant-accident (LOCA) thermal-hydraulic phenomena was assessed using loss-of-fluid test (LOFT) large-break loss-of-coolant experiment data.

Thermal-hydraulic post-test analysis of OECD LOFT LP-FP-2 experiment [microform] / prepared by J.J. Pena Assessment of RELAP5/MOD using LOFT large break LOCA test, LP [microform] / prepared by T.S.

Cho. RELAP5/MOD Assessment Using INSC SP-PSBV1. Using a smaller break based on investigations of local thermal-hydraulic parameters in the fuel rod imitators assembly at the large-scale test.

Experimental Study of Small and Medium Break LOCA in the TTL-2 Thermo-Hydraulic Test Loop and Its Modeling with RELAP5/MOD Code M. Taherzadeh1;, J. Jafari2, N. Vosoughi1 and H.

Arabnezhad1 Abstract. Small and medium break LOCA accidents at low pressure and under low velocity conditionsAuthor: M Taherzadeh, J Jafari, N Vosoughi, H Arabnezhad. Some experimental data on PWR IBLOCAs have been obtained by using such integral test facilities as LOFT in the US (Nalezny, ), LOBI in Italy (Addabbo and Annunziato, ), and PSB-VVER in Russia (Del Nevo et al., ).

The obtained data, however, would be insufficient to clarify specific thermal-hydraulic responses due to such atypical Cited by: 2. Based on the assessment results presented in Section 3, the method was applied to the analysis of a LBLOCA of the LOFT facility, namely the LP–6 test, to verify the applicability of the method to the nuclear systems.

B.S. Park, et ment of RELAP5/MOD Using LOFT Large Break LOCA Test, LP Nuclear Regulatory Author: Qingwen Xiong, Junli Gou, Yan Wen, Jianqiang Shan.

Experimental study of small and medium break LOCA in the TTL-2 thermo-hydraulic test loop and its modeling with RELAP5/MOD code November Scientia Iranica 17(6).

Experiment LP was conducted on October 3, It was the first large-break loss-of-coolant accident (LOCA) simulation and the fourth experiment at all conducted in the Loss-Of-Fluid-Test (LOFT) facility at the Idaho National Engineering Laboratory under the auspicies of the OECD.

RELAPD is a simulation tool that allows users to model the coupled behavior of the reactor coolant system and the core for various operational transients and postulated accidents that might occur in a nuclear (Reactor Excursion and Leak Analysis Program) can be used for reactor safety analysis, reactor design, simulator training of operators, and as an educational tool by License: Proprietary.

Assessment of RELAP5/MOD using LOFT large break LOCA test, LP / by: Choi, T. S., Published: () Potential degradation of post loss-of-coolant recirculation capability as a result of debris Published: (). Describe a Story Element in Depth RL / RL - Activities for teaching Reading: Literature, including Reading: Literature worksheets, Reading: Literature practice, questions, assessments, quizzes, tests, lesson plans - aligned to Common Core and state standards - Goalbook Pathways.

Assessment of RELAP5/MOD using LOFT large break LOCA test, LP / by: Choi, T. S., Published: () Assessment of RELAP5/MOD with the semiscale natural circulation experiment, S-NC-8B / by: Bang, Y.

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A ROSA/LSTF experiment was conducted for OECD/NEA ROSA Project simulating a PWR loss-of-feedwater (LOFW) transient with specific assumptions of failure of scram that may cause natural circulation with high core power and total failure of high pressure injection system. Auxiliary feedwater (AFW) was provided to well observe the long-term high-power natural by: RELAP5/MOD2 analysis of LOFT experiment L (SuDoc Y 3.N /) Unknown Binding – January 1, by M.

Keevill (Author) See all formats and editions Hide other formats and editions. Enter your mobile number or email address below and we'll send you Author: M. Keevill. This report presents the results of the RELAP5/MOD3 Version 7j assessment on BETHSY TC. BETHSY TC test corresponding to a six inch cold leg break LOCA of the Pressurizer Water Reactor(PWR).

The primary objective of the test was to provide reference data of two facilities of different scales (BETHSY and LSTF facility). On the other hand, the present calculation aims at analysis of Author: Young-Jong Chung, Jae-Jun Jeong, Won-Pyo Chang, Dong-Su Kim.

Sunergos Milk Training Video: Learn Milk Science, Steaming, and Latte Art - Duration: Sunergos Coffee Recommended for you. A test condition was similar to TMLB’ scenario but with AFW actuation to well observe two-phase natural circulation under high core power for relatively long time.

The core power curve for the LSTF experiment was obtained by analysis for PWR LOFW transient without scram using RELAP5/MOD3. Publisher: Elsevier; Assessment of the COBRA/RELAP5 code using the LOFT L large-break loss-of-coolant experiment The RELAP5/modg was applied for the post-test analysis of the small break loss of coolant experiment performed on the PMK-2 facility.

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